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Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Documented Safety Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Documented Safety Analysis Documented Safety Analysis FUNCTIONAL AREA GOAL: A document that provides an adequate description of the hazards of a facility during its design, construction, operation, and eventual cleanup and the basis to prescribe operating and engineering controls through Technical Safety Requirements (TSR) or Administrative Controls (AC). REQUIREMENTS:  10 CFR 830.204, Nuclear Safety Rule  DOE-STD-1027-92, Hazard Categorization, 1992.  DOE-STD-1104-96, Change Notice 1, Review and Approval of Nuclear Facility Safety Basis Documents (documented Safety Analyses and Technical Safety Requirements), dated May 2002.  DOE-STD-3009-2002, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, Change Notice No. 2, April 2002.

2

Using Addenda in Documented Safety Analysis Reports  

Science Conference Proceedings (OSTI)

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

Douglas S. Swanson; Michael A. Thieme

2003-06-01T23:59:59.000Z

3

Using Addenda in Documented Safety Analysis Reports  

Science Conference Proceedings (OSTI)

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

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

2003-06-16T23:59:59.000Z

4

Review of Documented Safety Analysis Development for the Hanford...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

U.S. Department of Energy Subject: Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immob ilization Plant (LBL Facilities) - C riteria and...

5

CRAD, Documented Safety Analysis Development - April 23, 2013 | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Documented Safety Analysis Development - April 23, 2013 Documented Safety Analysis Development - April 23, 2013 CRAD, Documented Safety Analysis Development - April 23, 2013 April 23, 2013 Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immobilization Plant (LBL Facilities) (HSS CRAD 45-58, Rev. 0) The review will consider selected aspects of the development of the Documented Safety Analysis (DSA) for the Waste Treatment and Immobilization Plant (WTP); Low Activity Waste (LAW) facility, Balance of Facilities and Analytical Laboratory (LAB) (collectively identified as LBL) to assess the extent to which nuclear safety is integrated into the design of the LBL facilities in accordance with DOE directives; in particular, DOE Order 420. l B and DOE-STD-3009-94. The review will focus on a few selected

6

SNF fuel retrieval sub project safety analysis document  

SciTech Connect

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

BERGMANN, D.W.

1999-02-24T23:59:59.000Z

7

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

Science Conference Proceedings (OSTI)

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

Brown, Tulanda

2003-06-01T23:59:59.000Z

8

Safety Evaluation Report of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis  

Science Conference Proceedings (OSTI)

This Safety Evaluation Report (SER) documents the Department of Energys (DOE's) review of Revision 9 of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis, DOE/WIPP-95-2065 (WIPP CH DSA), and provides the DOE Approval Authority with the basis for approving the document. It concludes that the safety basis documented in the WIPP CH DSA is comprehensive, correct, and commensurate with hazards associated with CH waste disposal operations. The WIPP CH DSA and associated technical safety requirements (TSRs) were developed in accordance with 10 CFR 830, Nuclear Safety Management, and DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports.

Washington TRU Solutions LLC

2005-09-01T23:59:59.000Z

9

K West integrated water treatment system subproject safety analysis document  

Science Conference Proceedings (OSTI)

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

SEMMENS, L.S.

1999-02-24T23:59:59.000Z

10

TA-55 Final Safety Analysis Report Comparison Document and DOE Safety Evaluation Report Requirements  

Science Conference Proceedings (OSTI)

This document provides an overview of changes to the currently approved TA-55 Final Safety Analysis Report (FSAR) that are included in the upgraded FSAR. The DOE Safety Evaluation Report (SER) requirements that are incorporated into the upgraded FSAR are briefly discussed to provide the starting point in the FSAR with respect to the SER requirements.

Alan Bond

2001-04-01T23:59:59.000Z

11

Planning Document for an NBSR Conversion Safety Analysis Report  

SciTech Connect

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

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

2013-09-25T23:59:59.000Z

12

Documented Safety Analysis for the B695 Segment  

SciTech Connect

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

Laycak, D

2008-09-11T23:59:59.000Z

13

Documented Safety Analysis for the Waste Storage Facilities March 2010  

SciTech Connect

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

Laycak, D T

2010-03-05T23:59:59.000Z

14

Documented Safety Analysis for the Waste Storage Facilities  

Science Conference Proceedings (OSTI)

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

Laycak, D

2008-06-16T23:59:59.000Z

15

Acceptable NSLS Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Acceptable NSLS Safety Documentation Print NSLS users who have completed NSLS Safety Module must present a copy of one of the following documents to receive ALS 1001: Safety at the...

16

Generic safety documentation model  

SciTech Connect

This document is intended to be a resource for preparers of safety documentation for Sandia National Laboratories, New Mexico facilities. It provides standardized discussions of some topics that are generic to most, if not all, Sandia/NM facilities safety documents. The material provides a ``core`` upon which to develop facility-specific safety documentation. The use of the information in this document will reduce the cost of safety document preparation and improve consistency of information.

Mahn, J.A.

1994-04-01T23:59:59.000Z

17

Processing Exemptions to Nuclear Safety Rules and Approval of Alternative Methods for Documented Safety Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

STD-1083-2009 STD-1083-2009 June 2009 DOE STANDARD PROCESSING EXEMPTIONS TO NUCLEAR SAFETY RULES AND APPROVAL OF ALTERNATIVE METHODS FOR DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web Page at http://www.hss.energy.gov/nuclearsafety/techstds DOE-STD-1083-2009 iii FOREWORD 1. This Department of Energy (DOE) Standard has been prepared by the Office of Quality Assurance Policy and Assistance to provide acceptable processes for: a. requesting and granting exemptions to DOE nuclear safety rules and b. requesting and approving alternate methodologies for documented safety analyses

18

CFAST Computer Code Application Guidance for Documented Safety Analysis, Final Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Final CFAST Code Guidance Final CFAST Code Guidance CFAST Computer Code Application Guidance for Documented Safety Analysis Final Report U.S. Department of Energy Office of Environment, Safety and Health 1000 Independence Ave., S.W. Washington, DC 20585-2040 July 2004 DOE/NNSA-DP Technical Report CFAST Computer Code Application Guidance Final Report July 2004 ii INTENTIONALLY BLANK. DOE/NNSA-DP Technical Report CFAST Computer Code Application Guidance Final Report July 2004 iii FOREWORD This document provides guidance to Department of Energy (DOE) facility analysts in the use of the CFAST computer software for supporting Documented Safety Analysis applications. Information is provided herein that supplements information found in the CFAST documentation

19

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

20

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

22

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

23

SSC Safety Review Document  

Science Conference Proceedings (OSTI)

The safety strategy of the Superconducting Super Collider (SSC) Central Design Group (CDG) is to mitigate potential hazards to personnel, as far as possible, through appropriate measures in the design and engineering of the facility. The Safety Review Document identifies, on the basis of the Conceptual Design Report (CDR) and related studies, potential hazards inherent in the SSC project independent of its site. Mitigative measures in the design of facilities and in the structuring of laboratory operations are described for each of the hazards identified.

Toohig, T.E. [ed.

1988-11-01T23:59:59.000Z

24

Canister storage building (CSB) safety analysis report phase 3: Safety analysis documentation supporting CSB construction  

Science Conference Proceedings (OSTI)

The Canister Storage Building (CSB) will be constructed in the 200 East Area of the U.S. Department of Energy (DOE) Hanford Site. The CSB will be used to stage and store spent nuclear fuel (SNF) removed from the Hanford Site K Basins. The objective of this chapter is to describe the characteristics of the site on which the CSB will be located. This description will support the hazard analysis and accident analyses in Chapter 3.0. The purpose of this report is to provide an evaluation of the CSB design criteria, the design's compliance with the applicable criteria, and the basis for authorization to proceed with construction of the CSB.

Garvin, L.J.

1997-04-28T23:59:59.000Z

25

Final safety analysis report for the Galileo Mission: Volume 1, Reference design document  

SciTech Connect

The Galileo mission uses nuclear power sources called Radioisotope Thermoelectric Generators (RTGs) to provide the spacecraft's primary electrical power. Because these generators contain nuclear material, a Safety Analysis Report (SAR) is required. A preliminary SAR and an updated SAR were previously issued that provided an evolving status report on the safety analysis. As a result of the Challenger accident, the launch dates for both Galileo and Ulysses missions were later rescheduled for November 1989 and October 1990, respectively. The decision was made by agreement between the DOE and the NASA to have a revised safety evaluation and report (FSAR) prepared on the basis of these revised vehicle accidents and environments. The results of this latest revised safety evaluation are presented in this document (Galileo FSAR). Volume I, this document, provides the background design information required to understand the analyses presented in Volumes II and III. It contains descriptions of the RTGs, the Galileo spacecraft, the Space Shuttle, the Inertial Upper Stage (IUS), the trajectory and flight characteristics including flight contingency modes, and the launch site. There are two appendices in Volume I which provide detailed material properties for the RTG.

Not Available

1988-05-01T23:59:59.000Z

26

Preliminary Safety Assessment Document  

NLE Websites -- All DOE Office Websites (Extended Search)

LCSAD-001, Ver. 2 LCSAD-001, Ver. 2 Linac Commissioning Safety Assessment Document for the National Synchrotron Light Source II Photon Sciences Directorate Version 2 May 11, 2011 Prepared by Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 managed by Brookhaven Science Associates for the U.S. Department of Energy Office of Science Basic Energy Science under contract DE-AC02-98CD10886 ii National Synchrotron Light Source II ii LT-C-ESH-LCSAD-001 ii DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any

27

Preliminary Safety Assessment Document  

NLE Websites -- All DOE Office Websites (Extended Search)

BCSAD-001 BCSAD-001 Photon Sciences Directorate Booster Commissioning Safety Assessment Document For the National Synchrotron Light Source II Version 2 December 8, 2011 Prepared by Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 managed by Brookhaven Science Associates for the U.S. Department of Energy Office of Science Basic Energy Science under contract DE-AC02-98CD10886 ii National Synchrotron Light Source II Photon Sciences Directorate ii DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any

28

Final safety analysis report for the Galileo Mission: Volume 2, Book 2: Accident model document: Appendices  

Science Conference Proceedings (OSTI)

This section of the Accident Model Document (AMD) presents the appendices which describe the various analyses that have been conducted for use in the Galileo Final Safety Analysis Report II, Volume II. Included in these appendices are the approaches, techniques, conditions and assumptions used in the development of the analytical models plus the detailed results of the analyses. Also included in these appendices are summaries of the accidents and their associated probabilities and environment models taken from the Shuttle Data Book (NSTS-08116), plus summaries of the several segments of the recent GPHS safety test program. The information presented in these appendices is used in Section 3.0 of the AMD to develop the Failure/Abort Sequence Trees (FASTs) and to determine the fuel releases (source terms) resulting from the potential Space Shuttle/IUS accidents throughout the missions.

Not Available

1988-12-15T23:59:59.000Z

29

Style, content and format guide for writing safety analysis documents. Volume 1, Safety analysis reports for DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of Volume 1 of this 4-volume style guide is to furnish guidelines on writing and publishing Safety Analysis Reports (SARs) for DOE nuclear facilities at Sandia National Laboratories. The scope of Volume 1 encompasses not only the general guidelines for writing and publishing, but also the prescribed topics/appendices contents along with examples from typical SARs for DOE nuclear facilities.

Not Available

1994-06-01T23:59:59.000Z

30

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

SciTech Connect

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

Fisk, Patricia; Rutherford, Lavon

2003-06-01T23:59:59.000Z

31

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

NLE Websites -- All DOE Office Websites (Extended Search)

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

32

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

33

Final safety analysis report for the Galileo Mission: Volume 2: Book 1, Accident model document  

SciTech Connect

The Accident Model Document (AMD) is the second volume of the three volume Final Safety Analysis Report (FSAR) for the Galileo outer planetary space science mission. This mission employs Radioisotope Thermoelectric Generators (RTGs) as the prime electrical power sources for the spacecraft. Galileo will be launched into Earth orbit using the Space Shuttle and will use the Inertial Upper Stage (IUS) booster to place the spacecraft into an Earth escape trajectory. The RTG's employ silicon-germanium thermoelectric couples to produce electricity from the heat energy that results from the decay of the radioisotope fuel, Plutonium-238, used in the RTG heat source. The heat source configuration used in the RTG's is termed General Purpose Heat Source (GPHS), and the RTG's are designated GPHS-RTGs. The use of radioactive material in these missions necessitates evaluations of the radiological risks that may be encountered by launch complex personnel as well as by the Earth's general population resulting from postulated malfunctions or failures occurring in the mission operations. The FSAR presents the results of a rigorous safety assessment, including substantial analyses and testing, of the launch and deployment of the RTGs for the Galileo mission. This AMD is a summary of the potential accident and failure sequences which might result in fuel release, the analysis and testing methods employed, and the predicted source terms. Each source term consists of a quantity of fuel released, the location of release and the physical characteristics of the fuel released. Each source term has an associated probability of occurrence. 27 figs., 11 tabs.

Not Available

1988-12-15T23:59:59.000Z

34

Preparation Guide for U. S. Department of Energy Nonreator Nuclear Facility Document Safety Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SENSITIVE DOE-STD-3009-94 July 1994 CHANGE NOTICE NO. 1 January 2000 CHANGE NOTICE NO. 2 April 2002 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS TS This document has been reproduced directly 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 U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161;

35

Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-3009-94 July 1994 CHANGE NOTICE NO. 12 January 2000 5 December 24 April 20021 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSISANALYSES REPORTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced directly 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 U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161;

36

Reactor operation safety information document  

Science Conference Proceedings (OSTI)

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

Not Available

1990-01-01T23:59:59.000Z

37

Light-Weight Radioisotope Heater Unit Final Safety Analysis Report (LWRHU FSAR): Volume 3, Nuclear Risk Analysis Document  

SciTech Connect

The Light-Weight Radioisotope Heater Unit (LWRHU) Final Safety Analysis Report (FSAR), Volume 2, Accident Model Document (AMD) describes potential accident scenarios during the Galileo mission and evaluates the response of the LWRHUs to the associated accident environments. Any resulting source terms, consisting of PuO2 (with Pu-238 the dominant radionuclide), are then described in terms of curies released, particle size distribution, release location, and probabilities. This volume (LWRHU-FSAR, Volume 3, Nuclear Risk Analysis Document (NRAD)) contains the radiological analyses which estimate the consequences of the accident scenarios described in the AMD. It also contains the quantification of mission risks resulting from the LWRHUs based on consideration of all accident scenarios and their probabilities. Estimates of source terms and their characteristics derived in the AMD are used as inputs to the analyses in the NRAD. The Failure Abort Sequence Trees (FASTs) presented in the AMD define events for which source terms occur and quantify them. Based on this information, three types of source term cases (most probable, maximum, and expectation) for each mission phase were developed for use in evaluating the radiological consequences and mission risks. 4 refs., 5 figs., 8 tabs.

Not Available

1988-11-30T23:59:59.000Z

38

Documents: Cost Analysis  

NLE Websites -- All DOE Office Websites (Extended Search)

Analysis Search Documents: Search PDF Documents View a list of all documents Cost Analysis PDF Icon Summary of the Cost Analysis Report for the Long-term Management of Depleted UF6...

39

Safety and Emergency Management Evaluations - Guidance Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Guidance Documents Guidance Documents Safety and Emergency Management Evaluations Office Protocols Office of Safety and Emergency Management Evaluations Protocol for the Development and Maintenance of Criteria and Review Approach Documents, July 2013 Office of Safety and Emergency Management Evaluations Protocol for High Hazard Nuclear Facility Project Oversight, November 2012 Office of Safety and Emergency Management Evaluations Protocol for Required Reading, June 2012 Office of Safety and Emergency Management Evaluations Protocol for Small Team Oversight Activities, June 2012 (Rev. 1) Office of Safety and Emergency Management Evaluations Qualification Standard for the Site Lead Program, May 2011 Office of Safety and Emergency Management Evaluations Protocol for Site Leads, May 2011

40

Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immobilization Plant (LBL Facilities), April 23, 2013 (HSS CRAD 45-58, Rev. 0)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

U.S. Department of U.S. Department of Energy Subject: Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immob ilization Plant (LBL Facilities) - C riteria and Review Approach D oc um~ HS: HSS CRAD 45-58 Rev: 0 Eff. Date: April 23, 2013 Office of Safety and Emergency Management Evaluations Acting Di rec or, Office of Safety and Emergency Nltanagement Evaluations Date: Apri l 23 , 20 13 Criteria and Review Approach Document ~~ trd,James Low Date: April 23 , 20 13 1.0 PURPOSE Within the Office of H.ealth, Safety and Security (HSS), the Office of Enforcement and Overs ight, Office of Safety and Emergency Management Evaluations (HS-45) miss io n is to assess the effectiveness of the environment, safety, health, and emergency management systems and practices used by line and

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Review and Approval of Nuclear Facility Safety Basis Documents (Documented Safety Analyses and Technical Safety Requirements)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

February 1996 February 1996 CHANGE NOTICE NO. 2 Date November 2005 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly 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 U.S. Department of Commerce, Technology Adminis tration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000.

42

Transportation Safety Excellence in Operations Through Improved Transportation Safety Document  

Science Conference Proceedings (OSTI)

A recent accomplishment of the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Nuclear Safety analysis group was to obtain DOE-ID approval for the inter-facility transfer of greater-than-Hazard-Category-3 quantity radioactive/fissionable waste in Department of Transportation (DOT) Type A drums at MFC. This accomplishment supported excellence in operations through safety analysis by better integrating nuclear safety requirements with waste requirements in the Transportation Safety Document (TSD); reducing container and transport costs; and making facility operations more efficient. The MFC TSD governs and controls the inter-facility transfer of greater-than-Hazard-Category-3 radioactive and/or fissionable materials in non-DOT approved containers. Previously, the TSD did not include the capability to transfer payloads of greater-than-Hazard-Category-3 radioactive and/or fissionable materials using DOT Type A drums. Previous practice was to package the waste materials to less-than-Hazard-Category-3 quantities when loading DOT Type A drums for transfer out of facilities to reduce facility waste accumulations. This practice allowed operations to proceed, but resulted in drums being loaded to less than the Waste Isolation Pilot Plant (WIPP) waste acceptance criteria (WAC) waste limits, which was not cost effective or operations friendly. An improved and revised safety analysis was used to gain DOE-ID approval for adding this container configuration to the MFC TSD safety basis. In the process of obtaining approval of the revised safety basis, safety analysis practices were used effectively to directly support excellence in operations. Several factors contributed to the success of MFCs effort to obtain approval for the use of DOT Type A drums, including two practices that could help in future safety basis changes at other facilities. 1) The process of incorporating the DOT Type A drums into the TSD at MFC helped to better integrate nuclear safety requirements with waste requirements. MFCs efforts illustrate that utilizing the requirements of other disciplines, beyond nuclear safety, can provide an efficient process. Analyzing current processes to find better ways of meeting the requirements of multiple disciplines within a safety basis can lead to a more cost-effective, streamlined process. 2) Incorporating the DOT Type A drums into the MFC TSD was efficient because safety analysts utilized a transportation plan that provided analysis that could also be used for the change to the TSD addendum. In addition, because the plan they used had already been approved and was in use by the Idaho Cleanup Project (ICP) at the INL, justification for the change to the TSD was more compelling. MFC safety analysts proved that streamlining a process can be made more feasible by drawing from analysis that has already been completed.

Dr. Michael A. Lehto; MAL

2007-05-01T23:59:59.000Z

43

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enforcement » Nuclear Safety Enforcement Documents Enforcement » Nuclear Safety Enforcement Documents Nuclear Safety Enforcement Documents Documents Available for Download July 22, 2013 Enforcement Letter, NEL-2013-03 Issued to Lawrence Livermore National Security, LLC related to Programmatic Deficiencies in the Software Quality Assurance Program at the Lawrence Livermore National Laboratory February 12, 2013 Enforcement Letter, NEL-2013-02 Issued to Los Alamos National Security, LLC related to a Radiological Contamination Event at the Los Alamos Neutron Science Center at Los Alamos National Laboratory January 7, 2013 Enforcement Letter, NEL-2013-01 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant October 23, 2012 Enforcement Letter, Controlled Power Company - WEL-2012-02

44

Final safety analysis report for the Galileo mission: Volume 3 (Book 2), Nuclear risk analysis document: Appendices: Revision 1  

DOE Green Energy (OSTI)

It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with if there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. Book 2 contains eight appendices.

Not Available

1989-01-25T23:59:59.000Z

45

Final safety analysis report for the Galileo mission: Volume 3 (Book 1), Nuclear risk analysis document: Revision 1  

DOE Green Energy (OSTI)

It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with if there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. 4 refs., 11 figs., 31 tabs.

Not Available

1989-01-13T23:59:59.000Z

46

Safety Basis Criteria & Review Approach Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Basis Criteria & Review Approach Documents Safety Basis Criteria & Review Approach Documents Safety Basis Criteria & Review Approach Documents Documents Available for Download CRAD, Safety Basis - Idaho MF-628 Drum Treatment Facility CRAD, Safety Basis - Idaho Accelerated Retrieval Project Phase II CRAD, Safety Basis - Los Alamos National Laboratory TA 55 SST Facility CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion Facility

47

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation  

Science Conference Proceedings (OSTI)

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

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

2000-03-23T23:59:59.000Z

48

K Basin safety analysis  

DOE Green Energy (OSTI)

The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

Porten, D.R.; Crowe, R.D.

1994-12-16T23:59:59.000Z

49

Occupational Safety & Health Criteria & Review Approach Documents |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Occupational Safety & Health Criteria & Review Approach Documents Occupational Safety & Health Criteria & Review Approach Documents Occupational Safety & Health Criteria & Review Approach Documents Documents Available for Download CRAD, Occupational Safety & Health - Idaho MF-628 Drum Treatment Facility CRAD, Occupational Safety & Health - Idaho Accelerated Retrieval Project Phase II CRAD, Occupational Safety & Health - Los Alamos National Laboratory TA 55 SST Facility CRAD, Occupational Safety & Health - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR

50

Light-Weight Radioisotope Heater Unit final safety analysis report (LWRHU-FSAR): Volume 2: Accident Model Document (AMD)  

Science Conference Proceedings (OSTI)

The purpose of this volume of the LWRHU SAR, the Accident Model Document (AMD), are to: Identify all malfunctions, both singular and multiple, which can occur during the complete mission profile that could lead to release outside the clad of the radioisotopic material contained therein; Provide estimates of occurrence probabilities associated with these various accidents; Evaluate the response of the LWRHU (or its components) to the resultant accident environments; and Associate the potential event history with test data or analysis to determine the potential interaction of the released radionuclides with the biosphere.

Johnson, E.W.

1988-10-01T23:59:59.000Z

51

Review and Approval of Nuclear Facility Safety Basis Documents...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

institutional programs in Integrated Safety Management System documents and site-wide manuals was added. p. 13 Sect. 3 Approval Bases for Technical Safety Requirements New...

52

Evolution of Safety Basis Documentation for the Fernald Site  

SciTech Connect

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

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

2004-03-01T23:59:59.000Z

53

Style, content and format guide for writing safety analysis documents: Volume 2, Safety assessment reports for DOE non-nuclear facilities  

SciTech Connect

The purpose of Volume 2 of this 4-volume style guide is to furnish guidelines on writing and publishing Safety Assessment Reports (SAs) for DOE non-nuclear facilities at Sandia National Laboratories. The scope of Volume 2 encompasses not only the general guidelines for writing and publishing, but also the prescribed topics/appendices contents along with examples from typical SAs for DOE non-nuclear facilities.

Mahn, J.A.; Silver, R.C.; Balas, Y.; Gilmore, W.

1995-07-01T23:59:59.000Z

54

Light-Weight Radioisotope Heater Unit Safety Analysis Report (LWRHU-SAR). Volume II. Accident model document  

SciTech Connect

Purposes of this volume (AMD), are to: Identify all malfunctions, both singular and multiple, which can occur during the complete mission profile that could lead to release outside the clad of the radioisotopic material contained therein; provide estimates of occurrence probabilities associated with these various accidents; evaluate the response of the LWRHU (or its components) to the resultant accident environments; and associate the potential event history with test data or analysis to determine the potential interaction of the released radionuclides with the biosphere.

Johnson, E.W.

1985-10-01T23:59:59.000Z

55

Environmental restoration and decontamination & decommissioning safety documentation. Revision 2  

SciTech Connect

This document presents recommendations of a working group designated by the Environmental Restoration and Remediation (ER) and Decontamination and Decommissioning (D&D) subcommittees of the Westinghouse M&O (Management and Operation) Nuclear Facility Safety Committee. A commonalty of approach to safety documentation specific to ER and D&D activities was developed and is summarized below. Allowance for interpretative tolerance and documentation flexibility appropriate to the activity, graded for hazard category, duration, and complexity, was a primary consideration in development of this guidance.

Hansen, J.L. [Westinghouse Savannah River Co., Aiken, SC (United States); Frauenholz, L.H. [Westinghouse Idaho Nuclear Co., Inc. (United States); Kerr, N.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-05-18T23:59:59.000Z

56

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

14, 2002 14, 2002 Preliminary Notice of Violation, Fluor Hanford, Incorporated - EA-2002-03 Preliminary Notice of Violation issued to Fluor Hanford, Incorporated, related to Quality Assurance issues at the Hanford Site. June 19, 2002 Enforcement Letter, Kaiser-Hill Company, L.L.C. - June 19, 2002 Enforcement Letter issued to Kaiser-Hill Company, LLC related to Unplanned Radioactive Material Uptakes at the Rocky Flats Environmental Technology Site October 22, 2001 Special Report Order, CH2M Hill Hanford Group, Inc. - October 22, 2001 Special Report Order issued to CH2M Hill Hanford Group, Inc., related to Multiple Nuclear Safety Issues at the Hanford Site October 9, 2001 Enforcement Letter, LANL - October 9, 2001 Enforcement Letter issued to Los Alamos National Laboratory related to

57

DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011  

Energy.gov (U.S. Department of Energy (DOE))

PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis.

58

Development of Onsite Transportation Safety Documents for Nevada Test Site  

Science Conference Proceedings (OSTI)

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

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

2008-05-08T23:59:59.000Z

59

Worker Safety and Health Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Worker Safety and Health Enforcement Worker Safety and Health Enforcement Documents Worker Safety and Health Enforcement Documents Documents Available for Download November 27, 2013 Enforcement Letter, WEL-2013-04 Issued to National Renewable Energy Laboratory related to a drum rupture and flash event of the Thermochemical User Facility. August 29, 2013 Preliminary Notice of Violation, Brookhaven Science Associates, LLC - WEA-2013-01 issued to Brookhaven Science Associates, LLC, related to a Fall Injury Event that occurred in Building 701 at the Brookhaven National Laboratory WEA-2013-01 July 30, 2013 Enforcement Letter, WEL-2013-02 Issued to Wastren Advantage, Inc. related to the Loss of Supplied Breathing Air in the Box Breakdown Area of the Transuranic Waste Processing Center located in Oak Ridge, Tennessee

60

Program for documenting the criticality safety basis for operations in a research and development facility consistent with new regulatory requirements  

SciTech Connect

A program was developed and implemented at LLNL to provide more detailed, documented Criticality Safety Evaluations of operations in an R&D facility. The new Criticality Safety evaluations were consistent with regulatory requirements of the then new DOE Order 5480.24, Nuclear Criticality Safety. The evaluations provide a criticality safety basis for each operation in the facility in support of the facility Safety Analysis Report. This implementation program provided a transition from one method of conducting and documenting Criticality Safety Evaluations to a new method consistent with new regulatory requirements. The program also allowed continued safe operation of the facility while the new implementation level Criticality Safety Evaluations were developed.

Pearson, J.S.; Evarts, R.B.; Huang, S.T.; Goebel, G.

1997-04-24T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

National Offshore Petroleum Safety Authority Purpose of this Document  

E-Print Network (OSTI)

This document has been prepared to provide guidance on the preparation, submission and assessment of Safety Cases for petroleum facilities in Australian offshore waters. It has been prepared by the National Offshore Petroleum Safety Authority, in consultation with a Technical Working Group comprising representatives of Australias offshore petroleum industry, the State/NT designated authorities, and the offshore workforce. Following these guidelines should assist in achieving compliance with the relevant law. These Guidelines are currently in draft form only, and will remain draft until 1 January 2005, when NOPSA assumes control of offshore petroleum safety regulation, and corresponding amendments to the law come into force. This draft has been issued prior to the transition date to ensure that operators currently developing or revising a Safety Case understand the changes that will be occurring. Areas where guidance material is currently incomplete are indicated by the word HOLD. When formally issued on 1 January 2005, these new Guidelines will replace the current guidelines

unknown authors

2004-01-01T23:59:59.000Z

62

Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5506-2007 5506-2007 April 2007 DOE STANDARD Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities U.S. Department of Energy Washington, D.C. 20585 AREA-SAFT DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-5506-2007 ii Available on the Department of Energy Technical Standards Program Web Site at Http://tis.eh.doe.gov/techstds/ DOE-STD-5506-2007 iii Foreword This Standard provides analytical assumptions and methods, as well as hazard controls to be used when developing Safety Basis (SB) documents for transuranic (TRU) waste facilities in the U.S. Department of Energy (DOE) Complex. It also provides supplemental technical

63

Solid waste burial grounds interim safety analysis  

SciTech Connect

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

Saito, G.H.

1994-10-01T23:59:59.000Z

64

Digital Libraries and Document Image Analysis  

Science Conference Proceedings (OSTI)

The rapid growth of digital libraries (DLs) worldwideposes many new challenges for document image analysis(DIA) research and development. DLs promise to offermore people access to larger document collections, and atfar greater speed, than physical libraries ...

Henry S. Baird

2003-08-01T23:59:59.000Z

65

DOE Order Self Study Modules - 10 CFR 830 Safety Basis Documentation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Orders Orders Self-Study Program Safety Basis Documentation 10 CFR 830, NUCLEAR SAFETY MANAGEMENT DOE G 421.1-2, IMPLEMENTATION GUIDE FOR USE IN DEVELOPING DOCUMENTED SAFETY ANALYSES TO MEET SUBPART B OF 10 CFR 830 DOE G 423.1.1, IMPLEMENTATION GUIDE FOR USE IN DEVELOPING TECHNICAL SAFETY REQUIREMENTS DOE G 424.1-1, IMPLEMENTATION GUIDE FOR USE IN ADDRESSING UNREVIEWED SAFETY QUESTION REQUIREMENTS DOE-STD-1104-96, REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) NNSA SERVICE CENTER Change No: 0 Safety Basis Documents Level: Familiar Date: 10/15/03 1 SAFETY BASIS DOCUMENTS FAMILIAR LEVEL OBJECTIVES Given the familiar level of this module and the resources listed below, you will be able to:

66

Package Safety Analysis Assessment for Sludge Transportation System  

SciTech Connect

This package safety analysis assessment demonstrates that the Sludge Transportation System meets the acceptance criteria for an equivalent package as specified in DOE/RL-2001-36, Hanford Sitewide Transportation Safety Document for onsite shipment.

ROMANO, T.

2003-03-19T23:59:59.000Z

67

Cold Vacuum Drying facility design basis accident analysis documentation  

SciTech Connect

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

CROWE, R.D.

2000-08-08T23:59:59.000Z

68

Reactor instrumentation and safety circuit status review and program document  

SciTech Connect

This document has been prepared for internal use by the General Electric Company to serve as a program for evaluating reactor instrumentation and safety circuit equipment needs. It is intended that this document be used as a guide for defining, planning and scheduling engineering effort; budgeting of capital money; and project planning for new instrumentation systems. Effort will be made to periodically evaluate the status of the programs presented and provide updating information accordingly.After a plant has been built and operated for a number of years, it becomes apparent to operating and engineering personnel that certain modifications in controls and monitoring systems would provide both tangible and intangible benefits. Systems which were once thought to be the primary points of control shift in importance as others become recognized. As time passes this shifting spreads the main control focus from the central control desk to various other areas in the control room. Production rate increases cause instrument ranges and scales to be changed so that information on the process can still be obtained from existing equipment. Response times, sensitivity, limits, and time constants which were figured for one level must be used or revised for new levels. Further, it is discovered that the process monitoring points could be relocated or increased in number to provide more and better data on plant operation. New monitoring equipment is developed and installed to fill voids in information so production can continue meeting high standards for safety and process control. Equipment is fitted here and there in an already crowded control room, and some is even relocated to less advantageous positions to make available the necessary panel space. This in brief, is the rather complex status of Hanford Production Reactor instrumentation today.

Deichman, J.L.

1963-02-15T23:59:59.000Z

69

Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD .................................................................................................................................. v INTRODUCTION ..........................................................................................................................

70

ASD Facility Hazard Analysis Document - Building 382  

NLE Websites -- All DOE Office Websites (Extended Search)

reviews 1 NA ESH145 ESH119 ESH195 NA NA NA A ESH108382 Surface Analysis Chamber High voltage Compressed gas Cryogenic vacuum Cage Limited access Clean hood TLD Safety...

71

Independent component analysis for document restoration  

Science Conference Proceedings (OSTI)

We propose a novel approach to restoring digital document images, with the aim of improving text legibility and OCR performance. These are often compromised by the presence of artifacts in the background, derived from many kinds of degradations, such ... Keywords: Blind source separation, Degraded documents, Independent component analysis, Palimpsest restoration- Bleed-through cancellation

Anna Tonazzini; Luigi Bedini; Emanuele Salerno

2004-03-01T23:59:59.000Z

72

Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program  

SciTech Connect

Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

1994-02-01T23:59:59.000Z

73

Technical Standards, Safety Analysis Toolbox Codes - November 2003 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Analysis Toolbox Codes - November 2003 Safety Analysis Toolbox Codes - November 2003 Technical Standards, Safety Analysis Toolbox Codes - November 2003 November 2003 Software Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes Safety analysis software for the DOE "toolbox" was designated by DOE/EH in March 2003 (DOE/EH, 2003). The supporting basis for this designation was provided by a DOE-chartered Safety Analysis Software Group in the technical report, Selection of Computer Codes for DOE Safety Analysis Applications, (August, 2002). Technical Standards, Safety Analysis Toolbox Codes More Documents & Publications DOE G 414.1-4, Safety Software Guide for Use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance Technical Standards, MELCOR - Gap Analysis - May 3, 2004

74

Order Module--NNSA Orders Self-Study Program Safety Basis Documentation |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSA Orders Self-Study Program Safety Basis NNSA Orders Self-Study Program Safety Basis Documentation Order Module--NNSA Orders Self-Study Program Safety Basis Documentation The familiar level of this module is divided into five sections. In the first section, we will discuss the regulation. In the second, third, and fourth sections, we will discuss the U. Department of Energy (DOE) guides for documented safety analyses (DSAs), technical safety requirements (TSRs), and unreviewed safety questions (USQs). Section 5 discusses the DOE standard related to DSAs and TSRs. We have provided several examples and practices throughout the module to help familiarize you with the material. The practices will also help prepare you for the criterion test. DOE Order Self Study Modules - 10 CFR 830 Safety Basis Documentation

75

SYNTHESIS OF SAFETY ANALYSIS AND FIRE HAZARD ANALYSIS METHODOLOGIES  

Science Conference Proceedings (OSTI)

Successful implementation of both the nuclear safety program and fire protection program is best accomplished using a coordinated process that relies on sound technical approaches. When systematically prepared, the documented safety analysis (DSA) and fire hazard analysis (FHA) can present a consistent technical basis that streamlines implementation. If not coordinated, the DSA and FHA can present inconsistent conclusions, which can create unnecessary confusion and can promulgate a negative safety perception. This paper will compare the scope, purpose, and analysis techniques for DSAs and FHAs. It will also consolidate several lessons-learned papers on this topic, which were prepared in the 1990s.

Coutts, D

2007-04-17T23:59:59.000Z

76

Aviation safety analysis  

E-Print Network (OSTI)

Introduction: Just as the aviation system is complex and interrelated, so is aviation safety. Aviation safety involves design of aircraft and airports, training of ground personnel and flight crew members' maintenance of ...

Ausrotas, Raymond A.

1984-01-01T23:59:59.000Z

77

Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Bulletin 2011-01, Events Beyond Design Safety Basis Analysis Bulletin 2011-01, Events Beyond Design Safety Basis Analysis Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and the subsequent tsunami. While there is still a lot to be learned from the accident · about the adequacy of design specifications and the equipment failure modes, reports from the Nuclear Regulatory Commission (NRC) have identified some key aspects of the operational emergency at the Fukushima Daiichi nuclear power station.

78

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

SciTech Connect

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

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

1993-04-15T23:59:59.000Z

79

NREL: Energy Analysis - HERS/EEMs Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

HERSEEMs Documents Search NREL's document database for research papers about Home Energy Rating Systems (HERs) and Energy Efficient Mortgages (EEMs). Listed below are some...

80

Worker Safety and Health Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

, 2009 , 2009 Preliminary Notice of Violation, Western Allied Mechanical, Inc. - WEA-2010-03 Preliminary Notice of Violation issued to Sandia Corporation related to the Inadvertent Ignition of a Rocket Motor May 20, 2009 Enforcement Letter, CH2M-Washington Group Idaho LLC , - May 20, 2009 Enforcement Letter issued to CH2M-Washington Group Idaho, LLC, for Electrical Safety Deficiencies at the Idaho National Laboratory February 13, 2009 Enforcement Letter, Oak Ridge National Laboratory LLC- May 13, 2009 Enforcement Letter issued to UT-Battelle, LLC related to a Radioactive Material Release at the Holifield Radioactive Ion Beam Facility at Oak Ridge National Laboratory June 20, 2008 Preliminary Notice of Violation, Battelle Energy Alliance, LLC - WEA-2008-01 Notice of Violation issued to Battelle Energy Alliance, LLC, related to a

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Worker Safety and Health Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3, 2002 3, 2002 Preliminary Notice of Violation, BWXT Idaho, LLC - EA-2002-02 Preliminary Notice of Violation issued to BWXT Idaho, LLC, related to Work Process Violations and Quality Issues at the Radioactive Waste Management Complex and Advanced Test Reactor at the Idaho National Engineering and Environmental Laboratory January 4, 2002 Preliminary Notice of Violation, Fluor Fernald, Inc - EA-2001-06 Preliminary Notice of Violation issued to Fluor Fernald, Inc., related to Unplanned Radiation Exposures and Quality Improvement Deficiencies at the Fernald Environmental Management Project, EA-2001-06 March 19, 2001 Preliminary Notice of Violation, BNFL, Inc - EA-2001-02 Preliminary Notice of Violation issued to BNFL, Inc., related to Quality Assurance and Nuclear Safety Issues with the Converter Tube Bundle Fire at

82

Waste Isolation Pilot Plant Safety Analysis Report  

Science Conference Proceedings (OSTI)

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

NONE

1995-11-01T23:59:59.000Z

83

Safety analysis report for the Waste Storage Facility. Revision 2  

SciTech Connect

This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

Bengston, S.J.

1994-05-01T23:59:59.000Z

84

Volume II - Accident and Operational Safety Analysis Handbook  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

208-2012 208-2012 July 2012 DOE HANDBOOK Accident and Operational Safety Analysis Volume II: Operational Safety Analysis Techniques U.S. Department of Energy Washington, D.C. 20585 NOT MEASUREMENT SENSITIVE DOE-HDBK-1208-2012 i ACKNOWLEDGEMENTS This Department of Energy (DOE) Accident and Operational Safety Analysis Handbook was prepared under the sponsorship of the DOE Office of Health Safety and Security (HSS), Office of Corporate Safety Programs, and the Energy Facility Contractors Operating Group (EFCOG), Industrial Hygiene and Safety Sub-group of the Environmental Health and Safety Working Group. The preparers would like to gratefully acknowledge the authors whose works are referenced in this document, and the individuals who provided valuable technical insights and/or specific

85

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Federal Register Federal Register / Vol. 76, No. 19 / Friday, January 28, 2011 / Notices No decision will be made to implement any alternative until the U.S. Navy F-35C West Coast Homebasing EIS process is completed and a Record of Decision is signed by the Assistant Secretary of the Navy (Energy, Installations and Environment) or designee. Resource areas to be addressed in the U.S. Navy F-35C West Coast Homebasing EIS will include, but not be limited to: Air quality, noise environment, land use, socioeconomics, infrastructure and community services, natural resources, biological resources, cultural resources, safety and environmental hazards. The analysis will evaluate direct and indirect impacts, and will account for cumulative impacts from other relevant activities in the area of NAS Lemoore

86

Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Discovery of Uranium Discovery of Uranium Uranium was discovered in 1789 by Martin Klaproth, a German chemist, who isolated an oxide of uranium while analyzing pitchblende samples from the Joachimsal silver mines in the former Kingdom of Bohemia located in the present day Czech Republic. more facts >> Mailing List Signup Receive e-mail updates about this project and web site. your e-mail address Sign Me Up Search: OK Button DUF6 Guide DU Uses DUF6 Management and Uses DUF6 Conversion EIS Documents News FAQs Internet Resources Glossary Home » Documents Search Documents: Search PDF Documents View a list of all documents Depleted UF6 Management Program Documents Downloadable documents about depleted UF6 management and related topics, including Depleted UF6 Conversion and Programmatic EIS documents

87

Idaho Chemical Processing Plant safety document ICPP hazardous chemical evaluation  

Science Conference Proceedings (OSTI)

This report presents the results of a hazardous chemical evaluation performed for the Idaho Chemical Processing Plant (ICPP). ICPP tracks chemicals on a computerized database, Haz Track, that contains roughly 2000 individual chemicals. The database contains information about each chemical, such as its form (solid, liquid, or gas); quantity, either in weight or volume; and its location. The Haz Track database was used as the primary starting point for the chemical evaluation presented in this report. The chemical data and results presented here are not intended to provide limits, but to provide a starting point for nonradiological hazards analysis.

Harwood, B.J.

1993-01-01T23:59:59.000Z

88

ASD Facility Hazard Analysis Document - Building 413  

NLE Websites -- All DOE Office Websites (Extended Search)

13 13 Equipment Hazards Engineered Controls Electrical Safety Training References Electrical Safety Procedures Mechanical Safety Training References Mechanical Safety Procedures Radiological, Environmental & Chemical Training References Radiological, Environmental & Chemical Procedures Additional Safety Tool References DC Power Supplies DC voltages < 200 Volts DC currents < 200 Amps AC voltages < 600 Volts Lifting < 350 lbs Supplies mounted in relay racks Rack doors locked or bolted closed Power source signage 120/208/480 VAC covered Lifting fixture Emergency stop buttons Flashing strobes LOTO 1, 7 1110-00124 31020101-00025 1110-00125 Power Supplies Hot Work Permits 6, 7 NA NA NA A ASD108/400 GESPAC Power Supply Control Units 120 VAC Fans Fan blades covered 1, 7 Power Supplies Hot Work Permit

89

ASD Facility Hazard Analysis Document - Building 412  

NLE Websites -- All DOE Office Websites (Extended Search)

2 2 Equipment Hazards Engineered Controls Electrical Safety Training References Electrical Safety Procedures Mechanical Safety Training References Mechanical Safety Procedures Radiological, Environmental & Chemical Training References Radiological, Environmental & Chemical Procedures Additional Safety Tool References DC Power Supplies DC voltages < 300 Volts DC currents < 500 Amps AC voltages < 600 Volts Lifting < 350 lbs Supplies mounted in relay racks Rack doors locked or bolted closed Power source signage 120/208/480 VAC covered Lifting fixture Emergency stop buttons Flashing strobes LOTO 1, 7 2502-00005 2502-00006 2502-00007 2502-00008 2502-00010 250201-00028 250202-00001 2502-00006 2502-00007 250206-00007 2202-00006 2202-00009 250203-00006 250204-00002 250205-00004

90

ASD Facility Hazard Analysis Document - Building 400  

NLE Websites -- All DOE Office Websites (Extended Search)

Equipment Hazards Engineered Controls Electrical Safety Training References Electrical Safety Procedures Mechanical Safety Training References Mechanical Safety Procedures Radiological, Environmental & Chemical Training References Radiological, Environmental & Chemical Procedures Additional Safety Tool References DC Power Supplies DC voltages < 72 Volts DC currents < 450 Amps Lifting < 75 lbs Supplies mounted in NEMA enclosures Rack doors locked Power source signage 120/208 VAC covered Emergency stop buttons Flashing strobes LOTO 1,7 31020101-00025 3108-00006 310202-00089 3102-00064 2202-00006 Power Supplies Hot Work Permits 6, 7 NA NA NA A ASD108/400 Hi Power DC Power Supply DC voltages < 72 Volts DC currents < 2600 Amps AC voltages < 600 Volts Supplies built in NEMA enclosures

91

ASD Facility Hazard Analysis Document - Building 420  

NLE Websites -- All DOE Office Websites (Extended Search)

20 20 Equipment Hazards Engineered Controls Electrical Safety Training References Electrical Safety Procedures Mechanical Safety Training References Mechanical Safety Procedures Radiological, Environmental & Chemical Training References Radiological, Environmental & Chemical Procedures Additional Safety Tool References DC Power Supplies DC voltages < 300 Volts DC currents < 500 Amps AC voltages < 600 Volts Lifting < 350 lbs Supplies mounted in relay racks Rack doors locked or bolted closed Power source signage 120/208/480 VAC covered Lifting fixture Emergency stop buttons Flashing strobes LOTO 1, 7 2202-00006 2402-00002 240201-00002 240202-00003 240204-00003 31020101-00025 2202-00004 2202-00006 2202-00009 220209-00057 31020101-00025 Power Supplies Hot Work Permits

92

Independent Component Analysis for Document Restoration  

E-Print Network (OSTI)

We propose a novel approach to restoring digital document images, with the aim of improving text legibility and OCR performance. These are often compromised by the presence of artifacts in the background, derived from many kinds of degradations, such as spots, underwritings, and show-through or bleed-through e#ects. So far, background removal techniques have been based on local, adaptive filters and morphological--structural operators to cope with frequent low-contrast situations. For the specific problem of bleed-through/show-through, most work has been based on the comparison between the front and back pages. This, however, requires a preliminary registration of the two images. Our approach is based on viewing the problem as one of separating overlapped texts and then reformulating it as a blind source separation problem, approached through independent component analysis techniques. These methods have the advantage that no models are required for the background. In addition, we use the spectral components of the image at di#erent bands, so that there is no need for registration. Examples of bleed-through cancellation and recovery of underwriting from palimpsests are provided.

Anna Tonazzini; Luigi Bedini; Emanuele Salerno

2004-01-01T23:59:59.000Z

93

Rapid Exploitation and Analysis of Documents  

SciTech Connect

Analysts are overwhelmed with information. They have large archives of historical data, both structured and unstructured, and continuous streams of relevant messages and documents that they need to match to current tasks, digest, and incorporate into their analysis. The purpose of the READ project is to develop technologies to make it easier to catalog, classify, and locate relevant information. We approached this task from multiple angles. First, we tackle the issue of processing large quantities of information in reasonable time. Second, we provide mechanisms that allow users to customize their queries based on latent topics exposed from corpus statistics. Third, we assist users in organizing query results, adding localized expert structure over results. Forth, we use word sense disambiguation techniques to increase the precision of matching user generated keyword lists with terms and concepts in the corpus. Fifth, we enhance co-occurrence statistics with latent topic attribution, to aid entity relationship discovery. Finally we quantitatively analyze the quality of three popular latent modeling techniques to examine under which circumstances each is useful.

Buttler, D J; Andrzejewski, D; Stevens, K D; Anastasiu, D; Gao, B

2011-11-28T23:59:59.000Z

94

Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Comparison of Integrated Safety Analysis (ISA) and Probabilistic Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11 Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11 During the 580th meeting of the Advisory Committee on Reactor Safeguards (ACRS), February 10-12, 2011, we reviewed the staff's white paper, "A Comparison of Integrated Safety Analysis and Probabilistic Risk Assessment." Our Radiation Protection and Nuclear Materials Subcommittee also reviewed this matter during a meeting on January 11, 2011. During these meetings we met with representatives of the NRC staff and the Nuclear Energy Institute. We also had the benefit of the documents referenced. Comparison of Intergrated Safety Analysis (ISA) and Probabilistic Risk

95

DOE: Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities, 10j/24/03  

Energy.gov (U.S. Department of Energy (DOE))

This document contains software quality assurance (SQA) assessment criteria and guidelines for assessing the safety software currently in use in the safety analysis and design of structures,...

96

Documents  

Open Energy Info (EERE)

documents en MHK LCOE Reporting documents en MHK LCOE Reporting Guidance Draft http://en.openei.org/community/document/mhk-lcoe-reporting-guidance-draft To normalize competing claims of LCOE, DOE has developed-for its own use-a standardized cost and performance data reporting process to facilitate uniform calculation of LCOE from MHK device developers. This standardization framework is only the first version in what is anticipated to be an iterative process that involves industry and the broader DOE stakeholder community. Multiple files are attached here for review and comment.document/mhk-lcoe-reporting-guidance-draft" target="_blank">read more http://en.openei.org/community/document/mhk-lcoe-reporting-guidance-draft#comments

97

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

558 Federal Register 558 Federal Register / Vol. 74, No. 203 / Thursday, October 22, 2009 / Notices If you use a TDD, call the FRS, toll free, at 1-800-877-8339. VIII. Other Information Accessible Format: Individuals with disabilities can obtain this document and a copy of the application package in an accessible format (e.g., braille, large print, audiotape, or computer diskette) on request to the program contact person listed under For Further Information Contact in Section VII of this notice. Electronic Access to This Document: You can view this document, as well as all other documents of this Department published in the Federal Register, in text or Adobe Portable Document Format (PDF) on the Internet at the following site: http://www.ed.gov/news/ fedregister. To use PDF, you must have Adobe

98

NITROGEN -N2 MSDS (Document # 001040) PAGE 1 OF 10 MATERIAL SAFETY DATA SHEET  

E-Print Network (OSTI)

in an emergency? 1. PRODUCT IDENTIFICATION CHEMICAL NAME; CLASS: NITROGEN - N2 LIQUEFIED NITROGEN N2, (CryogenicNITROGEN - N2 MSDS (Document # 001040) PAGE 1 OF 10 MATERIAL SAFETY DATA SHEET Prepared to U ppm ppm ppm Nitrogen 7727-37-9 >99 % There are no specific exposure limits for Nitrogen. Nitrogen

Choi, Kyu Yong

99

Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3009-94 3009-94 July 1994 CHANGE NOTICE NO.1 January 2000 CHANGE NOTICE NO. 2 April 2002 CHANGE NOTICE NO. 3 March 2006 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-3009-94 Page ii This document has been reproduced directly 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. DOE-STD-3009-94 Page iii Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses Table of Changes

100

Document  

NLE Websites -- All DOE Office Websites (Extended Search)

5R1 Guide for Developing Data Quality Objectives for Ecological Risk Assessment at DOE Oak Ridge Operations Facilities This document has been approved by the K-25 Site Technical...

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

44 Federal Register 44 Federal Register / Vol. 76, No. 62 / Thursday, March 31, 2011 / Notices not anticipate recurrence of violations that gave rise to this PDL. As a result, under the authority in 20 U.S.C. 1234a(j), the Department has determined that compromise of this claim to $675,000 is appropriate. The public is invited to comment on the Department's intent to compromise this claim. Additional information may be obtained by contacting the person listed under FOR FURTHER INFORMATION CONTACT. Electronic Access to This Document: You can view this document, as well as all other documents of this Department published in the Federal Register, in text or Adobe Portable Document Format (PDF) on the Internet at the following site: http://www.ed.gov/news/ fedregister. To use PDF you must have

102

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Online links at http: www.ferc.gov. To facilitate electronic service, persons with Internet access who will eFile a document andor be listed as a contact for an intervenor must...

103

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the EIS and requests to be added to the document mailing list should be addressed to: Dr. Jerry Pell, Office of Electricity Delivery and Energy Reliability (OE-20), U.S. Department...

104

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

compliance with Commission submission guidelines at http: www.ferc.govhelpsubmission- guide.asp. Comments may be eFiled. The eFiling option under the Documents & Filings tab on...

105

Document  

NLE Websites -- All DOE Office Websites (Extended Search)

988 Federal Register 988 Federal Register / Vol. 75, No. 242 / Friday, December 17, 2010 / Notices texts of formal documents issued by the Commission, such as orders, notices, and rulemakings. In addition, the Commission now offers a free service called eSubscription which allows you to keep track of all formal issuances and submittals in specific dockets. This can reduce the amount of time you spend researching proceedings by automatically providing you with notification of these filings, document summaries, and direct links to the documents. Go to http:// www.ferc.gov/esubscribenow.htm. Finally, public meetings or site visits will be posted on the Commission's calendar located at http://www.ferc.gov/ EventCalendar/EventsList.aspx along with other related information.

106

Knowing what happened - automatic documentation of image analysis processes  

Science Conference Proceedings (OSTI)

Proper archiving or later reconstruction and verification of results in data analysis requires thorough logging of all manipulative actions on the data and corresponding parameter settings. Unfortunately such documentation tasks often enforce extensive ... Keywords: XML, automatic documentation, image analysis, meta data, processing graph

Birgit Mller; Oliver Gre; Stefan Posch

2011-09-01T23:59:59.000Z

107

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0 Federal Register 0 Federal Register / Vol. 75, No. 220 / Tuesday, November 16, 2010 / Notices at the following site: http://www.ed.gov/ news/fedregister. To use PDF you must have Adobe Acrobat Reader, which is available free at this site. Note: The official version of this document is the document published in the Federal Register. Free Internet access to the official edition of the Federal Register and the Code of Federal Regulations is available on GPO access at: http://www.gpoaccess.gov/nara/ index.html. Authority: 5 U.S.C. 552a; 21 U.S.C. 862(a)(1). Dated: November 10, 2010. James F. Manning, Chief of Staff, Federal Student Aid, U.S. Department of Education. [FR Doc. 2010-28856 Filed 11-15-10; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY [OE Docket No. PP-371]

108

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

667 Federal Register 667 Federal Register / Vol. 74, No. 105 / Wednesday, June 3, 2009 / Notices Part 1 Chapter 3 of the TGDC Recommendations, with the exception of Chapter 3's performance benchmark requirements. Part 1 Chapter 3 of the TGDC Recommendations is primarily a maintenance level upgrade to the 2005 VVSG with minor modifications, clarifications, and a few additions including performance and poll worker usability requirements. (The VSS 2002 contained almost no usability, accessibility, and privacy requirements. As a result, the 2005 VVSG Section 3 was mostly new material based on research, best practices, and standards relating to human factors and the design of user interfaces as they apply to voting systems.) 7. System Security Documentation Requirements-Security documentation

109

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

78 Federal Register 78 Federal Register / Vol. 75, No. 207 / Wednesday, October 27, 2010 / Notices 1 Western has authority to prepare and approve EISs for integrating transmission facilities with its system pursuant to an October 4, 1999 Delegation Order from the DOE Assistant Secretary for Environment, Health and Safety. DEPARTMENT OF ENERGY Western Area Power Administration Draft Environmental Impact Statement/ Staff Assessment for the Solar Reserve LLC Rice Solar Energy Project, Riverside County, CA (DOE/ EIS-0439) and Possible California Desert Conservation Area Plan Amendment AGENCY: Western Area Power Administration, DOE. ACTION: Notice of Availability of Draft Environmental Impact Statement/Staff Assessment. SUMMARY: In accordance with the National Environmental Policy Act

110

Safety System Oversight Program Assessment Criteria and Review Approach Document (CRAD), Revision 0  

NLE Websites -- All DOE Office Websites (Extended Search)

of 7 of 7 Safety System Oversight (SSO) Program Implementation Assessment Criteria and Review Approach Documents (CRADs) Revision 0 PROGRAM (PGM) OBJECTIVE PGM.1 An effective SSO Program is established by the Field Element Manager to apply engineering expertise to maintain safety system configuration and to assess system condition and effectiveness of safety management program implementation. Criteria PGM.1.1 The SSO Qualification Program is part of the Technical Qualification Program (DOE M 426.1-1A, Chapter III, Section 1, 2.b (1)). PGM.1.2 The SSO Program establishes appropriate training, qualification, and performance requirements for SSO personnel and the supervisors are held accountable for achieving them (DOE M 426.1-1A, Chapter III, Section 1, 2.b

111

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

52841 52841 Vol. 67, No. 157 Wednesday, August 14, 2002 DEPARTMENT OF AGRICULTURE Federal Crop Insurance Corporation 7 CFR Part 457 Common Crop Insurance Regulations; Sugarcane Crop Insurance Provisions AGENCY: Federal Crop Insurance Corporation, USDA. ACTION: Final rule; correction. SUMMARY: This document contains corrections to the final rule, Common Crop Insurance Regulations; Sugarcane Crop Insurance Provisions that the Federal Crop Insurance Corporation published in the Federal Register on Friday, July 12, 2002 (67 FR 46093- 46096). EFFECTIVE DATE: August 14, 2002. FOR FURTHER INFORMATION CONTACT: Arden Routh, Risk Management Specialist, Product Development Division, Federal Crop Insurance Corporation, United States Department of Agriculture, 6501 Beacon Drive,

112

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

60 Federal Register 60 Federal Register / Vol. 73, No. 207 / Friday, October 24, 2008 / Notices 1 The nuclear weapons stockpile consists of nuclear weapons that are both deployed to the military services (''operationally deployed'') and ''reserve weapons'' that could be used to augment the operationally deployed weapons or to provide replacements for warheads that experience safety or reliability problems. Informed Commitment-Confirm willingness and availability of appropriate agency leadership and staff at all levels to commit to principles of engagement, and ensure commitment to participate in good faith with open mindset to new perspectives. Balanced, Voluntary Representation- Ensure balanced inclusion of affected/ concerned interests; all parties should be willing and able to participate and select

113

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9 Federal Register 9 Federal Register / Vol. 74, No. 122 / Friday, June 26, 2009 / Notices 1 DOE's NEPA regulations state at 10 CFR 1021.343(c) that the Secretary of Energy must provide written approval of any variance under that section. However, this authority has been delegated to the General Counsel pursuant to Department of Energy Delegation Order No. 00-015.00A to the General Counsel. 1 As noted in Western's Notice of Intent to prepare a Big Stone II EIS, Western became the lead agency for preparation of the EIS because the construction of Big Stone II would incorporate a major new generation resource into Western's Continued DOE's existing NEPA regulations provide for certain variances ''soundly based on the interests of national security or the public health, safety, or

114

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

586 586 Federal Register / Vol. 64, No. 143 / Tuesday, July 27, 1999 / Notices Telephone: (202) 205-9817. If you use a telecommunications device for the deaf (TDD), you may call the Federal Information Relay Service (FIRS) at 1- 800-877-8339. However, the Department is not able to reproduce in an alternate format the standard forms included in the application package. FOR FURTHER INFORMATION CONTACT: Sylvia Johnson, U.S. Department of Education, 400 Maryland Avenue, SW. (room 3318, Switzer Building), Washington, DC 20202-2649. Telephone (202) 205-9312. If you use a telecommunications device for the deaf (TDD), you may call the Federal Information Relay Service (FIRS) at 1- 800-877-8339. Individuals with disabilities may obtain this document in an alternate format (e.g., Braille, large print,

115

Document  

NLE Websites -- All DOE Office Websites (Extended Search)

May 22, 2000 Part III Environmental Protection Agency 40 CFR Part 261 Regulatory Determination on Wastes from the Combustion of Fossil Fuels; Final Rule VerDate 112000 16:01 May 19, 2000 Jkt 190000 PO 00000 Frm 00001 Fmt 4717 Sfmt 4717 E:\FR\FM\22MYR3.SGM pfrm02 PsN: 22MYR3 32214 Federal Register / Vol. 65, No. 99 / Monday, May 22, 2000 / Rules and Regulations ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 261 [FRL-6588-1] RIN 2050-AD91 Notice of Regulatory Determination on Wastes From the Combustion of Fossil Fuels AGENCY: Environmental Protection Agency. ACTION: Regulatory determination. SUMMARY: This document explains EPA's determination of whether regulation of fossil fuel combustion wastes is warranted under subtitle C of the Resource Conservation and Recovery Act (RCRA). Today's action

116

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

945 Federal Register 945 Federal Register / Vol. 75, No. 143 / Tuesday, July 27, 2010 / Notices 1 The full text of the Convention on Supplementary Compensation for Nuclear Damage is available at http://www.iaea.org/Publication/ Documents/Infircs/1998/infcirc567.shtml. A detailed interpretation of the CSC and its provisions is contained in ''The 1997 Vienna Convention on Civil Liability for Nuclear Damage and the 1997 Convention on Supplementary Compensation for Nuclear Damage-Explanatory Texts,'' International Atomic Energy Agency (IAEA) (''Explanatory Texts''). International Law Series No. 3 (2007). The Explanatory Texts is available at http://www- pub.iaea.org/MTCD/publications/PDF/ Pub1279_web.pdf . 2 SDR is the unit of account defined by the International Monetary Fund (''IMF'') and used by

117

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

51 Federal Register 51 Federal Register / Vol. 76, No. 71 / Wednesday, April 13, 2011 / Notices VII. Agency Contact See chart in the Award Information section in this notice for the name, room number and telephone number of the contact person for each competition. You can write to the contact person at the following address: U.S. Department of Education, 400 Maryland Avenue, SW., Potomac Center Plaza (PCP), Washington, DC 20202-2600. If you use a TDD, call the Federal Relay Service (FRS), toll free, at 1-800- 877-8339. VIII. Other Information Accessible Format: Individuals with disabilities can obtain this document and a copy of the application package in an accessible format (e.g., braille, large print, audiotape, or computer diskette) by contacting the Grants and Contracts

118

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

902 Federal Register 902 Federal Register / Vol. 75, No. 15 / Monday, January 25, 2010 / Notices including Comments Resolution Matrixes (CRMs) and track changed documents, will be posted at: http:// www.losangeles.af.mil/library/ factsheets/factsheet.asp?id=9364. Please send all CRM comments to Vimal Gopal by 5 February 2010. DATES: 12 February 2010: IS-GPS-200E. 8 a.m.-12 p.m. (Pacific Time). Dial-In Information: Phone: 1-800- FON-SAIC (1-800-366-7242). Code: 4511074. FOR FURTHER INFORMATION CONTACT: Vimal Gopal, vimal.gopal.ctr@losangeles.af.mil, 1- 310-909-7294 or Captain Neal Roach, neal.roach@losangeles.af.mil, 1-310- 653-3771. Bao-Anh Trinh, Air Force Federal Register Liaison Officer. [FR Doc. 2010-1273 Filed 1-22-10; 8:45 am] BILLING CODE 5001-05-P DEPARTMENT OF ENERGY

119

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

79 Federal Register 79 Federal Register / Vol. 75, No. 242 / Friday, December 17, 2010 / Notices of a portion of National Guard Avenue to meet recommended stand-off distance between perimeter fence and mission critical resources and personnel). The decision was based on matters discussed in the Final Environmental Impact Statement (EIS) for the Proposed Realignment of National Guard Avenue and New Main Gate Construction, inputs from the public and regulatory agencies, and other relevant factors. The Final EIS was made available to the public on August 13, 2010 through a NOA in the Federal Register (Volume 75, Number 156, Page 49487) with a wait period that ended on September 14, 2010. The ROD documents only the decision of the Air Force with respect to the proposed Air Force actions analyzed

120

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 4 Federal Register / Vol. 68, No. 79 / Thursday, April 24, 2003 / Notices j. Deadline for filing comments and/ or motions: May 19, 2003. All documents (original and eight copies) should be filed with: Magalie R. Salas, Secretary, Federal Energy Regulatory Commission, 888 First Street, NE., Washington, DC 20426. Please include the project number (P- 10855-005) on any comments or motions filed. k. Description of Request: Upper Peninsula Power Company (UPPCO) proposes to add additional acreage to the project boundary in the area of the Emergency Fuse Plug. The additional acres are necessary for project operations. l. Location of the Application: A copy of the application is available for inspection and reproduction at the Commission's Public Reference Room,

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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121

Document  

NLE Websites -- All DOE Office Websites (Extended Search)

July 2, 2008 Part V The President Executive Order 13467-Reforming Processes Related to Suitability for Government Employment, Fitness for Contractor Employees, and Eligibility for Access to Classified National Security Information VerDate Aug2005 18:32 Jul 01, 2008 Jkt 214001 PO 00000 Frm 00001 Fmt 4717 Sfmt 4717 E:\FR\FM\02JYE0.SGM 02JYE0 hsrobinson on PROD1PC76 with PROPOSALS2 VerDate Aug2005 18:32 Jul 01, 2008 Jkt 214001 PO 00000 Frm 00002 Fmt 4717 Sfmt 4717 E:\FR\FM\02JYE0.SGM 02JYE0 hsrobinson on PROD1PC76 with PROPOSALS2 Presidential Documents 38103 Federal Register Vol. 73, No. 128 Wednesday, July 2, 2008 Title 3- The President Executive Order 13467 of June 30, 2008 Reforming Processes Related to Suitability for Government Employment, Fitness for Contractor Employees, and Eligi-

122

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

34 Federal Register 34 Federal Register / Vol. 72, No. 200 / Wednesday, October 17, 2007 / Notices public an opportunity to comment on the Guidance Memoranda prior to their approval. On May 6, 2005, a Notice of Availability was placed in the Federal Register (70 FR 24008) inviting the public to comment on the final draft of the Guidance Memoranda. As a result of public comment we received on the final draft, we have revised the Guidance Memoranda and invite the public to comment on the revised final draft. The programmatic regulations also require the concurrence of the Secretary of the Interior and the Governor of Florida on the Guidance Memoranda prior to their approval. An electronic copy of the guidance memoranda document is available at: http:// www.evergladesplan.org/pm/

123

Document  

National Nuclear Security Administration (NNSA)

44786 Federal Register 44786 Federal Register / Vol. 73, No. 148 / Thursday, July 31, 2008 / Notices same file as the submission itself, and not as separate files. Petitions will be available for public inspection by appointment with the staff of the USTR Public Reading Room, except for information granted ''business confidential'' status pursuant to 15 CFR 2003.6. If the submission contains business confidential information, a non-confidential version of the submission must also be submitted that indicates where confidential information was redacted by inserting asterisks where material was deleted. In addition, the confidential submission must be clearly marked ''BUSINESS CONFIDENTIAL'' in large, bold letters at the top and bottom of every page of the documents. The public version that does not contain

124

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2 Federal Register 2 Federal Register / Vol. 76, No. 14 / Friday, January 21, 2011 / Notices it is recommended that documents be transmitted by overnight mail, by electronic mail to Christopher.Lawrence@hq.doe.gov, or by facsimile to 202-586-8008. FOR FURTHER INFORMATION CONTACT: Christopher Lawrence (Program Office) 202-586-5260. SUPPLEMENTARY INFORMATION: Exports of electricity from the United States to a foreign country are regulated by the Department of Energy (DOE) pursuant to sections 301(b) and 402(f) of the Department of Energy Organization Act (42 U.S.C. 7151(b), 7172(f)) and require authorization under section 202(e) of the FPA (16 U.S.C.824a(e)). On August 31, 1999 the Department of Energy (DOE) issued Order No. EA-216, which authorized TEMUS to transmit electric energy from the United States to

125

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

945 Federal Register 945 Federal Register / Vol. 75, No. 143 / Tuesday, July 27, 2010 / Notices 1 The full text of the Convention on Supplementary Compensation for Nuclear Damage is available at http://www.iaea.org/Publication/ Documents/Infircs/1998/infcirc567.shtml. A detailed interpretation of the CSC and its provisions is contained in ''The 1997 Vienna Convention on Civil Liability for Nuclear Damage and the 1997 Convention on Supplementary Compensation for Nuclear Damage-Explanatory Texts,'' International Atomic Energy Agency (IAEA) (''Explanatory Texts''). International Law Series No. 3 (2007). The Explanatory Texts is available at http://www- pub.iaea.org/MTCD/publications/PDF/ Pub1279_web.pdf . 2 SDR is the unit of account defined by the International Monetary Fund (''IMF'') and used by

126

Document  

NLE Websites -- All DOE Office Websites (Extended Search)

5/R3 5/R3 Toxicological Benchmarks for Screening Contaminants of Potential Concern for Effects on Terrestrial Plants: 1997 Revision This document has been approved by the East Tennessee Technology Park Technical Information Office for release to the public. Date: ES/ER/TM-85/R3 Toxicological Benchmarks for Screening Contaminants of Potential Concern for Effects on Terrestrial Plants: 1997 Revision R. A. Efroymson M. E. Will G. W. Suter II A. C. Wooten Date Issued-November 1997 Prepared for the U.S. Department of Energy Office of Environmental Management under budget and reporting code EW 20 LOCKHEED MARTIN ENERGY SYSTEMS, INC. managing the Environmental Management Activities at the East Tennessee Technology Park Oak Ridge Y-12 Plant Oak Ridge National Laboratory Paducah Gaseous Diffusion Plant

127

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

197 Federal Register 197 Federal Register / Vol. 74, No. 117 / Friday, June 19, 2009 / Notices Instructions: All submissions received must include the agency name, docket number and title for this Federal Register document. The general policy for comments and other submissions from members of the public is to make these submissions available for public viewing on the Internet at http:// www.regulations.gov as they are received without change, including any personal identifiers or contact information. DoD Clearance Officer: Ms. Patricia Toppings. Written requests for copies of the information collection proposal should be sent to Ms. Toppings at WHS/ESD/ Information Management Division, 1777 North Kent Street, RPN, Suite 11000, Arlington, VA 22209-2133. Dated: May 31, 2009.

128

Manpower analysis in transportation safety. Final report  

DOE Green Energy (OSTI)

The project described provides a manpower review of national, state and local needs for safety skills, and projects future manning levels for transportation safety personnel in both the public and private sectors. Survey information revealed that there are currently approximately 121,000 persons employed directly in transportation safety occupations within the air carrier, highway and traffic safety, motor carrier, pipeline, rail carrier, and marine carrier transportation industry groups. The projected need for 1980 is over 145,000 of which over 80 percent will be in highway safety. An analysis of transportation tasks is included, and shows ten general categories about which the majority of safety activities are focused. A skills analysis shows a generally high level of educational background and several years of experience are required for most transportation safety jobs. An overall review of safety programs in the transportation industry is included, together with chapters on the individual transportation modes.

Bauer, C.S.; Bowden, H.M.; Colford, C.A.; DeFilipps, P.J.; Dennis, J.D.; Ehlert, A.K.; Popkin, H.A.; Schrader, G.F.; Smith, Q.N.

1977-05-01T23:59:59.000Z

129

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

70 Federal Register 70 Federal Register / Vol. 73, No. 207 / Friday, October 24, 2008 / Notices and Operational Needs, Funding and U.S. Army COE Section 404 Permit, City of Missoula, Missoula County, MT. Summary: EPA expressed concern about air and water construction impacts and recommended additional analysis and information to fully assess and mitigate impacts of the proposed action. Rating EC2. EIS No. 20080365, ERP No. D-NPS- C61012-NY, Fort Stanwix National Monument General Management Plan, Implementation, Funding, City of Rome, Oneida County, NY. Summary: EPA has no objections to the preferred alternative. Rating LO. Final EISs EIS No. 20080339, ERP No. F-BLM- J65497-UT, Monticello Field Office Resource Management Plan, To Guide the Management of Public Land, Southern two-third of San Juan

130

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5 Federal Register 5 Federal Register / Vol. 73, No. 202 / Friday, October 17, 2008 / Notices DEPARTMENT OF ENERGY Notice of Availability of Draft Global Nuclear Energy Partnership Programmatic Environmental Impact Statement AGENCY: Office of Nuclear Energy, U.S. Department of Energy. ACTION: Notice of Availability and Public Hearings. SUMMARY: The Department of Energy (DOE) announces the availability of the Draft Global Nuclear Energy Partnership Programmatic Environmental Impact Statement (Draft GNEP PEIS, DOE/EIS- 0396). The Draft GNEP PEIS provides an analysis of the potential environmental consequences of the reasonable alternatives to support expansion of domestic and international nuclear energy production while reducing the risks associated with nuclear proliferation and reducing the impacts

131

Document:  

NLE Websites -- All DOE Office Websites (Extended Search)

9 9 Quasi-static Thermoelastic Analysis for a Semi-infinite Plane Subjected to a Gaussian Heat Source - Beam Missteering of the Storage Ring in the APS I. C. Sheng and J. Howell Accelerator Systems Division Advanced Photon Source Argonne National Laboratory 9700 South Cass Ave. Argonne, IL 60439 Abstract A two-dimensional, semi-infinite analytical solution of the transient temperature and the thermal stress due to heating from the bending magnet beam missteering in the APS has been developed. In order to solve the thermal stress analytically, an effective absorption function is introduced, and the transient temperature can be written as a function of the exponential inte- grals. At the origin where the peak power is applied, the effective stress is found to be the maxi-

132

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

266 Federal Register 266 Federal Register / Vol. 72, No. 58 / Tuesday, March 27, 2007 / Notices and outcomes of different internal arrangements and agency decisions. (d) Increased knowledge of ''best VR practices'' for prioritizing and providing services to individuals with the most significant disabilities. The RRTC must contribute to this outcome by conducting research on the extent to which individuals with the most significant disabilities are given priority for services from their respective State VR programs, and identifying best practices among the State VR programs in ensuring that individuals with the most significant disabilities receive services on a priority basis. Collection and analysis of data for this research must be coordinated with and informed by research on the disability

133

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

86 Federal Register 86 Federal Register / Vol. 71, No. 189 / Friday, September 29, 2006 / Rules and Regulations expected to have little effect on U.S. marketers and consumers. Alternatives Considered This rule has been prompted by the need to restrict the importation of PSB host material into the United States from Canada in order to help prevent the introduction of PSB into noninfested areas of the United States. In assessing the need for this rule, we considered several alternatives to the chosen course of action. These alternatives are discussed in the ''Regulatory Flexibility'' section of the full economic analysis. In conclusion, we anticipate limited costs associated with this rule, which is parallel to Canadian restrictions imposed on U.S. exports of PSB host

134

Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

21 Federal Register 21 Federal Register / Vol. 75, No. 88 / Friday, May 7, 2010 / Proposed Rules republication, the NRC will not initiate a second comment period on this action in the event the direct final rule is withdrawn. A significant adverse comment is a comment where the commenter explains why the rule would be inappropriate, including challenges to the rule's underlying premise or approach, or would be ineffective or unacceptable without a change. A comment is adverse and significant if: (1) The comment opposes the rule and provides a reason sufficient to require a substantive response in a notice-and- comment process. For example, a substantive response is required when: (a) The comment causes the NRC staff to reevaluate (or reconsider) its position or conduct additional analysis;

135

DNFSB 2002-1 Software Quality Assurance Improvement Plan Commitment 4.2.1.2: Safety Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2-Criteria 2-Criteria Defense Nuclear Facilities Safety Board Recommendation 2002-1 Software Quality Assurance Improvement Plan Commitment 4.2.1.2: Software Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes U.S. Department of Energy Office of Environment, Safety and Health 1000 Independence Ave., S.W. Washington, DC 20585-2040 November 2003 Software Quality Assurance Criteria for Safety Analysis Codes November 2003 INTENTIONALLY BLANK ii Software Quality Assurance Criteria for Safety Analysis Codes November 2003 FOREWORD This document discusses the Software Quality Assurance plan, and criteria and implementation procedures to be used to evaluate designated, safety-related computer software for the

136

Hot Cell Facility (HCF) Safety Analysis Report  

Science Conference Proceedings (OSTI)

This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.

MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

2000-11-01T23:59:59.000Z

137

Development of an auditable safety analysis in support of a radiological facility classification  

SciTech Connect

In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23.

Kinney, M.D. [Roy F. Weston, Inc., Rockville, MD (United States); Young, B. [Dept. of Energy, Albuquerque, NM (United States)

1995-03-01T23:59:59.000Z

138

Safety analysis report for packaging (onsite) sample pig transport system  

Science Conference Proceedings (OSTI)

This Safety Analysis Report for Packaging (SARP) provides a technical evaluation of the Sample Pig Transport System as compared to the requirements of the U.S. Department of Energy, Richland Operations Office (RL) Order 5480.1, Change 1, Chapter III. The evaluation concludes that the package is acceptable for the onsite transport of Type B, fissile excepted radioactive materials when used in accordance with this document.

MCCOY, J.C.

1999-03-16T23:59:59.000Z

139

GENII Guidance Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

GENII Computer Code GENII Computer Code Application Guidance for Documented Safety Analysis Final Report U.S. Department of Energy Office of Environment, Safety, and Health 1000 Independence Ave., S.W. Washington, DC 20585-2040 July 2004 GENII Guidance Report July 2004 Final Report INTENTIONALLY BLANK ii GENII Guidance Report July 2004 Final Report FOREWORD This document provides guidance to Department of Energy (DOE) facility analysts in the use of the GENII computer code for supporting Documented Safety Analysis applications. Information is provided herein that supplements information found in the GENII documentation provided by the code developer. GENII is one of six computer codes designated by the DOE Office of Environmental, Safety and Health as a toolbox code for safety analysis.

140

Policy and Guidance Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Protection, Sustainability Support & Corporate Safety Analysis Environmental Protection, Sustainability Support & Corporate Safety Analysis HS-20 Home Mission & Functions » Office of Nuclear Safety, Quality Assurance & Environment » Sustainability Support » Environmental Policy & Assistance » Corporate Safety Programs » Analysis Program Contacts What's New? Sustainability Support Environment Corporate Safety Programs Analysis Environment Environmental Policy Environmental Guidance Environmental Reports Environmental Management System Radiation Protection Environmental Compliance Environmental Justice Environmental Training Environmental Tools Search Our Documents Topics & Resources Air Analytical Services Program CERCLA Cultural & Natural Resources DOE Comments on Rulemakings Federal Environmental Laws

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Development of a pilot safety information document (PSID) for the replacement of radioactive liquid waste treatment facility at Los Alamos National Laboratory  

E-Print Network (OSTI)

Based on recent decisions made by Los Alamos National Laboratory concerning the development of site-wide National Environmental Policy Act documents, an effort was undertaken to develop a Pilot Safety Information Document (PSID) for the replacement Radioactive Liquid Waste Treatment Facility. The PSID documents risk analysis for the proposed facility and some of the alternatives, accident analysis, radioactive and hazardous material doses to off-site individuals, and the cumulative safety risk from adjacent facilities. In addition, this study also compared two methods for calculating the consequences of a radioactive spill. The methods compared were the Superfund model and the release fraction model. It was determined that the release fraction model gives a more realistic estimate of the doses incurred as the result of an accident, and that the Superfund model should be used for estimating the dose before and during the remediation effort. The cumulative safety risk was determined by calculating the exceedance probability if the individual dose from four geographically related facilities. The risk for cancer fatalities was determined to be within the DOE's Nuclear Safety Policy Goals.

Selvage, Ronald Derek

1995-01-01T23:59:59.000Z

142

Washington TRU Solutions - Job Safety/Hazard Analysis Booklet  

NLE Websites -- All DOE Office Websites (Extended Search)

participation is important to efficient, safe, and increased productivity. Through the process of Job Safety Analysis, these benefits are fully realized. Job Safety Analysis can...

143

FACILITY WORKER TECHNICAL BASIS DOCUMENT  

Science Conference Proceedings (OSTI)

This technical basis document was developed to support RPP-13033, ''Tank Farms Documented Safety Analysis (DSA). It describes the criteria and methodology for allocating controls to hazardous conditions with significant facility worker (FW) consequence and presents the results of the allocation. The criteria and methodology for identifying controls that address FW safety are in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''.

SHULTZ, M.V.

2005-03-31T23:59:59.000Z

144

Web Document Analysis for Companies Listed in Bursa Malaysia  

E-Print Network (OSTI)

This paper discusses a research on web document analysis for companies listed on Bursa Malaysia which is the forerunner of financial and investment center in Malaysia. Data set used in this research are from the company web documents listed in the Main Board and Second Board on Bursa Malaysia. This research has used the Web Resources Extraction System which was developed by the research group mainly to extract information for the web documents involved. Our research findings have shown that the level of website usage among the companies on Bursa Malaysia is still minimal. Furthermore, research has also found that 60.02 percent of the image files are utilized making it the most used type of file in creating websites.

Othman, Mohd Shahizan; Salim, Juhana

2009-01-01T23:59:59.000Z

145

FFTF Final Safety Analysis Report Amendment 81 [SEC 1 & 2  

Science Conference Proceedings (OSTI)

Since the last reactor operation of FFTF in March of 1992, the FFTF has either been in a programmatic status of Standby or Shutdown. The facility hazards have decreased markedly. Rather than making extensive Final Safety Analysis Report (FSAR) changes, Appendix G was prepared to reflect the design and operation during Standby or Shutdown. Appendix G describes the application of the entire FSAR for the current configuration, accounting for the natural reduction in hazards and new system configurations associated with Standby/Shutdown. The technical system chapters and the safety analysis chapter of the FSAR describe how the design and operation fulfilled the requirements necessary to support reactor operation; this information is retained for design basis and historical information. This Final Safety Analysis Report (FSAR) is submitted per the requirements of Paragraph 014, Energy Research and Development Administration (ERDA) Manual Chapter 0540, ''Safety of ERDA-Owned Reactors.'' This FSAR and its supporting documentation provide a complete description and safety evaluation of the site, plant design, normal and emergency operations, potential accidents and predicted consequences of such accidents, and the means that will prevent such accidents and/or reduce their consequences to an acceptable level.

DAUTEL, W.A.

2002-01-10T23:59:59.000Z

146

Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)  

Science Conference Proceedings (OSTI)

The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: {sm_bullet} Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) {sm_bullet} Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as {open_quotes}low{close_quotes} hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with {open_quotes}moderate{close_quotes} or {open_quotes}high{close_quotes} hazard classifications.

NONE

1995-09-01T23:59:59.000Z

147

ACCIDENT ANALYSES & CONTROL OPTIONS IN SUPPORT OF THE SLUDGE WATER SYSTEM SAFETY ANALYSIS  

Science Conference Proceedings (OSTI)

This report documents the accident analyses and nuclear safety control options for use in Revision 7 of HNF-SD-WM-SAR-062, ''K Basins Safety Analysis Report'' and Revision 4 of HNF-SD-SNF-TSR-001, ''Technical Safety Requirements - 100 KE and 100 KW Fuel Storage Basins''. These documents will define the authorization basis for Sludge Water System (SWS) operations. This report follows the guidance of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', for calculating onsite and offsite consequences. The accident analysis summary is shown in Table ES-1 below. While this document describes and discusses potential control options to either mitigate or prevent the accidents discussed herein, it should be made clear that the final control selection for any accident is determined and presented in HNF-SD-WM-SAR-062.

WILLIAMS, J.C.

2003-11-15T23:59:59.000Z

148

DOE-NE-STD-1004-92; Root Cause Analysis Guidance Document  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NE-STD-1004-92 NE-STD-1004-92 DOE GUIDELINE ROOT CAUSE ANALYSIS GUIDANCE DOCUMENT February 1992 U.S. Department of Energy Office of Nuclear Energy Office of Nuclear Safety Policy and Standards Washington, D.C. 20585 ii ABSTRACT DOE Order 5000.3A, "Occurrence Reporting and Processing of Operations Information," investigation and reporting of occurrences (including the performance of root cause analysis) requires the and the selection, implementation, and follow-up of corrective actions. The level of effort expended should be based on the significance attached to the occurrence. Most off-normal occurrences need only a scaled- down effort while most emergency occurrences should be investigated using one or more of the formal analytical models. A discussion of methodologies, instructions, and worksheets in this document guides

149

Review of Documented Safety Analysis Development for the Hanford...  

NLE Websites -- All DOE Office Websites (Extended Search)

surveillance requirements, administrative controls, and specific administrative controls provided and technically accurate? * Are the facility design aspects necessary to...

150

Safety of ncker's strictness analysis  

Science Conference Proceedings (OSTI)

This paper proves correctness of Ncker's method of strictness analysis, implemented in the Clean compiler, which is an effective way for strictness analysis in lazy functional languages based on their operational semantics. We improve upon the ...

Manfred Schmidt-schauss; David Sabel; Marko Schtz

2008-07-01T23:59:59.000Z

151

The HABS Culture of Documentation with an Analysis of Drawing and Technology  

E-Print Network (OSTI)

The Historic American Buildings Survey (HABS) is one of the oldest federal programs in the United States. In 1933, the HABS culture of documentation started with the mission of creating a permanent record of the nation's architectural heritage. Since the inception of the program, the formal documentation methodology has been measured drawings, large-format photographs, and written histories. HABS documentation accentuates the act of drawing as a mediating conversation between the documenter and the historic environment. In a typical HABS project, the documenter is immersed in the historic setting by hand measuring the structure and creating field notes. The documenter's intimate access to the artifact develops his awareness of cultural heritage and helps cultivate an appreciation for the compositional sensibilities of the architectural precedents. However, the HABS culture of documentation has been fine-tuned to incorporate a number of digital technologies into documentation projects. When projects involve issues of logistics, time, and cost, HABS professionals utilize a host of digital methodologies to produce measured drawings. Although HABS prepares deliverables to meet the archival standards of the Library of Congress, the hardware and software necessary to recognize digital files have a limited lifespan that makes them unacceptable for use in the Library. Only measured drawings that use archival ink on stable translucent material, accompanied by negatives on safety film, can be submitted to the Library. Thus, if HABS pursued only digital technologies and deliverables, the effects of this approach on the quality of the documenter's engagement with cultural heritage would pose a significant question. This study addressed the question of how the HABS culture of documentation evolved in regards to drawing and technology, and how this relationship might be transformed in the future. Using HABS as a focus of inquiry is important in order to illuminate similar dynamics in heritage projects that utilize digital technologies. The methodology used in this study included a literature review, participant observations, and an analysis of documentation projects, as well as in-depth interviews with HABS staff, project participants, private practitioners, and academicians. The outcome of the study will be recommendations to heritage professionals for a future that resides in digital means without compromising the qualities that the HABS experience has offered to generation of documenters.

Akboy, Serra

2011-12-01T23:59:59.000Z

152

Facility worker technical basis document  

SciTech Connect

This report documents the technical basis for facility worker safety to support the Tank Farms Documented Safety Analysis and described the criteria and methodology for allocating controls to hazardous conditions with significant facility worker consequences and presents the results of the allocation.

EVANS, C.B.

2003-03-21T23:59:59.000Z

153

Test Protocol Document, Hydrogen Safety Sensor Testing; Phase I: Non-Flammable Mixtures  

DOE Green Energy (OSTI)

This test protocol document includes an overview of hydrogen sensor technologies, test hardware requrements, and an outline of potential testing.

Burgess, R.; Blake, C.; Tracy, C. E.

2008-09-01T23:59:59.000Z

154

Safety Analysis, Hazard and Risk Evaluations [Nuclear Waste Management  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Analysis, Hazard Safety Analysis, Hazard and Risk Evaluations Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Safety Analysis, Hazard and Risk Evaluations Bookmark and Share NE Division personnel had a key role in the creation of the FCF Final Safety Analysis Report (FSAR), FCF Technical Safety Requirements (TSR)

155

H:\\Transfer\\My Documents\\Cleary Fire Report\\Annual Fire Safety Report 2012.doc Annual Fire Safety Report  

E-Print Network (OSTI)

St North & Hillside which includes Fairmount Towers, the Child Development Center and a vacant lot locked and alarmed, 24 hours a day. The Housing and Residence Life Handbook describes safety, security alcohol and substance abuse violations. The Housing and Residence Life Handbook describes the Judicial

Sze, Lawrence

156

Worker Safety and Health and Nuclear Safety Quarterly Performance Analysis (January - March 2008)  

Science Conference Proceedings (OSTI)

The DOE Office of Enforcement expects LLNL to 'implement comprehensive management and independent assessments that are effective in identifying deficiencies and broader problems in safety and security programs, as well as opportunities for continuous improvement within the organization' and to 'regularly perform assessments to evaluate implementation of the contractor's processes for screening and internal reporting.' LLNL has a self-assessment program, described in ES&H Manual Document 4.1, that includes line, management and independent assessments. LLNL also has in place a process to identify and report deficiencies of nuclear, worker safety and health and security requirements. In addition, the DOE Office of Enforcement expects LLNL to evaluate 'issues management databases to identify adverse trends, dominant problem areas, and potential repetitive events or conditions' (page 14, DOE Enforcement Process Overview, December 2007). LLNL requires that all worker safety and health and nuclear safety noncompliances be tracked as 'deficiencies' in the LLNL Issues Tracking System (ITS). Data from the ITS are analyzed for worker safety and health (WSH) and nuclear safety noncompliances that may meet the threshold for reporting to the DOE Noncompliance Tracking System (NTS). This report meets the expectations defined by the DOE Office of Enforcement to review the assessments conducted by LLNL, analyze the issues and noncompliances found in these assessments, and evaluate the data in the ITS database to identify adverse trends, dominant problem areas, and potential repetitive events or conditions. The report attempts to answer three questions: (1) Is LLNL evaluating its programs and state of compliance? (2) What is LLNL finding? (3) Is LLNL appropriately managing what it finds? The analysis in this report focuses on data from the first quarter of 2008 (January through March). This quarter is analyzed within the context of information identified in previous quarters to include April 2007 through March 2008. The results from analyzing the deficiencies are presented in accordance with the two primary NTS reporting thresholds for WSH and nuclear safety noncompliances: (1) those related to certain events or conditions and (2) those that are management issues. In addition, WSH noncompliances were also analyzed to determine if any fell under the 'other significant condition' threshold. This report also identifies noncompliance topical areas that may have issues that do not meet the NTS reporting threshold but should remain under observation. These are placed on the 'watch list' for continued analysis.

Kerr, C E

2009-10-07T23:59:59.000Z

157

Surveillance Analysis Computer System (SACS) software design document (SDD)  

SciTech Connect

This document contains the Software Design Description for Phase II of the SACS project, and Impact Level 3Q system

Glasscock, J.A.

1995-09-01T23:59:59.000Z

158

Safety Bulletin  

NLE Websites -- All DOE Office Websites (Extended Search)

those analyzed in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and...

159

Risk D&D Rapid Prototype: Scenario Documentation and Analysis Tool  

SciTech Connect

Report describes process and methodology associated with a rapid prototype tool for integrating project risk analysis and health & safety risk analysis for decontamination and decommissioning projects.

Unwin, Stephen D.; Seiple, Timothy E.

2009-05-28T23:59:59.000Z

160

GCtool for fuel cell systems design and analysis : user documentation.  

DOE Green Energy (OSTI)

GCtool is a comprehensive system design and analysis tool for fuel cell and other power systems. A user can analyze any configuration of component modules and flows under steady-state or dynamic conditions. Component models can be arbitrarily complex in modeling sophistication and new models can be added easily by the user. GCtool also treats arbitrary system constraints over part or all of the system, including the specification of nonlinear objective functions to be minimized subject to nonlinear, equality or inequality constraints. This document describes the essential features of the interpreted language and the window-based GCtool environment. The system components incorporated into GCtool include a gas flow mixer, splitier, heater, compressor, gas turbine, heat exchanger, pump, pipe, diffuser, nozzle, steam drum, feed water heater, combustor, chemical reactor, condenser, fuel cells (proton exchange membrane, solid oxide, phosphoric acid, and molten carbonate), shaft, generator, motor, and methanol steam reformer. Several examples of system analysis at various levels of complexity are presented. Also given are instructions for generating two- and three-dimensional plots of data and the details of interfacing new models to GCtool.

Ahluwalia, R.K.; Geyer, H.K.

1999-01-15T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

340 Waste handling Facility Hazard Categorization and Safety Analysis  

DOE Green Energy (OSTI)

The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3.

T. J. Rodovsky

2010-10-25T23:59:59.000Z

162

ASD Facility Hazard Analysis Document - Building 400-EAA  

NLE Websites -- All DOE Office Websites (Extended Search)

-EAA -EAA Equipment Hazards Engineered Controls Electrical Safety Training References Electrical Safety Procedures Mechanical Safety Training References Mechanical Safety Procedures Radiological, Environmental & Chemical Training References Radiological, Environmental & Chemical Procedures Additional Safety Tool References Blue Oven Temperature to 600° F voltage 208 VAC Signage 1 NA 6, 7 Physical Agents Training NA NA NA A ASD108/400 Compressed Air Line 65-130 PSI Regulator Pressure relief NA NA 6, 7 ESH119 NA NA A ASD108/400 Various Shop Tools (lathe, drill press, grinder, belt sander, shears, hand tools) Eye hazard Pinch points Abrasive Rotating machinery 120 VAC Hydraulic pressure Guarding Anti-restart devices 1 NA 6, 7 NA NA NA A ASD108/400 Water Flow Test Stand Pressure Slip hazard NA

163

A ''Toolbox''21 Equivalent Process for Safety Analysis Software  

Science Conference Proceedings (OSTI)

Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1 (Quality Assurance for Safety-Related Software) identified a number of quality assurance issues on the use of software in Department of Energy (DOE) facilities for analyzing hazards, and designing and operating controls that prevent or mitigate potential accidents. The development and maintenance of a collection, or ''toolbox,'' of multiple-site use, standard solution, Software Quality Assurance (SQA)-compliant safety software is one of the major improvements identified in the associated DOE Implementation Plan (IP). The DOE safety analysis toolbox will contain a set of appropriately quality-assured, configuration-controlled, safety analysis codes, recognized for DOE-broad, safety basis applications. Currently, six widely applied safety analysis computer codes have been designated for toolbox consideration. While the toolbox concept considerably reduces SQA burdens among DOE users of these codes, many users of unique, single-purpose, or single-site software may still have sufficient technical justification to continue use of their computer code of choice, but are thwarted by the multiple-site condition on toolbox candidate software. The process discussed here provides a roadmap for an equivalency argument, i.e., establishing satisfactory SQA credentials for single-site software that can be deemed ''toolbox-equivalent''. The process is based on the model established to meet IP Commitment 4.2.1.2: Establish SQA criteria for the safety analysis ''toolbox'' codes. Implementing criteria that establish the set of prescriptive SQA requirements are based on implementation plan/procedures from the Savannah River Site, also incorporating aspects of those from the Waste Isolation Pilot Plant (SNL component) and the Yucca Mountain Project. The major requirements are met with evidence of a software quality assurance plan, software requirements and design documentation, user's instructions, test report, a configuration and control procedure, an error notification and corrective action process, and evidence of available training on use of the software. The process is best performed with an independent SQA evaluator, i.e., a technically knowledgeable individual in the application area who is not part of the development team. The process provides a consistent, systematic approach based on the experience gained with SQA evaluations of the toolbox codes. Experience has shown that rarely will existing software be fully compliant with SQA criteria. Instead, the typical case is where SQA elements are deficient. For this case, it is recommended that supplemental remedial documentation be generated. Situations may also arise where the SQA evaluator must weigh whether the entire SQA suite be reconstituted. Regardless, the process is described sufficiently to guide a comprehensive evaluation. If the candidate software is successful in meeting process requirements, the software is ''toolbox-equivalent''. The benefit of the methodology outlined is that it provides a standard evaluation technique for choosing the most applicable software for a given application. One potential outcome is that the software of choice will be found to be applicable with ample SQA justification. Alternatively, the software in question may be found not to meet SQA process requirements. In this case, the analyst may then make an informed decision and possibly select one of the multiple-use, toolbox codes. With either outcome, the DSA is improved.

O'KULA, KR

2004-04-30T23:59:59.000Z

164

Preliminary Safety Analysis Report for the Transuranic Storage Area Retrieval Enclosure at the Idaho National Engineering Laboratory. Revision 8  

SciTech Connect

This Transuranic Storage Area Retrieval Enclosure Preliminary Safety Analysis Report was completed as required by DOE Order 5480.23. The purpose of this document is to construct a safety basis that supports the design and permits construction of the facility. The facility has been designed to the requirements of a Radioactive Solid Waste Facility presented in DOE Order 6430.1A.

1993-03-01T23:59:59.000Z

165

Rankine bottoming cycle safety analysis. Final report  

SciTech Connect

Vector Engineering Inc. conducted a safety and hazards analysis of three Rankine Bottoming Cycle Systems in public utility applications: a Thermo Electron system using Fluorinal-85 (a mixture of 85 mole % trifluoroethanol and 15 mole % water) as the working fluid; a Sundstrand system using toluene as the working fluid; and a Mechanical Technology system using steam and Freon-II as the working fluids. The properties of the working fluids considered are flammability, toxicity, and degradation, and the risks to both plant workers and the community at large are analyzed.

Lewandowski, G.A.

1980-02-01T23:59:59.000Z

166

Mechanistic facility safety and source term analysis  

SciTech Connect

A PC-based computer program was created for facility safety and source term analysis at Hanford The program has been successfully applied to mechanistic prediction of source terms from chemical reactions in underground storage tanks, hydrogen combustion in double contained receiver tanks, and proccss evaluation including the potential for runaway reactions in spent nuclear fuel processing. Model features include user-defined facility room, flow path geometry, and heat conductors, user-defined non-ideal vapor and aerosol species, pressure- and density-driven gas flows, aerosol transport and deposition, and structure to accommodate facility-specific source terms. Example applications are presented here.

PLYS, M.G.

1999-06-09T23:59:59.000Z

167

Oversight Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

26, 2013 26, 2013 Independent Oversight Review, Hanford Tank Farms - April 2013 Review of Management of Safety Systems at the Hanford Tank Farms April 25, 2013 CRAD, Documented Safety Analysis Development - April 23, 2013 Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immobilization Plant (LBL Facilities) (HSS CRAD 45-58, Rev. 0) April 23, 2013 Independent Activity Report, Los Alamos National Laboratory - April 2013 Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report [HIAR-LANL-2013-04-08] April 22, 2013 Independent Oversight Review, Waste Isolation Pilot Plant - April 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control

168

An enhanced framework of subjective logic for semantic document analysis  

Science Conference Proceedings (OSTI)

Unlike propositional logic which works on truth or falsity of statements, human judgements are subjective in nature having certain degree of uncertainty. Two different people will analyse and interpret a document in two different ways based on their ...

Sukanya Manna; B. Sumudu. U. Mendis; Tom Gedeon

2010-10-01T23:59:59.000Z

169

Microsoft Word - Nuclear Safety Reporting Criteria.docx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of other TSROSR requirement (3) Violation of DSA hazard control B. Documented Safety Analysis (DSA) Inadequacies (1) Positive unreviewed safety question C. Nuclear Criticality...

170

Multichannel blind separation and deconvolution of images for document analysis  

Science Conference Proceedings (OSTI)

In this paper, we apply Bayesian blind source separation (BSS) from noisy convolutive mixtures to jointly separate and restore source images degraded through unknown blur operators, and then linearly mixed. We found that this problem arises in several ... Keywords: Markov random fields (MRFs), blind image deconvolution, blind source separation, document image processing, parameter learning

Anna Tonazzini; Ivan Gerace; Francesca Martinelli

2010-04-01T23:59:59.000Z

171

Hazard Analysis Database report  

Science Conference Proceedings (OSTI)

This document describes and defines the Hazard Analysis Database for the Tank Waste Remediation System Final Safety Analysis Report.

Niemi, B.J.

1997-08-12T23:59:59.000Z

172

Aviation Safety and Air Traffic Management Analysis - Center...  

NLE Websites -- All DOE Office Websites (Extended Search)

support tools. Visualization and analysis of diverse data sources including flight track, weather, airport, aircraft, ATM elements and geographic data supports aviation safety...

173

Office of Safety and Emergency Management Evaluations Protocol for the Development and Maintenance of Criteria and Review Approach Documents, July 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

<: <: iisS Offlct of Hulth , S.ftly ind St curity OFFICE OF SAFETY AND EMERGENCY MANAGEMENT EVALUATIONS PROTOCOL FOR THE DEVELOPMENT AND MAINTENANCE OF CRITERIA AND REVIEW APPROACH DOCUMENTS July 2013 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Office of Safety and Emergency Management Evaluations Protocol for the Development and Maintenance of Criteria and Review Approach Documents July 2013 Reviewed by: 1 .. ~~·\? Approved by: William E. Mi.lier Date Deputy Director Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight /\ Thomas R. Stak~r Deputy Director for Oversight Office of Enforcement and Oversight Office of Health, Safety and Security

174

Phase 2 safety analysis report: National Synchrotron Light Source  

SciTech Connect

The Phase II program was established in order to provide additional space for experiments, and also staging and equipment storage areas. It also provides additional office space and new types of advanced instrumentation for users. This document will deal with the new safety issues resulting from this extensive expansion program, and should be used as a supplement to BNL Report No. 51584 ''National Synchrotron Light Source Safety Analysis Report,'' July 1982 (hereafter referred to as the Phase I SAR). The initial NSLS facility is described in the Phase I SAR. It comprises two electron storage rings, an injection system common to both, experimental beam lines and equipment, and office and support areas, all of which are housed in a 74,000 sq. ft. building. The X-ray Ring provides for 28 primary beam ports and the VUV Ring, 16. Each port is capable of division into 2 or 3 separate beam lines. All ports receive their synchrotron light from conventional bending magnet sources, the magnets being part of the storage ring lattice. 4 refs.

Stefan, P. (ed.)

1989-06-01T23:59:59.000Z

175

Dataplot Documentation  

Science Conference Proceedings (OSTI)

... Linear Fitting, Data Analysis, and Mathematics", Proceedings of the ... the printed tutorial documentation does not describe ... Filliben, James J. (1981). ...

2013-11-27T23:59:59.000Z

176

Criteria Review and Approach Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criteria Review and Approach Documents Criteria Review and Approach Documents Criteria Review and Approach Documents May 31, 2013 CRAD, Criticality Safety Controls Implementation - May 31, 2013 Criticality Safety Controls Implementation with DOE activities and sites (HSS CRAD 45-18) May 6, 2013 CRAD, Review of Safety Basis Development - May 6, 2013 Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility (HSS CRAD 45-59, Rev. 0) April 25, 2013 CRAD, Documented Safety Analysis Development - April 23, 2013 Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immobilization Plant (LBL Facilities) (HSS CRAD 45-58, Rev. 0) February 1, 2013 CRAD, Review of Safety Basis Development - January 31, 2013 Review of Safety Basis Development for the Savannah River Site Salt Waste

177

Accident analysis and safety review of DOE Category B reactors  

SciTech Connect

DOE is employing the principle of comparability with the NRC requirements to guide its safety program. Since the safety record of research reactors licensed by the NRC has been established and accepted, the comparison of DOE Orders applicable to DOE research reactors with the NRC regulations applicable to research reactors would identify strengths and weaknesses of the DOE Orders. The comparison was made in 14 general topics of safety which are labeled Areas of Safety Concerns. This paper focuses on the Area of accident analysis and safety review and presents recommendations in these areas. 12 refs.

Kimura, C.Y.

1990-08-07T23:59:59.000Z

178

Analysis & Projections - Models & Documentation - U.S. Energy...  

Annual Energy Outlook 2012 (EIA)

U.S. Energy Information Administration - EIA - Independent Statistics and Analysis Sources & Uses Petroleum & Other Liquids Crude oil, gasoline, heating oil, diesel, propane, and...

179

Analysis and decision document in support of acquisition of steam supply for the Hanford 200 Area  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) is now evaluating its facility requirements in support of its cleanup mission at Hanford. One of the early findings is that the 200-Area steam plants, constructed in 1943, will not meet future space heating and process needs. Because the 200 Area will serve as the primary area for waste treatment and long-term storage, a reliable steam supply is a critical element of Hanford operations. This Analysis and Decision Document (ADD) is a preliminary review of the steam supply options available to the DOE. The ADD contains a comprehensive evaluation of the two major acquisition options: line-term versus privatization. It addresses the life-cycle costs associated with each alternative, as well as factors such as contracting requirements and the impact of market, safety, security, and regulatory issues. Specifically, this ADD documents current and future steam requirements for the 200 Area, describes alternatives available to DOE for meeting these requirements, and compares the alternatives across a number of decision criteria, including life-cycle cost. DOE has currently limited the ADD evaluation alternatives to replacing central steam plants rather than expanding the study to include alternative heat sources, such as a distributed network of boilers or heat pumps. Thirteen project alternatives were analyzed in the ADD. One of the alternatives was the rehabilitation of the existing 200-East coal-fired facility. The other twelve alternatives are combinations of (1) coal- or gas-fueled plants, (2) steam-only or cogeneration facilities, (3) primary or secondary cogeneration of electricity, and (4) public or private ownership.

Brown, D.R.; Daellenbach, K.K.; Hendrickson, P.L.; Kavanaugh, D.C.; Reilly, R.W.; Shankle, D.L.; Smith, S.A.; Weakley, S.A.; Williams, T.A. [Pacific Northwest Lab., Richland, WA (United States); Grant, T.F. [Battelle Human Affairs Research Center, Seattle, WA (United States)

1992-02-01T23:59:59.000Z

180

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10 Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10 Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is intended as an information source for the NRC and should serve as a foundation for discussion with industry representatives on the issue. This paper concludes that an ISA is a risk-informed, performance-based way of achieving and maintaining safety at fuel recycling facilities. As

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

PAT-1 safety analysis report addendum.  

SciTech Connect

The Plutonium Air Transportable Package, Model PAT-1, is certified under Title 10, Code of Federal Regulations Part 71 by the U.S. Nuclear Regulatory Commission (NRC) per Certificate of Compliance (CoC) USA/0361B(U)F-96 (currently Revision 9). The purpose of this SAR Addendum is to incorporate plutonium (Pu) metal as a new payload for the PAT-1 package. The Pu metal is packed in an inner container (designated the T-Ampoule) that replaces the PC-1 inner container. The documentation and results from analysis contained in this addendum demonstrate that the replacement of the PC-1 and associated packaging material with the T-Ampoule and associated packaging with the addition of the plutonium metal content are not significant with respect to the design, operating characteristics, or safe performance of the containment system and prevention of criticality when the package is subjected to the tests specified in 10 CFR 71.71, 71.73 and 71.74.

Weiner, Ruth F.; Schmale, David T.; Kalan, Robert J.; Akin, Lili A.; Miller, David Russell; Knorovsky, Gerald Albert; Yoshimura, Richard Hiroyuki; Lopez, Carlos; Harding, David Cameron; Jones, Perry L.; Morrow, Charles W.

2010-09-01T23:59:59.000Z

182

Model documentation of the Short-Term Coal Analysis System  

Science Conference Proceedings (OSTI)

The short-term coal analysis system (SCOAL) is used by the Data Analysis and Forecasting Branch (DAFB) as an analytic aid to support preparation of short-term projections of bituminous coal and lignite production at the state level, and anthracite production, domestic imports of coal, and domestic and export demand for US coal at the national level. A description of SCOAL is presented which includes a general overview of the model and its analytical capabilities. (DMC)

Not Available

1983-04-01T23:59:59.000Z

183

ARM - Publications: Science Team Meeting Documents: Using EOF analysis to  

NLE Websites -- All DOE Office Websites (Extended Search)

Using EOF analysis to uncover inhomogeneities in data from ground-based Using EOF analysis to uncover inhomogeneities in data from ground-based aerosol monitoring devices Gianelli, Scott NASA/GISS Carlson, Barbara NASA/Goddard Institute for Space Studies Lacis, Andrew NASA/Goddard Institute for Space Studies Empirical Orthogonal Function (EOF) analysis is performed on ground-based shadowband and sun photometer data. The instruments examined for this study include the Rotating Shadowband Spectroradiometer (RSS) and the CIMEL sun photometer CSPHOT located at the central facility of the Southern Great Plains (SGP) site; networks of Multi-Filter Rotating Shadowband Radiometer (MFRSR) devices sponsored by ARM and the USDA; and the network of nephelometers and aerosol particle counters of the Climate Monitoring Diagnostics Laboratory (CMDL). The original purpose of this investigation

184

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

SciTech Connect

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

None

1996-12-01T23:59:59.000Z

185

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

Science Conference Proceedings (OSTI)

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

None

1996-12-01T23:59:59.000Z

186

Project Cost Escalation Standards, document IEAB 2007-2 Page 1 Independent Economic Analysis Board  

E-Print Network (OSTI)

Project Cost Escalation Standards, document IEAB 2007-2 Page 1 Independent Economic Analysis Board Project Cost Escalation Standards Task 115 Council document IEAB 2007-2 March 30, 2007 Summary Project costs as described in project proposals sometimes turn out to be inaccurate. One source of error

187

Investigative analysis across documents and drawings: visual analytics for archaeologists  

Science Conference Proceedings (OSTI)

With the invention and rapid improvement of data-capturing devices, such as satellite imagery and digital cameras, the information that archaeologists must manage in their everyday's activities has rapidly grown in complexity and amount. In this work ... Keywords: information visualization, investigative analysis, rock art archaeology, visual analytics

V. Deufemia; L. Paolino; G. Tortora; A. Traverso; V. Mascardi; M. Ancona; M. Martelli; N. Bianchi; H. De Lumley

2012-05-01T23:59:59.000Z

188

Safety analysis of the UTSI-CFFF superconducting magnet  

DOE Green Energy (OSTI)

In designing a large superconducting magnet such as the UTSI-CFFF dipole, great attention must be devoted to the safety of the magnet and personnel. The conductor for the UTSI-CFFF magnet incorporates much copper stabilizer, which both insures its cryostability, and contributes to the magnet safety. The quench analysis and the cryostat fault condition analysis are presented. Two analyses of exposed turns follow; the first shows that gas cooling protects uncovered turns; the second, that the cryostat pressure relief system protects them. Finally the failure mode and safety analysis is presented.

Turner, L.R.; Wang, S.T.; Smith, R.P.; VanderArend, P.C.; Hsu, Y.H.

1979-01-01T23:59:59.000Z

189

WIPP Documents - Nuclear Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

workers, and the environment. The WIPP DSA demonstrates the extent to which the Waste Isolation Pilot Plant can be operated safely with respect to workers, the public, and the...

190

Evolutionary safety analysis: motivations from the air traffic management domain  

E-Print Network (OSTI)

Abstract. In order realistically and cost-effectively to realize the ATM (Air Traffic Management) 2000+ Strategy, systems from different suppliers will be interconnected to form a complete functional and operational environment, covering ground segments and aerospace. Industry will be involved as early as possible in the lifecycle of ATM projects. EURO-CONTROL manages the processes that involve the definition and validation of new ATM solutions using Industry capabilities (e.g., SMEs). In practice, safety analyses adapt and reuse system design models (produced by third parties). Technical, organisational and cost-related reasons often determine this choice, although design models are unfit for safety analysis. Design models provide limited support to safety analysis, because they are tailored for system designers. The definition of an adequate model and of an underlying methodology for its construction will be highly beneficial for whom is performing safety analyses. Limited budgets and resources, often, constrain or inhibit the model definition phase as an integral part of safety analysis. This paper is concerned with problems in modeling ATM systems for safety analysis. The main objective is to highlight a model specifically targeted to support evolutionary safety analysis. 1

Massimo Felici

2005-01-01T23:59:59.000Z

191

DOE Order Self Study Modules - DOE-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facilities Documented Safety Analyses  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3009-94 3009-94 PREPARATION GUIDE FOR U.S. DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES DOE-STD-3009-94 Familiar Level June 2011 1 DOE-STD-3009-94 PREPARATION GUIDE FOR U.S. DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES FAMILIAR LEVEL _______________________________________________________________________________ OBJECTIVES Given the familiar level of this module and the resources listed below, you will be able to answer the following questions: 1. What are five general requirements for contractors who are responsible for a hazard category 1, 2, or 3 nuclear facility, as related to establishing a safety basis? 2. What actions must a contractor take when it is made aware of a potential inadequacy of

192

Review of Management of Safety Systems at the Hanford Tank Farms...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Maintenance CRAD Criteria, Review and Approach Document CSE Cognizant System Engineer DOE U.S. Department of Energy DSA Documented Safety Analysis DST Double Shell Tank EIR...

193

Process hazards analysis (PrHA) program, bridging accident analyses and operational safety  

SciTech Connect

Recently the Final Safety Analysis Report (FSAR) for the Plutonium Facility at Los Alamos National Laboratory, Technical Area 55 (TA-55) was revised and submitted to the US. Department of Energy (DOE). As a part of this effort, over seventy Process Hazards Analyses (PrHAs) were written and/or revised over the six years prior to the FSAR revision. TA-55 is a research, development, and production nuclear facility that primarily supports US. defense and space programs. Nuclear fuels and material research; material recovery, refining and analyses; and the casting, machining and fabrication of plutonium components are some of the activities conducted at TA-35. These operations involve a wide variety of industrial, chemical and nuclear hazards. Operational personnel along with safety analysts work as a team to prepare the PrHA. PrHAs describe the process; identi fy the hazards; and analyze hazards including determining hazard scenarios, their likelihood, and consequences. In addition, the interaction of the process to facility systems, structures and operational specific protective features are part of the PrHA. This information is rolled-up to determine bounding accidents and mitigating systems and structures. Further detailed accident analysis is performed for the bounding accidents and included in the FSAR. The FSAR is part of the Documented Safety Analysis (DSA) that defines the safety envelope for all facility operations in order to protect the worker, the public, and the environment. The DSA is in compliance with the US. Code of Federal Regulations, 10 CFR 830, Nuclear Safety Management and is approved by DOE. The DSA sets forth the bounding conditions necessary for the safe operation for the facility and is essentially a 'license to operate.' Safely of day-to-day operations is based on Hazard Control Plans (HCPs). Hazards are initially identified in the PrI-IA for the specific operation and act as input to the HCP. Specific protective features important to worker safety are incorporated so the worker can readily identify the safety parameters of the their work. System safety tools such as Preliminary Hazard Analysis, What-If Analysis, Hazard and Operability Analysis as well as other techniques as necessary provide the groundwork for both determining bounding conditions for facility safety, operational safety, and day-to-clay worker safety.

Richardson, J. A. (Jeanne A.); McKernan, S. A. (Stuart A.); Vigil, M. J. (Michael J.)

2003-01-01T23:59:59.000Z

194

Computational methods for criticality safety analysis within the scale system  

SciTech Connect

The criticality safety analysis capabilities within the SCALE system are centered around the Monte Carlo codes KENO IV and KENO V.a, which are both included in SCALE as functional modules. The XSDRNPM-S module is also an important tool within SCALE for obtaining multiplication factors for one-dimensional system models. This paper reviews the features and modeling capabilities of these codes along with their implementation within the Criticality Safety Analysis Sequences (CSAS) of SCALE. The CSAS modules provide automated cross-section processing and user-friendly input that allow criticality safety analyses to be done in an efficient and accurate manner. 14 refs., 2 figs., 3 tabs.

Parks, C.V.; Petrie, L.M.; Landers, N.F.; Bucholz, J.A.

1986-01-01T23:59:59.000Z

195

MODEL 9977 B(M)F-96 SAFETY ANALYSIS REPORT FOR PACKAGING  

Science Conference Proceedings (OSTI)

This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on and for the 9977 Shipping Package, referred to as the General Purpose Fissile Package (GPFP). The performance evaluation presented in this SARP documents the compliance of the 9977 package with the regulatory safety requirements for Type B packages. Per 10 CFR 71.59, for the 9977 packages evaluated in this SARP, the value of ''N'' is 50, and the Transport Index based on nuclear criticality control is 1.0. The 9977 package is designed with a high degree of single containment. The 9977 complies with 10 CFR 71 (2002), Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10 CFR 20 (2003) for As Low As Reasonably Achievable (ALARA) principles. The 9977 also satisfies the requirements of the Regulations for the Safe Transport of Radioactive Material--1996 Edition (Revised)--Requirements. IAEA Safety Standards, Safety Series No. TS-R-1 (ST-1, Rev.), International Atomic Energy Agency, Vienna, Austria (2000). The 9977 package is designed, analyzed and fabricated in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1992 edition.

Abramczyk, G; Paul Blanton, P; Kurt Eberl, K

2006-05-18T23:59:59.000Z

196

Safety analysis for tank 241-AZ-101 mixer pump process test  

Science Conference Proceedings (OSTI)

This document establishes the safety envelope for Project W-151,the process test of two mixer pumps in AWF waste tank 241-AZ-101.

Milliken, N.J., Westinghouse Hanford

1996-08-01T23:59:59.000Z

197

Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Energy Institute (NEI) Attachment, Integrated Safety Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis This paper addresses why the use of an Integrated Safety Analysis ("ISA") is appropriate for fuel recycling facilities1 which would be licensed under new regulations currently being considered by NRC. The use of the ISA for fuel facilities under Part 70 is described and compared to the use of a Probabilistic Risk Assessment ("PRA") for reactor facilities. A basis is provided for concluding that future recycling facilities - which will possess characteristics similar to today's fuel cycle facilities and distinct from reactors - can best be assessed using established qualitative or semi-quantitative ISA techniques to achieve and

198

Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary  

Science Conference Proceedings (OSTI)

The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected.

Shedrow, C.B.

1999-11-29T23:59:59.000Z

199

Referenced Documents  

Science Conference Proceedings (OSTI)

Table 1   Thermal spray resource documents...www.aws.org ??A Guide to the Health and Safety at Work etc. Act? ? (U.K.) 1974, L1 ISBN 0 7176 044441 1 Free ??Risk Radar? software download ? Software Program Managers Network www.riskradarprogram.com...

200

Underground Test Area Subproject Phase I Data Analysis Task. Volume IV - Hydrologic Parameter Data Documentation Package  

Science Conference Proceedings (OSTI)

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

None

1996-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

September 26, 2011, Department letter transmitting the Implementation Plan for Board Recommendation 2010-1, Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers.  

NLE Websites -- All DOE Office Websites (Extended Search)

September 26, 2011 September 26, 2011 The Honorable Peter S. Winokur Chairman Defense Nuclear Facilities Safety Board 625 Indiana Avenue, NW, Suite 700 Washington, DC 20004-2941 Dear Mr. Chairman: Enclosed is the Department of Energy's Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2010-1, Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers. This Plan provides the Department's approach for updating its Documented Safety Analysis Standards and requirements to clarify them in regards to performance of hazard and accident analysis and the identification of safety controls. I have assigned Dr. James B. O'Brien, Acting Director, Office of Nuclear Safety in the Office of Health, Safety and Security, as the Department's Responsible

202

Safety analysis report for packaging (onsite) steel drum  

SciTech Connect

This Safety Analysis Report for Packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the steel drum packaging system meets the transportation safety requirements of HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments, for an onsite packaging containing Type B quantities of solid and liquid radioactive materials. The basic component of the steel drum packaging system is the 208 L (55-gal) steel drum.

McCormick, W.A.

1998-09-29T23:59:59.000Z

203

Safety Analysis Of Automated Highway Systems  

E-Print Network (OSTI)

hazard analysis of process-control software requirements. In contrast, the analyst does not have a tool

Leveson, Nancy G.

1997-01-01T23:59:59.000Z

204

Safety Bulletin  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Bulletin Bulletin Offtce 01 Health. Safety and Sa<:urtty Events Beyond Design Safety Basis Analysis No. 2011-01 PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and the subsequent tsunami. While there is still a lot to be learned from the accident · about the adequacy of design specifications and the equipment failure modes, reports from the Nuclear Regulatory Commission (NRC) have identified some key aspects of the operational emergency at the Fukushima Daiichi nuclear power station.

205

Certification process of safety analysis and risk management computer codes at the Savannah River Site  

Science Conference Proceedings (OSTI)

The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

Ades, M.J. (Westinghouse Savannah River Co., Aiken, SC (United States)); Toffer, H.; Lewis, C.J.; Crowe, R.D. (Westinghouse Hanford Co., Richland, WA (United States))

1992-01-01T23:59:59.000Z

206

Certification process of safety analysis and risk management computer codes at the Savannah River Site  

Science Conference Proceedings (OSTI)

The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Toffer, H.; Lewis, C.J.; Crowe, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

1992-05-01T23:59:59.000Z

207

Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2  

Science Conference Proceedings (OSTI)

This document is the second volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, except for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of failure modes and effects analysis; accident analysis; operational safety requirements; quality assurance program; ES&H management program; environmental, safety, and health systems critical to safety; summary of waste-management program; environmental monitoring program; facility expansion, decontamination, and decommissioning; summary of emergency response plan; summary plan for employee training; summary plan for operating procedures; glossary; and appendices A and B.

NONE

1994-10-01T23:59:59.000Z

208

ISO Standards Documents  

Science Conference Proceedings (OSTI)

ISO/TC 34: Food products and TC 34/SC 17: Management systems for food safety ISO Standards Documents iso3rss ISO Standards Development ISO Standards Development

209

TASSEL 3.0 Universal Network Enabled Analysis Kit (UNEAK) pipeline documentation  

E-Print Network (OSTI)

1 TASSEL 3.0 Universal Network Enabled Analysis Kit (UNEAK) pipeline documentation Authors: Fei Lu.............................................................................................................................. 8 Introduction The UNEAK is the non-reference Genotyping by Sequencing (GBS) SNP calling pipeline the command line in the following format (Linux or Mac operating system; for Windows use run_pipeline

Buckler, Edward S.

210

Overview Documents: Document 0703019  

NLE Websites -- All DOE Office Websites (Extended Search)

Sites Feedback Overview Documents Page 19 Next - - - > < - Previous U.S. Atomic Energy Commission Minutes of Commissioners' Executive Session 74 - 29 May 13, 1974 Document...

211

Maintaining scale as a realiable computational system for criticality safety analysis  

SciTech Connect

Accurate and reliable computational methods are essential for nuclear criticality safety analyses. The SCALE (Standardized Computer Analyses for Licensing Evaluation) computer code system was originally developed at Oak Ridge National Laboratory (ORNL) to enable users to easily set up and perform criticality safety analyses, as well as shielding, depletion, and heat transfer analyses. Over the fifteen-year life of SCALE, the mainstay of the system has been the criticality safety analysis sequences that have featured the KENO-IV and KENO-V.A Monte Carlo codes and the XSDRNPM one-dimensional discrete-ordinates code. The criticality safety analysis sequences provide automated material and problem-dependent resonance processing for each criticality calculation. This report details configuration management which is essential because SCALE consists of more than 25 computer codes (referred to as modules) that share libraries of commonly used subroutines. Changes to a single subroutine in some cases affect almost every module in SCALE! Controlled access to program source and executables and accurate documentation of modifications are essential to maintaining SCALE as a reliable code system. The modules and subroutine libraries in SCALE are programmed by a staff of approximately ten Code Managers. The SCALE Software Coordinator maintains the SCALE system and is the only person who modifies the production source, executables, and data libraries. All modifications must be authorized by the SCALE Project Leader prior to implementation.

Bowmann, S.M.; Parks, C.V.; Martin, S.K.

1995-04-01T23:59:59.000Z

212

Technical Review Report for the Mound 1KW Package Safety Analysis Report for Packaging Addendum No. 1, through Revision b  

SciTech Connect

This Technical Review Report (TRR) documents the review, performed by the Lawrence Livermore National Laboratory (LLNL) staff, at the request of the U.S. Department of Energy (DOE), on the 'Mound 1KW Package Safety Analysis Report for Packaging, Addendum No. 1, Revision b', dated May 2007 (Addendum 1). The Mound 1KW Package is certified by DOE Certificate of Compliance (CoC) number USA/9516/B(U)F-85 for the transportation of Type B quantities of plutonium heat source material. The safety analysis of the package is documented in the 'Safety Analysis Report for Packaging (SARP) for the Mound 1KW Package' (i.e., the Mound 1KW SARP, or the SARP). Addendum 1 incorporates a new fueled capsule assembly payload. The following changes have been made to add this payload: (1) The primary containment vessel (PCV) will be of the same design, but will increase in height to 11.16 in.; (2) A new graphite support block will be added to support up to three fueled capsule assemblies per package; (3) The cutting groove height on the secondary containment vessel (SCV) will be heightened to accommodate the taller PCV; and (4) A 3.38 in. high graphite filler block will be placed on top of the PCV. All other packaging features, as described in the Mound 1KW SARP [3], remain unchanged. This report documents the LLNL review of Addendum 1[1]. The specific review for each SARP Chapter is documented herein.

DiSabatino, A; West, M; Hafner, R; Russell, E

2007-10-04T23:59:59.000Z

213

Texas Emissions and Energy Calculator (eCALC): Documentation of Analysis Methods, Report to the TCEQ  

E-Print Network (OSTI)

This report provides documentation about the Energy Systems Laboratorys Emissions and Energy Calculator (eCALC), including information about the web structure, new building models, and community projects. In each of the sections a description of the basic user input is provided, and a description of the analysis that eCALC performs once the use submits a project for analysis. This report also provides a brief summary of the literature reviews for the analysis methods that were developed to document the uncertainty reported in the literature, including: F-Chart, PV F-Chart, ASHRAEs Inverse Model Toolkit (IMT), Cool Roofs, and the DOE-2 program. This report also provides a description of the methods used to assemble actual weather data files for 1999 through 2003 for use in eCALC.

Haberl, J. S.; Gilman, D.; Culp, C.

2004-01-01T23:59:59.000Z

214

Cost-Effectiveness Analysis of the 2009 and 2012 IECC Residential Provisions -- Technical Support Document  

NLE Websites -- All DOE Office Websites (Extended Search)

2068 2068 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Cost-Effectiveness Analysis of the 2009 and 2012 IECC Residential Provisions - Technical Support Document V Mendon R Lucas S Goel April 2013 PNNL-22068 Cost-Effectiveness Analysis of the 2009 and 2012 IECC Residential Provisions - Technical Support Document V Mendon R Lucas S Goel April 2013 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 iii Executive Summary This analysis was conducted by Pacific Northwest National Laboratory (PNNL) in support of the U.S. Department of Energy's (DOE) Building Energy Codes Program (BECP). DOE supports the

215

Nuclear criticality safety guide  

Science Conference Proceedings (OSTI)

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

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

1996-09-01T23:59:59.000Z

216

SRS - SRNS General Provisions and Related Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

SRNS General Provisions and Related Documents General ProvisionsTerms and Conditions Documents Certifications SolicitationSubcontract Documents Focused Observation Safety...

217

Applicability of trends in nuclear safety analysis to space nuclear power systems  

SciTech Connect

A survey is presented of some current trends in nuclear safety analysis that may be relevant to space nuclear power systems. This includes: lessons learned from operating power reactor safety and licensing; approaches to the safety design of advanced and novel reactors and facilities; the roles of risk assessment, extremely unlikely accidents, safety goals/targets; and risk-benefit analysis and communication.

Bari, R.A.

1992-10-01T23:59:59.000Z

218

QuantUM: Quantitative Safety Analysis of UML Models  

E-Print Network (OSTI)

When developing a safety-critical system it is essential to obtain an assessment of different design alternatives. In particular, an early safety assessment of the architectural design of a system is desirable. In spite of the plethora of available formal quantitative analysis methods it is still difficult for software and system architects to integrate these techniques into their every day work. This is mainly due to the lack of methods that can be directly applied to architecture level models, for instance given as UML diagrams. Also, it is necessary that the description methods used do not require a profound knowledge of formal methods. Our approach bridges this gap and improves the integration of quantitative safety analysis methods into the development process. All inputs of the analysis are specified at the level of a UML model. This model is then automatically translated into the analysis model, and the results of the analysis are consequently represented on the level of the UML model. Thus the analysi...

Leitner-Fischer, Florian; 10.4204/EPTCS.57.2

2011-01-01T23:59:59.000Z

219

Guidance Related to Analysis of Impacts to Workers in National Environmental Policy Act Documentation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

D D A T E : June 10, 1988 REPLY TO ATTN OF: E H - 2 5 SUBJECT: Guidance Related to Analysis of Impacts to Workers in National Environmental Policy Act (NEPA) Documentation TO : D I S T R I BUT I ON The purpose of this memorandum is to provide general guidance regarding the analysis of impacts to workers in DOE environmental impact statements (EISs) and environmental assessments (EAs) in order to assist DOE program and field offices in meeting the requirements of NEPA and to establish a general consistency in the Department's NEPA documentation. This guidance was prompted by several questions raised in this regard and was developed by the Office of NEPA Project Assistance, after consultation with the Office of General Counsel. Background Neither the Council on Environmental Quality (CEQ) regulations for

220

Hanford Waste Vitrification Plant project Preliminary Safety Analysis Report comment response records  

SciTech Connect

The initial draft version of the Hanford Waste Vitrification Plant (HWVP) Preliminary Safety Analysis Report (PSAR) was issued for review and comment on July 17, 1989, and was designated as Revision A. Following resolution of comments arising from the Revision A review, the PSAR was revised as a final draft. This version, which was designated as HWVP PSAR, Revision B, was issued for review and comment on July 16, 1990. The PSAR was again revised as Revision O following the resolution of the Revision B comments. The HWVP PSAR, Revision O, was approved by Westinghouse Hanford Company (Westinghouse Hanford) on May 21, 1991, and issued as WHC-EP-0250, Hanford Waste Vitrification Plant Preliminary Safety Analysis Report to the Department of Energy-Richland Operations Office (DOE-RL). While Westinghouse Hanford organizations were reviewing the drafts of the HWVP PSAR (i.e., Revisions A and B), a parallel review was being performed by the DOE-RL on both versions. This supporting document provides a summary of the PSAR Comment Response Databases for the Westinghouse Hanford and DOE-RL reviews of HWVP PSAR, Revisions A and B. This document also provides copies of all the closed-out Review Comment Records (RCR) submitted by these organizations. 8 refs., 1 fig., 2 tabs.

Herborn, D.I.; Campbell, L.M.

1991-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Statistical analysis of what drives industrial energy demand: Volume III of the PURHAPS model documentation  

Science Conference Proceedings (OSTI)

The overall price of energy has far less direct effect on industrial demand than conventional models, such as the Jorgenson translog model, have indicated. Much of what appears to be conservation in recent years can be explained as the result of structural changes (e.g., less steel production), electrification, and a slowdown in the long-term trend towards more use of energy relative to other factors of production. This report documents these findings and the other findings from the statistical analysis used in developing the PURchased Heat And Power System, as used in producing the 1982 Annual Energy Outlook forecasts. This report is intended partly to convey these findings to substantive energy experts and energy policy analysts; it is also intended to fulfill EIA requirements for model documentation. Volume I of this series documents the full mathematical specification of the model, including accounting identites and benchmarks; Volume II documents the data used both in the estimation and in the model. Appendix B of this report provides a purely historical breakdown of actual changes in oil and electricity use from 1974 to 1981, showing what changes are due to general economic growth, improved general productivity, etc. preliminary work for the 1983 Annual Energy Outlook is discussed in general terms.

Werbos, P.J.

1983-12-01T23:59:59.000Z

222

Reactor Safety Testing and Analysis - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

223

Analysis Tools for Nuclear Criticality Safety - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

224

Methods and criteria for safety analysis (FIN L2535)  

SciTech Connect

In response to the NRC request for a proposal dated October 20, 1992, Westinghouse Savannah River Company (WSRC) submit this proposal to provide contractural assistance for FIN L2535, Methods and Criteria for Safety Analysis,'' as specified in the Statement of Work attached to the request for proposal. The Statement of Work involves development of safety analysis guidance for NRC licensees, arranging a workshop on this guidance, and revising NRC Regulatory Guide 3.52. This response to the request for proposal offers for consideration the following advantages of WSRC in performing this work: Experience, Qualification of Personnel and Resource Commitment, Technical and Organizational Approach, Mobilization Plan, Key Personnel and Resumes. In addition, attached are the following items required by the NRC: Schedule II, Savannah River Site - Job Cost Estimate, NRC Form 189, Project and Budget Proposal for NRC Work, page 1, NRC Form 189, Project and Budget Proposal for NRC Work, page 2, Project Description.

1992-12-01T23:59:59.000Z

225

Methods and criteria for safety analysis (FIN L2535)  

SciTech Connect

In response to the NRC request for a proposal dated October 20, 1992, Westinghouse Savannah River Company (WSRC) submit this proposal to provide contractural assistance for FIN L2535, ``Methods and Criteria for Safety Analysis,`` as specified in the Statement of Work attached to the request for proposal. The Statement of Work involves development of safety analysis guidance for NRC licensees, arranging a workshop on this guidance, and revising NRC Regulatory Guide 3.52. This response to the request for proposal offers for consideration the following advantages of WSRC in performing this work: Experience, Qualification of Personnel and Resource Commitment, Technical and Organizational Approach, Mobilization Plan, Key Personnel and Resumes. In addition, attached are the following items required by the NRC: Schedule II, Savannah River Site - Job Cost Estimate, NRC Form 189, Project and Budget Proposal for NRC Work, page 1, NRC Form 189, Project and Budget Proposal for NRC Work, page 2, Project Description.

1992-12-01T23:59:59.000Z

226

Guidance on health effects of toxic chemicals. Safety Analysis Report Update Program  

SciTech Connect

Martin Marietta Energy Systems, Inc. (MMES), and Martin Marietta Utility Services, Inc. (MMUS), are engaged in phased programs to update the safety documentation for the existing US Department of Energy (DOE)-owned facilities. The safety analysis of potential toxic hazards requires a methodology for evaluating human health effects of predicted toxic exposures. This report provides a consistent set of health effects and documents toxicity estimates corresponding to these health effects for some of the more important chemicals found within MMES and MMUS. The estimates are based on published toxicity information and apply to acute exposures for an ``average`` individual. The health effects (toxicological endpoints) used in this report are (1) the detection threshold; (2) the no-observed adverse effect level; (3) the onset of irritation/reversible effects; (4) the onset of irreversible effects; and (5) a lethal exposure, defined to be the 50% lethal level. An irreversible effect is defined as a significant effect on a person`s quality of life, e.g., serious injury. Predicted consequences are evaluated on the basis of concentration and exposure time.

Foust, C.B.; Griffin, G.D.; Munro, N.B.; Socolof, M.L.

1994-02-01T23:59:59.000Z

227

Safety analysis report vitrified high level waste type B shipping cask  

Science Conference Proceedings (OSTI)

This Safety Analysis Report describes the design, analyses, and principle features of the Vitrified High Level Waste (VHLW) Cask. In preparing this report a detailed evaluation of the design has been performed to ensure that all safety, licensing, and operational goals for the cask and its associated Department of Energy program can be met. The functions of this report are: (1) to fully document that all functional and regulatory requirements of 10CFR71 can be met by the package; and (2) to document the design and analyses of the cask for review by the Nuclear Regulatory Commission. The VHLW Cask is the reusable shipping package designed by GNSI under Department of Energy contract DE-AC04-89AL53-689 for transportation of Vitrified High Level Waste, and to meet the requirements for certification under 10CFR71 for a Type B(U) package. The VHLW cask has been designed as packaging for transport of canisters of Vitrified High Level Waste solidified at Department of Energy facilities.

NONE

1995-03-01T23:59:59.000Z

228

Safety analysis, 200 Area, Savannah River Plant: Separations area operations  

Science Conference Proceedings (OSTI)

The nev HB-Line, located on the fifth and sixth levels of Building 221-H, is designed to replace the aging existing HB-Line production facility. The nev HB-Line consists of three separate facilities: the Scrap Recovery Facility, the Neptunium Oxide Facility, and the Plutonium Oxide Facility. There are three separate safety analyses for the nev HB-Line, one for each of the three facilities. These are issued as supplements to the 200-Area Safety Analysis (DPSTSA-200-10). These supplements are numbered as Sup 2A, Scrap Recovery Facility, Sup 2B, Neptunium Oxide Facility, Sup 2C, Plutonium Oxide Facility. The subject of this safety analysis, the, Plutonium Oxide Facility, will convert nitrate solutions of {sup 238}Pu to plutonium oxide (PuO{sub 2}) powder. All these new facilities incorporate improvements in: (1) engineered barriers to contain contamination, (2) barriers to minimize personnel exposure to airborne contamination, (3) shielding and remote operations to decrease radiation exposure, and (4) equipment and ventilation design to provide flexibility and improved process performance.

Perkins, W.C.; Lee, R.; Allen, P.M.; Gouge, A.P.

1991-07-01T23:59:59.000Z

229

Overview Documents: Document 0706963  

NLE Websites -- All DOE Office Websites (Extended Search)

Related Sites Feedback Overview Documents Page 143 Next - - - > < - Previous Atomic Energy Commission Plan for Expansion of Research in Biology and Medicine. Note by the...

230

FAQS Qualification Card - Criticality Safety | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety Criticality Safety FAQS Qualification Card - Criticality 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, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-CriticalitySafety.docx Description Criticality Safety Qualification Card More Documents & Publications FAQS Gap Analysis Qualification Card - Criticality Safety

231

Environment, Safety, and Health Assurance Program Standard: analysis in the context of Department of Energy environment, safety, and health requirements  

SciTech Connect

An Environment, Safety and Health (ES and H) Assurance Program Standard is presented. The Standard was published for comments in a previous document, and has been revised as a result of those comments. The benefits of using the Standard are described and, through the use of comparisons, it is demonstrated that the requirements of the applicable Department of Energy (DOE) Orders are satisfied by a program designed in accordance with the Standard.

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

1979-09-01T23:59:59.000Z

232

The Zion integrated safety analysis for NUREG-1150  

SciTech Connect

The utility-funded Zion Probabilistic Safety Study provided not only a detailed and thorough assessment of the risk profile of Zion Unit 1, but also presented substantial advancement in the technology of probabilistic risk assessment (PRA). Since performance of that study, modifications of plant hardware, the introduction of new emergency procedures, operational experience gained, information generated by severe accident research programs and further evolution of PRA and uncertainty analysis methods have provided a basis for reevaluation of the Zion risk profile. This reevaluation is discussed in this report. 5 refs.

Unwin, S.D.; Park, C.K.

1988-01-01T23:59:59.000Z

233

Data development technical support document for the aircraft crash risk analysis methodology (ACRAM) standard  

SciTech Connect

The Aircraft Crash Risk Analysis Methodology (ACRAM) Panel has been formed by the US Department of Energy Office of Defense Programs (DOE/DP) for the purpose of developing a standard methodology for determining the risk from aircraft crashes onto DOE ground facilities. In order to accomplish this goal, the ACRAM panel has been divided into four teams, the data development team, the model evaluation team, the structural analysis team, and the consequence team. Each team, consisting of at least one member of the ACRAM plus additional DOE and DOE contractor personnel, specializes in the development of the methodology assigned to that team. This report documents the work performed by the data development team and provides the technical basis for the data used by the ACRAM Standard for determining the aircraft crash frequency. This report should be used to provide the generic data needed to calculate the aircraft crash frequency into the facility under consideration as part of the process for determining the aircraft crash risk to ground facilities as given by the DOE Standard Aircraft Crash Risk Assessment Methodology (ACRAM). Some broad guidance is presented on how to obtain the needed site-specific and facility specific data but this data is not provided by this document.

Kimura, C.Y.; Glaser, R.E.; Mensing, R.W.; Lin, T.; Haley, T.A.; Barto, A.B.; Stutzke, M.A.

1996-08-01T23:59:59.000Z

234

Forensic Database Questioned Documents Table  

Science Conference Proceedings (OSTI)

... specific user requirements. There is an API through which digital documents can be passed for analysis. Documents such ...

2013-06-06T23:59:59.000Z

235

Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2  

Science Conference Proceedings (OSTI)

This document is the first volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, except for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of an introduction, summary/conclusion, site description and assessment, description of facility, and description of operation.

NONE

1994-10-01T23:59:59.000Z

236

New enhancements to SCALE for criticality safety analysis  

Science Conference Proceedings (OSTI)

As the speed, available memory, and reliability of computer hardware increases and the cost decreases, the complexity and usability of computer software will increase, taking advantage of the new hardware capabilities. Computer programs today must be more flexible and user friendly than those of the past. Within available resources, the SCALE staff at Oak Ridge National Laboratory (ORNL) is committed to upgrading its computer codes to keep pace with the current level of technology. This paper examines recent additions and enhancements to the criticality safety analysis sections of the SCALE code package. These recent additions and enhancements made to SCALE can be divided into nine categories: (1) new analytical computer codes, (2) new cross-section libraries, (3) new criticality search sequences, (4) enhanced graphical capabilities, (5) additional KENO enhancements, (6) enhanced resonance processing capabilities, (7) enhanced material information processing capabilities, (8) portability of the SCALE code package, and (9) other minor enhancements, modifications, and corrections to SCALE. Each of these additions and enhancements to the criticality safety analysis capabilities of the SCALE code system are discussed below.

Hollenbach, D.F.; Bowman, S.M.; Petrie, L.M.; Parks, C.V. [Oak Ridge National Lab., TN (United States). Computational Physics and Engineering Div.

1995-09-01T23:59:59.000Z

237

Safety and Technical Services  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety and Technical Services Safety and Technical Services Minimize The Safety and Technical Services (STS) organization is a component of the Office of Science's (SC's) Oak Ridge Integrated Support Center. The mission of STS is to provide excellent environmental, safety, health, quality, and engineering support to SC laboratories and other U.S. Department of Energy program offices. STS maintains a full range of technically qualified Subject Matter Experts, all of whom are associated with the Technical Qualifications Program. Examples of the services that we provide include: Integrated Safety Management Quality Assurance Planning and Metrics Document Review Tracking and trending analysis and reporting Assessments, Reviews, Surveillances and Inspections Safety Basis Support SharePoint/Dashboard Development for Safety Programs

238

INTERPRETATION REGARDING EXEMPTION RELIEF UNDER 10 C.F.R. PART 820, SUBPART E, EXEMPTION RELIEF, AND NON-COMPLIANT DOCUMENTED SAFETY ANALYSES SUBJECT TO 10 C.F.R. PART 830, NUCLEAR SAFETY MANAGEMENT, SUBPART B, SAFETY BASIS REQUIREMENTS  

Energy.gov (U.S. Department of Energy (DOE))

The following document is the Office of General Counsel (GC) interpretation regarding exemption relief pursuant to10 C.F.R. Part 820, Procedural Rules for DOE Nuclear Activities, Subpart E,...

239

Office of Health & Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Beryllium Chemical Safety Biological Safety Radiation Safety Rules 10 CFR 707 10 CFR 835 10 CFR 850 10 CFR 851 OHS Document Collection Site Medical Clinics REACTS EEOICPA...

240

Documents: Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

Search Documents: Search PDF Documents View a list of all documents Transportation PDF Icon Transportation Impact Assessment for Shipment of Uranium Hexafluoride (UF6) Cylinders...

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Issues related to criticality safety analysis for burnup credit applications  

SciTech Connect

Spent fuel transportation and storage cask designs based on a burnup credit approach must consider issues that are not relevant in casks designed under a fresh fuel loading assumption. Parametric analyses are required to characterize the importance of fuel assembly and fuel cycle parameters on spent fuel composition and reactivity. Numerical models are evaluated to determine the sensitivity of criticality safety calculations to modeling assumptions. This paper discusses the results of studies to determine the effect of two important modeling assumptions on the criticality analysis of pressurized-water reactor (PWR) spent fuel: (1) the effect of assumed burnup history (i.e., specific power during and time-dependent variations in operational power) during depletion calculations, and (2) the effect of axial burnup distributions on the neutron multiplication factor calculated for a three-dimensional (3-D) conceptual cask design.

DeHart, M.D.; Parks, C.V.

1995-12-01T23:59:59.000Z

242

DOE-STD-1120-2005; Integration of Environment Safety and Health...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

INTO FACILITY DISPOSITION ACTIVITIES Volume 1 of 2: Documented Safety Analysis for Decommissioning and Environmental Restoration Projects U.S. Department of Energy AREA SAFT...

243

JM for Page Change to DOE O 420.1C, Facility Safety  

Directives, Delegations, and Requirements

DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and ...

2013-06-21T23:59:59.000Z

244

Safety analysis of the 700-horsepower combustion test facility  

SciTech Connect

The objective of the program reported herein was to provide a Safety Analysis of the 700 h.p. Combustion Test Facility located in Building 93 at the Pittsburgh Energy Technology Center. Extensive safety related measures have been incorporated into the design, construction, and operation of the Combustion Test Facility. These include: nitrogen addition to the coal storage bin, slurry hopper, roller mill and pulverizer baghouse, use of low oxygen content combustion gas for coal conveying, an oxygen analyzer for the combustion gas, insulation on hot surfaces, proper classification of electrical equipment, process monitoring instrumentation and a planned remote television monitoring system. Analysis of the system considering these factors has resulted in the determination of overall probabilities of occurrence of hazards as shown in Table I. Implementation of the recommendations in this report will reduce these probabilities as indicated. The identified hazards include coal dust ignition by hot ductwork and equipment, loss of inerting within the coal conveying system leading to a coal dust fire, and ignition of hydrocarbon vapors or spilled oil, or slurry. The possibility of self-heating of coal was investigated. Implementation of the recommendations in this report will reduce the ignition probability to no more than 1 x 10/sup -6/ per event. In addition to fire and explosion hazards, there are potential exposures to materials which have been identified as hazardous to personal health, such as carbon monoxide, coal dust, hydrocarbon vapors, and oxygen deficient atmosphere, but past monitoring experience has not revealed any problem areas. The major environmental hazard is an oil spill. The facility has a comprehensive spill control plan.

Berkey, B.D.

1981-05-01T23:59:59.000Z

245

Processes and Procedures for Application of CFD to Nuclear Reactor Safety Analysis  

SciTech Connect

Traditionally, nuclear reactor safety analysis has been performed using systems analysis codes such as RELAP5, which was developed at the INL. However, goals established by the Generation IV program, especially the desire to increase efficiency, has lead to an increase in operating temperatures for the reactors. This increase pushes reactor materials to operate towards their upper temperature limits relative to structural integrity. Because there will be some finite variation of the power density in the reactor core, there will be a potential for local hot spots to occur in the reactor vessel. Hence, it has become apparent that detailed analysis will be required to ensure that local hot spots do not exceed safety limits. It is generally accepted that computational fluid dynamics (CFD) codes are intrinsically capable of simulating fluid dynamics and heat transport locally because they are based on first principles. Indeed, CFD analysis has reached a fairly mature level of development, including the commercial level. However, CFD experts are aware that even though commercial codes are capable of simulating local fluid and thermal physics, great care must be taken in their application to avoid errors caused by such things as inappropriate grid meshing, low-order discretization schemes, lack of iterative convergence and inaccurate time-stepping. Just as important is the choice of a turbulence model for turbulent flow simulation. Turbulence models model the effects of turbulent transport of mass, momentum and energy, but are not necessarily applicable for wide ranges of flow types. Therefore, there is a well-recognized need to establish practices and procedures for the proper application of CFD to simulate flow physics accurately and establish the level of uncertainty of such computations. The present document represents contributions of CFD experts on what the basic practices, procedures and guidelines should be to aid CFD analysts to obtain accurate estimates of the flow and energy transport as applied to nuclear reactor safety. However, it is expected that these practices and procedures will require updating from time to time as research and development affect them or replace them with better procedures. The practices and procedures are categorized into five groups. These are: 1.Code Verification 2.Code and Calculation Documentation 3.Reduction of Numerical Error 4.Quantification of Numerical Uncertainty (Calculation Verification) 5.Calculation Validation. These five categories have been identified from procedures currently required of CFD simulations such as those required for publication of a paper in the ASME Journal of Fluids Engineering and from the literature such as Roache [1998]. Code verification refers to the demonstration that the equations of fluid and energy transport have been correctly coded in the CFD code. Code and calculation documentation simply means that the equations and their discretizations, etc., and boundary and initial conditions used to pose the fluid flow problem are fully described in available documentation. Reduction of numerical error refers to practices and procedures to lower numerical errors to negligible or very low levels as is reasonably possible (such as avoiding use of first-order discretizations). The quantification of numerical uncertainty is also known as calculation verification. This means that estimates are made of numerical error to allow the characterization of the numerical

Richard W. Johnson; Richard R. Schultz; Patrick J. Roache; Ismail B. Celik; William D. Pointer; Yassin A. Hassan

2006-09-01T23:59:59.000Z

246

Performance and Safety Analysis of a Generic Small Modular Reactor  

E-Print Network (OSTI)

The high and ever growing demand for electricity coupled with environmental concerns and a worldwide desire to shed petroleum dependence, all point to a shift to utilization of renewable sources of energy. The under developed nature of truly renewable energy sources such as, wind and solar, along with their limitations on the areas of applicability and the energy output calls for a renaissance in nuclear energy. In this second nuclear era, deliberately small reactors are poised to play a major role with a number of Small Modular Reactors (SMRs) currently under development in the U.S. In this work, an SMR model of the Integral Pressurized Water Reactor (IPWR) type is created, analyzed and optimized to meet the publically available performance criteria of the mPower SMR from B&W. The Monte Carlo codes MCNP5/MCNPX are used to model the core. Fuel enrichment, core inventory, core size are all variables optimized to meet the set goals of core lifetime and fuel utilization (burnup). Vital core behavior characteristics such as delayed neutron fraction and reactivity coefficients are calculated and shown to be typical of larger PWR systems, which is necessary to ensure the inherent safety and to achieve rapid deployment of the reactor by leveraging the vast body of operational experience amassed with the larger commercial PWRs. Inherent safety of the model is analyzed with the results of an analytical single channel analysis showing promising behavior in terms of axial and radial fuel element temperature distributions, the critical heat flux, and the departure from nucleate boiling ratio. The new fleet of proposed SMRs is intended to have increased proliferation resistance (PR) compared to the existing fleet of operating commercial PWRs. To quantify this PR gain, a PR analysis is performed using the Proliferation Resistance Analysis and Evaluation Tool for Observed Risk (PRAETOR) code developed by the Nuclear Science and Security Policy Institute at Texas A&M University. The PRAETOR code uses multi-attribute utility analysis to combine 63 factors affecting the PR value of a facility into a single metric which is easily comparable. The analysis compared hypothetical spent fuel storage facilities for the SMR model spent fuel assembly and one for spent fuel from a Westinghouse AP1000. The results showed that from a fuel material standpoint, the SMR and AP1000 had effectively the same PR value. Unable to analyze security systems and methods employed at specific nuclear power plant sites, it is premature to conclude that the SMR plants will not indeed show increased PR as intended.

Kitcher, Evans Damenortey, 1987-

2012-12-01T23:59:59.000Z

247

Model documentation of the Short-Term Coal Analysis System. Volume 2. Model description. [SCOAL  

Science Conference Proceedings (OSTI)

This is the second of three volumes of documentation for the Short-Term Coal Analysis System (SCOAL) developed by the Coal Data Analysis and Forecasting Branch, Office of Coal, Nuclear, Electric, and Alternate Fuels. The principal aim of SCOAL is to project on a quarterly basis the likely contribution of each of the 26 major bituminous coal, lignite, and anthracite producing states to total US production. A secondary objective is to estimate a companion demand-side aggregated by region but disaggregated by end-use sector. In its current use, the two sides are operated in tandem, and serve to cross-validate each other by means of tracking market balances. The purposes of this report are to describe the estimation method, results, and performance evaluation criteria that were deemed relevant in assessing the potential predictive performance of SCOAL's statistically fitted relationships and to discuss the pre- and post-estimation considerations that prevailed over the course of mode development. The single equation parameter estimates, associated significance levels, statistical equation performance measures, and general comments regarding SCOAL's supply and demand side equations are presented.

Not Available

1983-04-01T23:59:59.000Z

248

Underground Test Area Subproject Phase I Data Analysis Task. Volume V - Transport Parameter and Source Term Data Documentation Package  

Science Conference Proceedings (OSTI)

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

None

1996-12-01T23:59:59.000Z

249

Safety analysis of natural gas vehicles transiting highway tunnel  

Science Conference Proceedings (OSTI)

A safety analysis was performed to assess the relative hazard of compressed natural gas (CNG) fueled vehicles traveling on various tunnels and bridges in New York City. The study considered those hazards arising from the release of fuel from CNG vehicles ranging in size from a passenger sedan to a full size 53 passenger bus. The approach used was to compare the fuel hazard of CNG vehicles to the fuel hazard of gasoline vehicles. The risk was assessed by estimating the frequency of occurrence and the severity of the hazard. The methodology was a combination of analyzing accident data, performing a diffusion analysis of the gas released in the tunnel and determining the consequences of ignition. Diffusion analysis was performed using the TEMPEST code for various accident scenarios resulting in CNG release inside the Holland Tunnel. The study concluded that the overall hazard of CNG vehicles transiting a ventilated tunnel is less than the hazard from a comparable gasoline fueled vehicle. 134 refs., 23 figs., 24 tabs.

Shaaban, S.H.; Zuzovsky, M.; Anigstein, R.

1989-01-01T23:59:59.000Z

250

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

Science Conference Proceedings (OSTI)

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

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

1994-10-07T23:59:59.000Z

251

Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation  

SciTech Connect

One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

John D. Bess; J. Blair Briggs; David W. Nigg

2009-11-01T23:59:59.000Z

252

Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation  

SciTech Connect

One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

John D. Bess; J. Blair Briggs; David W. Nigg

2009-11-01T23:59:59.000Z

253

LNG storage: Safety analysis. Annual report, January-December 1980  

SciTech Connect

Progress is summarized on three projects in the areas of LNG safety: Rollover phenomena; Simultaneous boiling and spreading of cryogenic liquids; Modelling of LNG tank dynamics.

Reid, R.C.; Smith, K.A.; Virk, P.S.

1981-02-01T23:59:59.000Z

254

CRAD, Engineering Design and Safety Basis - December 22, 2009 | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Engineering Design and Safety Basis - December 22, 2009 Engineering Design and Safety Basis - December 22, 2009 CRAD, Engineering Design and Safety Basis - December 22, 2009 December 22, 2009 Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0) The engineering design and safety basis inspection will evaluate the effectiveness of programs and processes for the design and safety basis of selected safety structures, systems, and components (SSCs) of a nuclear facility. The nuclear facility may be an existing facility, a major modification to an existing facility, or a new facility under construction. Accordingly, the safety basis for the facility, for example, a documented safety analysis (DSA) or a preliminary documented safety analysis (PDSA),

255

CRAD, Engineering Design and Safety Basis - December 22, 2009 | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Engineering Design and Safety Basis - December 22, 2009 Engineering Design and Safety Basis - December 22, 2009 CRAD, Engineering Design and Safety Basis - December 22, 2009 December 22, 2009 Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0) The engineering design and safety basis inspection will evaluate the effectiveness of programs and processes for the design and safety basis of selected safety structures, systems, and components (SSCs) of a nuclear facility. The nuclear facility may be an existing facility, a major modification to an existing facility, or a new facility under construction. Accordingly, the safety basis for the facility, for example, a documented safety analysis (DSA) or a preliminary documented safety analysis (PDSA),

256

Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings  

SciTech Connect

This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and regulatory bases for the review, the manner in which the review is accomplished, and findings that are generally applicable for a package that meets the approval standards. This Packaging Review Guide (PRG) provides guidance for DOE review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE O 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. The primary objectives of this PRG are to: (1) Summarize the regulatory requirements for package approval; (2) Describe the technical review procedures by which DOE determines that these requirements have been satisfied; (3) Establish and maintain the quality and uniformity of reviews; (4) Define the base from which to evaluate proposed changes in scope and requirements of reviews; and (5) Provide the above information to DOE organizations, contractors, other government agencies, and interested members of the general public. This PRG was originally published in September 1987. Revision 1, issued in October 1988, added new review sections on quality assurance and penetrations through the containment boundary, along with a few other items. Revision 2 was published October 1999. Revision 3 of this PRG is a complete update, and supersedes Revision 2 in its entirety.

DiSabatino, A; Biswas, D; DeMicco, M; Fisher, L E; Hafner, R; Haslam, J; Mok, G; Patel, C; Russell, E

2007-04-12T23:59:59.000Z

257

Optimization of Lyapunov invariants in analysis and implementation of safety-critical software systems  

E-Print Network (OSTI)

This dissertation contributes to two major research areas in safety-critical software systems, namely, software analysis, and software implementation. In reference to the software analysis problem, the main contribution ...

Roozbehani, Mardavij

2008-01-01T23:59:59.000Z

258

FINAL SAFETY ANALYSIS REPORT. SNAP III THERMOELECTRIC GENERATOR  

SciTech Connect

The SNAP-III thermoelectric generator procedures power from the decay heat of 2100 curies of Po/sup 210/. This generator is to be used as a source of auxiliary power in a terrestrial satellite. For purposes of analysis, the satellite system postulated is launched from the Pacific Missile Bange into a 275- statute mile polar orbit with an orbital lifetime of about 1 year. Po/sup 210/ is an alpha emitter having a half life of 138 days and alpha and gamma decay energies of 5.3 and 0.8 mev, respectively. It is a natural component of the earth's crust, as a member of the uranium disintegration series. Sampling of polonium in the biosphere was conducted specifically for this program to determine background radiation levels. Since the fuel is primarily an alpha emitter, there is no direct radiation problem. An analysis was performed to determine the ability of the fuel container to withstand the various thermal, mechanical, and chemical forces imposed upon the generator by vehicle failures. Where theoretical analysis was impossible and experimental evidence was desired, capsules and generators were tested under simulated missile-failure conditions, Thus, the safety limits of SNAP-III in a satellite application were defined. SNAP-III is designed to be aerothermodynamically consumed on reentry into the earth's atmosphere so that the polonium will be dispersed as aerosols in the upper stratosphere. Since heating rates will be lower for aborts occurring prior to orbiting, 65 abort cases have been considered to define the general consequences of vehicle failures. The spatial and temporal relations of vehicle aborts are summarized in cartographic and tabular form. (auth)

Hagis, W.; Dix, G.P.

1960-06-01T23:59:59.000Z

259

A risk-informed approach to safety margins analysis  

SciTech Connect

The Risk Informed Safety Margins Characterization (RISMC) Pathway is a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. The model has been tested on the Advanced Test Reactor (ATR) at Idaho National Lab.

Curtis Smith; Diego Mandelli

2013-07-01T23:59:59.000Z

260

Development of a multichannel analysis code for the MITR-III safety analysis  

SciTech Connect

This paper describes the development of a MULti-CHannel analysis (MULCH-II) code to be used for the safety analysis of the Massachusetts Institute of Technology Research Reactor (MITR). The code models the primary and the secondary coolant systems with special emphasis on analysis of detailed thermal-hydraulic conditions in the core region. The hot channel is modeled in parallel with the average channels to predict conditions in the core during a flow excursion instability. Fuel and cladding temperatures are calculated under all conditions so that the margin to fuel failure is given in addition to the thermal-hydraulic conditions.

Hu, Lin-Wen; Bernard, J.A. [Massachusetts Inst. of Technology, Cambridge, MA (United States)

1996-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Documents: Other  

NLE Websites -- All DOE Office Websites (Extended Search)

Search Documents: Search PDF Documents View a list of all documents Other PDF Icon Investigation of the Chemical Reactivity of Phosgene in Uranium Hexafluoride 2.6 MB details PDF...

262

Surveillance Guide - NSS 18.3 Verification of Authorization Basis Documentation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

VERIFICATION OF AUTHORIZATION BASIS DOCUMENTATION VERIFICATION OF AUTHORIZATION BASIS DOCUMENTATION 1.0 Objective The objective of this surveillance is for the Facility Representative to verify that the facility's configuration and operations remain consistent with the authorization basis. As defined in DOE Notice 411.1-1B, the authorization basis consists of those aspects of the facility design basis and operational requirements relied upon by DOE to authorize operation. These aspects are considered to be important to the safety of the facility operations. The authorization basis is described in documents such as the facility safety analysis report and other documented safety analyses; hazard classification documents, and the Technical Safety Requirements, DOE- issued safety evaluation reports, and facility-specific commitments made in

263

An Integrated System for the Analysis and the Recognition of Characters in Ancient Documents  

Science Conference Proceedings (OSTI)

This paper describes an integrated system for processing and analyzing highly degraded ancient printed documents. For each page, the system reduces noise by wavelet-based filtering, extracts and segments the text lines into characters by a fast adaptive ...

Stefano Vezzosi; Luigi Bedini; Anna Tonazzini

2002-08-01T23:59:59.000Z

264

NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 The objective of this surveillance is for the Facility Representative to verify that the facility's configuration and operations remain consistent with the authorization basis. As defined in DOE Notice 411.1-1B, the authorization basis consists of those aspects of the facility design basis and operational requirements relied upon by DOE to authorize operation. These aspects are considered to be important to the safety of the facility operations. The authorization basis is described in documents such as the facility safety analysis report and other documented safety analyses; hazard classification documents, and the Technical Safety Requirements,

265

Hanford Sludge Treatment Project 105-KW Final Safety Analysis Report Review, August 2011  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Visit Report Site Visit Report Sludge Treatment Project 105-KW Final Safety Analysis Report Review May 2011 August 2011 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Introduction ............................................................................................................................................ 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 1 4.0 Results .................................................................................................................................................... 2

266

Hanford Sludge Treatment Project 105-KW Final Safety Analysis Report Review, August 2011  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site Visit Report Site Visit Report Sludge Treatment Project 105-KW Final Safety Analysis Report Review May 2011 August 2011 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Introduction ............................................................................................................................................ 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 1 4.0 Results .................................................................................................................................................... 2

267

Consolidation of public safety wireless networks: An options-based economic analysis of numerous scenarios  

Science Conference Proceedings (OSTI)

The Korean National Emergency Management Agency proposed to replace existing public safety wireless networks of 46 agencies with a nation-wide consolidated network. This study compares the public-private partnership alternative of sharing a network with ... Keywords: Consolidation, Exploratory modeling, Feasibility study, Public safety wireless network, Public-private partnership, Real option analysis

Sungho Lee

2011-03-01T23:59:59.000Z

268

An impact analysis method for safety-critical user interface design  

Science Conference Proceedings (OSTI)

We describe a method of assessing the implications for human error on user interface design of safety-critical systems. In previous work we have proposed a taxonomy of influencing factors that contribute to error. In this article, components of the taxonomy ... Keywords: Bayesian belief networks, human error, safety-critical, scenario-based casual analysis

Julia Galliers; Alistair Sutcliffe; Shailey Minocha

1999-12-01T23:59:59.000Z

269

Radiological Source Terms for Tank Farms Safety Analysis  

Science Conference Proceedings (OSTI)

This document provides Unit Liter Dose factors, atmospheric dispersion coefficients, breathing rates and instructions for using and customizing these factors for use in calculating radiological doses for accident analyses in the Hanford Tank Farms.

COWLEY, W.L.

2000-06-27T23:59:59.000Z

270

DOE G 421.1-2A, Implementation Guide for Use in Developing Documented Safety Analyses to Meet Subpart B of 10 CFR 830  

Directives, Delegations, and Requirements

Title 10 Code of Federal Regulations (CFR) Part 830, Subpart B, Safety Basis Requirements, requires the contractor responsible for a Department of Energy (DOE) ...

2011-12-19T23:59:59.000Z

271

H. UNREVIEWED SAFETY QUESTIONS  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

all safety basis documents submitted to DOE and (2) preparation of a safety evaluation report concerning the safety basis for a facility. 2. DOE will maintain a public list on the...

272

Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1  

Science Conference Proceedings (OSTI)

The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

Not Available

1993-01-01T23:59:59.000Z

273

System for the Analysis of Global Energy Markets - Vol. I, Model Documentation  

Reports and Publications (EIA)

Documents the objectives and the conceptual and methodological approach used in the development of projections for the International Energy Outlook. The first volume of this report describes the SAGE methodology and provides an in-depth explanation of the equations of the model.

Barry Kapilow-Cohen

2003-08-01T23:59:59.000Z

274

Nuclear criticality safety analysis summary report: The S-area defense waste processing facility  

SciTech Connect

The S-Area Defense Waste Processing Facility (DWPF) can process all of the high level radioactive wastes currently stored at the Savannah River Site with negligible risk of nuclear criticality. The characteristics which make the DWPF critically safe are: (1) abundance of neutron absorbers in the waste feeds; (2) and low concentration of fissionable material. This report documents the criticality safety arguments for the S-Area DWPF process as required by DOE orders to characterize and to justify the low potential for criticality. It documents that the nature of the waste feeds and the nature of the DWPF process chemistry preclude criticality.

Ha, B.C.

1994-10-21T23:59:59.000Z

275

Strategic Safety Goals | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Documents & Publications Occupational Safety Performance Trends Development of the Nuclear Safety Information Dashboard - September 2012 EA-1954: Draft Environmental Assessment...

276

Electrical Safety - Monthly Analyses of Electrical Safety Occurrences  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Analysis Office of Analysis Operating Experience Committee Safety Alerts Safety Bulletins Annual Reports Special Operations Reports Safety Advisories Special Reports Causal Analysis Reviews Contact Us HSS Logo Electrical Safety Monthly Analyses of Electrical Safety Occurrences 2013 September 2013 Electrical Safety Occurrences August 2013 Electrical Safety Occurrences July 2013 Electrical Safety Occurrences June 2013 Electrical Safety Occurrences May 2013 Electrical Safety Occurrences April 2013 Electrical Safety Occurrences March Electrical Safety Occurrence February Electrical Safety Occurrence January Electrical Safety Occurrence 2012 December Electrical Safety Occurrence November Electrical Safety Occurrence October Electrical Safety Occurrence September Electrical Safety Occurrence

277

Knowledge-centric and language independent framework for safety analysis tools  

Science Conference Proceedings (OSTI)

This paper presents a knowledge-centric and language independent framework and its application to develop safety analysis tools for avionics systems. A knowledge-centric approach is important to address domain-specific needs, with respect to the types ...

S. C. Kothari; Luke Bishop; Jeremias Sauceda; Gary Daugherty

2004-03-01T23:59:59.000Z

278

Technical Review Report for the Model 9975-96 Package Safety Analysis Report for Packaging (S-SARP-G-00003, Revision 0, January 2008)  

SciTech Connect

This Technical Review Report (TRR) documents the review, performed by the Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the U.S. Department of Energy (DOE), on the Safety Analysis Report for Packaging, Model 9975, Revision 0, dated January 2008 (S-SARP-G-00003, the SARP). The review includes an evaluation of the SARP, with respect to the requirements specified in 10 CFR 71, and in International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9975-96 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The safety analysis of the Model 9975-85 Packaging is documented in the Safety Analysis Report for Packaging, Model 9975, B(M)F-85, Revision 0, dated December 2003. The Model 9975-85 Package is certified by DOE Certificate of Compliance (CoC) package identification number, USA/9975/B(M)F-85, for the transportation of Type B quantities of uranium metal/oxide, {sup 238}Pu heat sources, plutonium/uranium metals, plutonium/uranium oxides, plutonium composites, plutonium/tantalum composites, {sup 238}Pu oxide/beryllium metal.

West, M

2009-05-22T23:59:59.000Z

279

Industrial fuel choice analysis model. Volume II. Appendices to model documentation  

SciTech Connect

Descriptions, documentation, and other information are included in these appendices dealing with industrial fuel choices: Energy Consumption Data Base; Major Fuel Burning Installation Survey; American Boiler Manufacturers Association Data File; Midrange Energy Forecasting System; Projection Method; Capacity Utilization Rates; Nonboiler Characteristics; Boiler Capital and O and M Cost Data; Nonboiler Capital and O and M Cost Data; Approach to Estimating Energy Impacts of the Coal Conversion Regulatory Program; Index or Acronyms.

1979-01-08T23:59:59.000Z

280

WIPP Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

a large file size. Environmental Monitoring Documents about environmental monitoring at WIPP, including annual site environmental reports Environmental Protection Agency...

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Thread-safety in an MPI implementation: Requirements and analysis  

Science Conference Proceedings (OSTI)

The MPI-2 Standard has carefully specified the interaction between MPI and user-created threads. The goal of this specification is to allow users to write multithreaded MPI programs while also allowing MPI implementations to deliver high performance. ... Keywords: MPI implementation, Message-passing interface (MPI), Multithreaded programming, Thread-safety

William Gropp; Rajeev Thakur

2007-09-01T23:59:59.000Z

282

Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.  

SciTech Connect

This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the experienced user-base and the experimental validation base was decaying away quickly.

Carbajo, Juan (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin, Madison, WI); Schmidt, Rodney Cannon; Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Ludewig, Hans (Brookhaven National Laboratory, Upton, NY); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Serre, Frederic (Centre d'%C3%94etudes nucl%C3%94eaires de Cadarache %3CU%2B2013%3E CEA, France)

2011-06-01T23:59:59.000Z

283

Authorization basis supporting documentation for plutonium finishing plant  

Science Conference Proceedings (OSTI)

The identification and definition of the authorization basis for the Plutonium Finishing Plant (PFP) facility and operations are essential for compliance to DOE Order 5480.21, Unreviewed Safety Questions. The authorization basis, as defined in the Order, consists of those aspects of the facility design basis, i.e., the structures, systems and components (SSCS) and the operational requirements that are considered to be important to the safety of operations and are relied upon by DOE to authorize operation of the facility. These facility design features and their function in various accident scenarios are described in WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysis Report (FSAR), Chapter 9, `Accident Analysis.` Figure 1 depicts the relationship of the Authorization Basis to its components and other information contained in safety documentation supporting the Authorization Basis. The PFP SSCs that are important to safety, collectively referred to as the `Safety Envelope` are discussed in various chapters of the FSAR and in WHC-SD-CP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements. Other documents such as Criticality Safety Evaluation Reports (CSERS) address and support some portions of the Authorization Basis and Safety Envelope.

King, J.P., Fluor Daniel Hanford

1997-03-05T23:59:59.000Z

284

Document Reviews | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Document Reviews Document Reviews Document Reviews The Office of Document Reviews, within the Office of Health, Safety and Security information and document declassification efforts promote the release of information needed by an informed citizenry to understand and oversee the actions of its Government. To meet our mission requirements, the Office of Document Reviews: Conducts pre-publication reviews of documents generated in classified subject areas at Headquarters that are to be released to the public. Conducts document reviews for other HSS and Headquarters organizations to identify classified and controlled unclassified information. Reviews classified documents requested under the Freedom of Information Act for the Department and denies the release of the document in total or provides a redacted copy for release to the requester.

285

Required Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Required Documents Required Documents Required Documents All foreign nationals, including students and postdocs, must select the foreign nationals employment category to complete the new-hire process. Contact (505) 665-7158 Email Complete following forms before New-Hire Orientation Be sure to bring the forms with you for the orientation event, but do not sign and date: Form I-9, Employment Eligibility Verification (pdf) - original, unexpired documents for verification of employment eligibility. Please refer to the I-9 verification form titled, "Lists of Acceptable Documents", which was included with your offer letter. (Laminated documents or hospital/temporary birth certificates are not accepted.) Note: Failure to provide required documents will result in delay and/or

286

Documents: Disposal of DUF6 Conversion Products  

NLE Websites -- All DOE Office Websites (Extended Search)

DUF6 Conversion Products Search Documents: Search PDF Documents View a list of all documents Disposal of DUF6 Conversion Products PDF Icon Engineering Analysis for Disposal of...

287

FAQS JOB TASK ANALYSIS - Electrical Systems and Safety Oversight  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Electrical Systems and Safety Oversight Electrical Systems and Safety Oversight Step 1 Identify and evaluate tasks - Develop a comprehensive list of tasks that define the job. o A great starting point is the list of Duties and Responsibilities from the FAQS. o Give careful thought to additional tasks that could be considered. o Don't worry about deleting tasks at this point - that is a part of the process further down. - List the tasks (and their sources, e.g., Duties and Responsibilities #1) in the chart below. - Discuss each task as a group and come to a consensus pertaining to Importance and Frequency of the task (i.e., each team member can consent to the assigned value, even if they don't exactly agree with it). - When all values have been assigned, consider as a group deleting tasks that receive

288

Hanford Generic Interim Safety Basis  

SciTech Connect

The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

Lavender, J.C.

1994-09-09T23:59:59.000Z

289

Occupational Safety Performance Trends | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Occupational Safety Trends More Documents & Publications Strategic Safety Goals EA-1954: Draft Environmental Assessment Development of the Nuclear Safety Information Dashboard...

290

DOE-STD-1027-92; Hazard Categorization and Accident Analysis Techniques For Compliance With DOE Order 5480.23, Nuclear Safety Analysis Reports  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7-92 7-92 December 1992 CHANGE NOTICE NO.1 September 1997 DOE STANDARD HAZARD CATEGORIZATION AND ACCIDENT ANALYSIS TECHNIQUES FOR COMPLIANCE WITH DOE ORDER 5480.23, NUCLEAR SAFETY ANALYSIS REPORTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650. Order No. DE98001283 Change Notice No. 1 DOE-STD-1027-92

291

ELECTRICAL POWER SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The purpose of this revision of the System Description Document (SDD) is to establish requirements that drive the design of the electrical power system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience are design engineers. This type of SDD leads and follows the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential to performing the design process. This SDD follows the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to this system are obtained from ''Project Functional and Operational Requirements'' (F&OR) (Siddoway, 2003). Other requirements to support the design process have been taken from higher level requirements documents such as ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), the fire hazards analyses, and the preclosure safety analysis. The above mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canori and Leitner 2003) requirements. This SDD includes several appendices with supporting information. Appendix B lists key system charts, diagrams, drawings, and lists; and Appendix C is a list of system procedures.

M. Maniyar

2004-06-22T23:59:59.000Z

292

Current Safety Performance Trends  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Protection, Sustainability Support & Corporate Safety Analysis HS-20 Home Mission & Functions Office of Sustainability, Environment, Safety and Anaylsis (SESA) ...

293

Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility  

SciTech Connect

The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL`s Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed.

Charak, I; Pedersen, D.R. [Argonne National Lab., IL (United States); Forrester, R.J.; Phipps, R.D. [Argonne National Lab., Idaho Falls, ID (United States)

1993-09-01T23:59:59.000Z

294

TAO: Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Home Download Documentation Users Manual and Manual pages Example Programs Installation Changes Publications Referencing TAO Impact Who We Are Acknowledgements License Contact Us...

295

Analysis of Fundamental NIST Sphere Experiments Related to Criticality Safety  

SciTech Connect

A series of neutron transport experiments was performed in 1989 and 1990 at NIST (National Institute of Standards and Technology) using a spherical stainless steel container and fission chambers. These experiments were performed to help understand errors observed in criticality calculations for arrays of individually subcritical components, particularly solution arrays [1-3]. They were supported by the U.S. Department of Energy, Environment and Health, Nuclear Criticality Technology and Safety Project. The intent was to evaluate the possibility that the criticality prediction errors stem from errors in the calculation of neutron leakage from individual components of the array. Thus, the explicit product of the experiments was the measurement of the leakage flux, as characterized by various Cd-shielded and unshielded fission rates. Because the various fission rates have different neutron-energy sensitivities, collectively they give an indication of the energy dependence of the leakage flux. Leakage and moderation were varied systematically through the use of different diameter spheres, with and without water. Some of these experiments with bare fission chambers have been evaluated by the International Criticality Safety Benchmark Evaluation Project (ICSBEP)[4].

Kim, Soon S.

2007-06-01T23:59:59.000Z

296

TEC Working Group Topic Groups Rail Archived Documents | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Group Topic Groups Rail Archived Documents ARCHIVED DOCUMENTS Inspections Summary Matrix TEC Transportation Safety WIPP-PIG Rail Comparison Regulatory Summary Matrix More...

297

SACRD: a data base for fast reactor safety computer codes, operational procedures  

SciTech Connect

SACRD (Safety Analysis Computerized Reactor Data) is a data base of nondesign-related information used in computer codes for fast reactor safety analyses. This document reports the procedures used in SACRD to help assure a reasonable level of integrity of the material contained in the data base. It also serves to document much of the computer software used with the data base.

Forsberg, V.M.; Arwood, J.W.; Greene, N.M.; Raiford, G.B.

1980-09-01T23:59:59.000Z

298

Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory  

DOE Green Energy (OSTI)

To ensure the continued safety of SERI's employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMS). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance. This document contains the appendices to the NREL safety analysis report.

Crandall, R.S.; Nelson, B.P.; Moskowitz, P.D.; Fthenakis, V.M.

1992-07-01T23:59:59.000Z

299

Guiding Documents and Links | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Order 436.1 - Departmental Sustainability DOE Policy 450.4A - Integrated Safety Management Policy 2012 DOE Strategic Sustainability Performance Plan LM Documents...

300

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT  

Science Conference Proceedings (OSTI)

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

KOZLOWSKI, S.D.

2007-05-30T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Untitled Document  

NLE Websites -- All DOE Office Websites (Extended Search)

The Office of Health, Safety and Security (HSS) has upgraded. The old URL has been changed from http:www.eh.dov.gov to http:www.hss.doe.gov You will be redirected to the new...

302

Volume II - Accident and Operational Safety Analysis Handbook  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

into analysis tools: Culture Attribute Matrix (CAM); Missed Opportunity Matrix (MOM); Human Error Precursor Matrix (TWIN); Latent Organizational Weakness Table (LOW) *...

303

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

by industry for recycling facilities 2 , is a systematic analysis to identify facility and external hazards and their potential for initiating accident sequences, the...

304

Criticality safety analysis of Hanford Waste Tank 241-101-SY  

SciTech Connect

As part of a safety assessment for proposed pump mixing operations to mitigate episodic gas releases in Tank 241-101-SY at the Hanford Site, Richland, Washington, a criticality safety analysis was made using the Sn transport code ONEDANT. The tank contains approximately one million gallons of waste and an estimated 910 G of plutonium. the criticality analysis considers reconfiguration and underestimation of plutonium content. The results indicate that Tank SY-101 does not present a criticality hazard. These methods are also used in criticality analyses of other Hanford tanks.

Perry, R.T.; Sapir, J.L.; Krohn, B.J.

1993-12-31T23:59:59.000Z

305

Cost-Effectiveness Analysis of the 2009 and 2012 IECC Residential Provisions Technical Support Document  

SciTech Connect

This analysis was conducted by Pacific Northwest National Laboratory (PNNL) in support of the U.S. Department of Energys (DOE) Building Energy Codes Program (BECP). DOE supports the development and adoption of efficient residential and commercial building energy codes. These codes set the minimum requirements for energy efficient building design and construction and ensure energy savings on a national level. This analysis focuses on one and two family dwellings, townhomes, and low-rise multifamily residential buildings. For these buildings, the basis of the energy codes is the International Energy Conservation Code (IECC). This report does not address commercial and high-rise residential buildings, which reference ANSI/ASHRAE/IES Standard 90.1.

Mendon, Vrushali V.; Lucas, Robert G.; Goel, Supriya

2012-12-04T23:59:59.000Z

306

ELM Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

ELM Home Documents ELM Plan ELM Tracts Tract Map ELM at Work ELM Home Documents ELM Plan ELM Tracts Tract Map ELM at Work ELM Documents Committee Charter: The formal charge from the Fermilab director to the ELM committee. Committee Membership: A list of the current members of the ELM committee. Tract Management ELM Plan: The site ecological management plan for the current year. Tract List: A list of links to tract summaries from the latest approved ELM plan. Tract Map: An interactive map showing the locations of the various ELM tracts. Fire Management Non-structural Fire Management Plan: (Microsoft Word Document) Burn Histories: View the burn histories for the relevant ELM tracts. Map of Proposed Burns for the current or upcoming fire management season. This map is interactive and can also display the locations of past burn sites.

307

Key Documents  

Science Conference Proceedings (OSTI)

AOCS by-laws, code of ethics and anti trust policy established during our 100+ legacy. Key Documents AOCS History and Governance about us aocs committees contact us division council fats governing board history oils professionals science value cen

308

AFFECTED DOCUMENT  

Office of Legacy Management (LM)

REF I I lOWED BY: (ORG) I I I I I TARGET DATE I CLOSING CCN COMPL DATE CLOSING REF TECHNICAL SERVICES DIVISION (TSD) BACKFIT (Documents dated prior to 1 November 1988) FUSRAP...

309

Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 1, Rev. 14  

Science Conference Proceedings (OSTI)

The condensed version of the TRUPACT-II Contact Handled Transuranic Waste Safety Analysis Report for Packaging (SARP) contains essential material required by TRUPACT-II users, plus additional contents (payload) information previously submitted to the U.S. Nuclear Regulatory Commission. All or part of the following sections, which are not required by users of the TRUPACT-II, are deleted from the condensed version: (i) structural analysis, (ii) thermal analysis, (iii) containment analysis, (iv) criticality analysis, (v) shielding analysis, and (vi) hypothetical accident test results.

NONE

1994-10-01T23:59:59.000Z

310

Decommissioning License Termination Plan Documents and Lessons Learned: Summary of LTPs for Two Reactors and Nuclear Regulatory Comm ission Safety Evaluation Reports for Three Nuclear Power Plant LTPs  

Science Conference Proceedings (OSTI)

This report offers those utilities beginning the preparation of License Termination Plans (LTPs) in the near future a comprehensive summary of the approaches currently taken in LTP preparation by major nuclear decommissioning projects. The report details the approach taken in addressing each element of the LTP, and the lessons learned by those utilities currently undergoing the license termination process. This document provides needed guidance for the LTP process, and will greatly benefit utilities cons...

2004-04-28T23:59:59.000Z

311

Hanford Sludge Treatment Project 105-KW Final Safety Analysis...  

NLE Websites -- All DOE Office Websites (Extended Search)

Analysis Report (HNF-SD-WM-SAR-062, Revision 14C) for the Sludge Treatment Project at the Hanford Site. 2.0 BACKGROUND The Sludge Treatment Project manages the removal of...

312

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Executive Summary This paper addresses why the use of an Integrated Safety Analysis ("ISA") is appropriate for fuel recycling facilities 1 which would be licensed under new regulations currently being considered by NRC. The use of the ISA for fuel facilities under Part 70 is described and compared to the use of a Probabilistic Risk Assessment ("PRA") for reactor facilities. A basis is provided for concluding that future recycling facilities - which will possess characteristics similar to today's fuel cycle facilities and distinct from reactors - can best be assessed using established qualitative or semi-quantitative ISA techniques to achieve and demonstrate safety in an effective and efficient manner.

313

Fuzzy-algebra uncertainty analysis for abnormal-environment safety assessment  

Science Conference Proceedings (OSTI)

Many safety (risk) analyses depend on uncertain inputs and on mathematical models chosen from various alternatives, but give fixed results (implying no uncertainty). Conventional uncertainty analyses help, but are also based on assumptions and models, the accuracy of which may be difficult to assure. Some of the models and assumptions that on cursory examination seem reasonable can be misleading. As a result, quantitative assessments, even those accompanied by uncertainty measures, can give unwarranted impressions of accuracy. Since analysis results can be a major contributor to a safety-measure decision process, risk management depends on relating uncertainty to only the information available. The uncertainties due to abnormal environments are even more challenging than those in normal-environment safety assessments, and therefore require an even more cautious approach. A fuzzy algebra analysis is proposed in this report that has the potential to appropriately reflect the information available and portray uncertainties well, especially for abnormal environments.

Cooper, J.A.

1994-01-01T23:59:59.000Z

314

Tracking and Analysis Framework (TAF) model documentation and user`s guide  

SciTech Connect

With passage of the 1990 Clean Air Act Amendments, the United States embarked on a policy for controlling acid deposition that has been estimated to cost at least $2 billion. Title IV of the Act created a major innovation in environmental regulation by introducing market-based incentives - specifically, by allowing electric utility companies to trade allowances to emit sulfur dioxide (SO{sub 2}). The National Acid Precipitation Assessment Program (NAPAP) has been tasked by Congress to assess what Senator Moynihan has termed this {open_quotes}grand experiment.{close_quotes} Such a comprehensive assessment of the economic and environmental effects of this legislation has been a major challenge. To help NAPAP face this challenge, the U.S. Department of Energy (DOE) has sponsored development of an integrated assessment model, known as the Tracking and Analysis Framework (TAF). This section summarizes TAF`s objectives and its overall design.

Bloyd, C.; Camp, J.; Conzelmann, G. [and others

1996-12-01T23:59:59.000Z

315

Supplement analysis for continued operation of Lawrence Livermore National Laboratory and Sandia National Laboratories, Livermore. Volume 2: Comment response document  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE), prepared a draft Supplement Analysis (SA) for Continued Operation of Lawrence Livermore National Laboratory (LLNL) and Sandia National Laboratories, Livermore (SNL-L), in accordance with DOE`s requirements for implementation of the National Environmental Policy Act of 1969 (NEPA) (10 Code of Federal Regulations [CFR] Part 1021.314). It considers whether the Final Environmental Impact Statement and Environmental Impact Report for Continued Operation of Lawrence Livermore National Laboratory and Sandia National Laboratories, Livermore (1992 EIS/EIR) should be supplement3ed, whether a new environmental impact statement (EIS) should be prepared, or no further NEPA documentation is required. The SA examines the current project and program plans and proposals for LLNL and SNL-L, operations to identify new or modified projects or operations or new information for the period from 1998 to 2002 that was not considered in the 1992 EIS/EIR. When such changes, modifications, and information are identified, they are examined to determine whether they could be considered substantial or significant in reference to the 1992 proposed action and the 1993 Record of Decision (ROD). DOE released the draft SA to the public to obtain stakeholder comments and to consider those comments in the preparation of the final SA. DOE distributed copies of the draft SA to those who were known to have an interest in LLNL or SNL-L activities in addition to those who requested a copy. In response to comments received, DOE prepared this Comment Response Document.

NONE

1999-03-01T23:59:59.000Z

316

PETSc: Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Documentation Documentation Home Download Features Documentation Manual pages and Users Manual Citing PETSc Tutorials Installation AMS Changes Bug Reporting Code Management FAQ License Linear Solver Table Applications/Publications Miscellaneous External Software Developers Site PETSc is a sophisticated package and fully understanding its usage requires time. However, application programmers can easily begin to use PETSc from a high level and then gradually learn more details according to their needs. Users should read the users manual before attempting to do any serious coding with PETSc! PETSc users manual - pdf (fully searchable with hyperlinks) Index of all help topics Index of all manual pages Strategies for using PETSc with Fortran PETSc Manual Pages and Examples MPI TAO Vector Operations (Vec)

317

Preliminary Accident Analysis for Construction and Operation of the Chornobyl New Safety Confinement  

Science Conference Proceedings (OSTI)

Analysis of potential exposure of personal and population during construction and exploitation of the New Safe Confinement was made. Scenarios of hazard event development were ranked. It is shown, that as a whole construction and exploitation of the NSC are in accordance with actual radiation safety norms of Ukraine.

Batiy, Valeriy; Rubezhansky, Yruiy; Rudko, Vladimir; shcherbin, vladimir; Yegorov, V; Schmieman, Eric A.; Timmins, Douglas C.

2005-08-08T23:59:59.000Z

318

Safety Design Strategy RM  

Energy.gov (U.S. Department of Energy (DOE))

The SDS Review Module (RM) is a tool that assists DOE federal project review teams in evaluating the adequacy of the conceptual safety design strategy documentation package (Conceptual Safety...

319

Oversight Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

oversight-documents Forrestal Building 1000 oversight-documents Forrestal Building 1000 Independence Avenue, SW Washington, DC 205851.800.dial.DOE en Independent Oversight Activity Report, Idaho Cleanup Project - November 2013 http://energy.gov/hss/downloads/independent-oversight-activity-report-idaho-cleanup-project-november-2013 Independent Oversight Activity Report, Idaho Cleanup Project - November 2013

320

Enforcement Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

enforcement-documents Forrestal Building 1000 enforcement-documents Forrestal Building 1000 Independence Avenue, SW Washington, DC 205851.800.dial.DOE en Enforcement Letter, WEL-2013-04 http://energy.gov/hss/downloads/enforcement-letter-wel-2013-04 Enforcement Letter, WEL-2013-04

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Top-Off Safety Analysis for NSLS-II  

Science Conference Proceedings (OSTI)

Top-off injection will be adopted in NSLS-II. To ensure no injected beam can pass into experimental beamlines with open photon shutters during top-off injection, simulation studies for possible machine fault scenarios are required. We compare two available simulation methods, backward (H. Nishimura-LBL) and forward tracking (A. Terebilo-SLAC). We also discuss the tracking settings, fault scenarios, apertures and interlocks considered in the analysis.

Li,Y.; Casey, B.; Heese, R.; Hseuh, H.; Job, O.; Krinsky, S.; Parker, B.; Shaftan, T.; Sharma, S.

2009-05-04T23:59:59.000Z

322

Coiled Tubing Safety Manual  

SciTech Connect

This document addresses safety concerns regarding the use of coiled tubing as it pertains to the preservation of personnel, environment and the wellbore.

Crow, W.

1999-04-06T23:59:59.000Z

323

Complete Safety Training  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Safety Training Print Complete Safety Training Print All users are required to take safety training before they may begin work at the ALS. It is the responsibility of the Principal Investigator and the Experimental Lead to ensure that all members of the team receive proper safety training before an experiment begins. Special consideration is available for NSLS users who have completed, and are up-to-date with, their safety training, NSLS Safety Module; they may take a brief equivalency course ALS 1010: Site-Specific Safety at the ALS in lieu of the complete safety training in ALS 1001: Safety at the ALS. These users must present documentation upon arrival at the ALS showing that they have completed NSLS Safety Module; see Acceptable NSLS Safety Documentation for examples.

324

Complete Safety Training  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Safety Training Print Complete Safety Training Print All users are required to take safety training before they may begin work at the ALS. It is the responsibility of the Principal Investigator and the Experimental Lead to ensure that all members of the team receive proper safety training before an experiment begins. Special consideration is available for NSLS users who have completed, and are up-to-date with, their safety training, NSLS Safety Module; they may take a brief equivalency course ALS 1010: Site-Specific Safety at the ALS in lieu of the complete safety training in ALS 1001: Safety at the ALS. These users must present documentation upon arrival at the ALS showing that they have completed NSLS Safety Module; see Acceptable NSLS Safety Documentation for examples.

325

Complete Safety Training  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Safety Training Print Complete Safety Training Print All users are required to take safety training before they may begin work at the ALS. It is the responsibility of the Principal Investigator and the Experimental Lead to ensure that all members of the team receive proper safety training before an experiment begins. Special consideration is available for NSLS users who have completed, and are up-to-date with, their safety training, NSLS Safety Module; they may take a brief equivalency course ALS 1010: Site-Specific Safety at the ALS in lieu of the complete safety training in ALS 1001: Safety at the ALS. These users must present documentation upon arrival at the ALS showing that they have completed NSLS Safety Module; see Acceptable NSLS Safety Documentation for examples.

326

Annual Planning Summaries: Health, Safety, and Security (HSS...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Agencies You are here Home Annual Planning Summaries: Health, Safety, and Security (HSS) Annual Planning Summaries: Health, Safety, and Security (HSS) Document(s) Available...

327

Safety and Techno-Economic Analysis of Solvent Selection for Supercritical Fischer-Tropsch Synthesis Reactors  

E-Print Network (OSTI)

Fisher-Tropsch Synthesis is a primary pathway for gas-to-liquid technology. In order to overcome commercial problems associated with reaction and transport phenomena, the use of supercritical solvents has been proposed to increase chemical conversion and improve temperature control. One of the major challenges in designing the supercritical FTS systems is the solvent selection. Numerous alternatives exist and should be screened based on relevant criteria. The main aim of the thesis was to develop a safety metric that can be incorporated in the selection of an optimal supercritical solvent or a mixture of solvents. The objective was to minimize the cost while satisfying safety constraints or to establish tradeoffs between cost and safety. Hydrocarbons from C3 to C9 were identified as feasible solvents for FTS purposes. The choice of these solvents is dependent on their mixture critical temperature and pressure requirements that need to be satisfied upon entry into the FTS reactor. A safety metric system was developed in order to compare the risk issues associated with using the aforementioned solvents. In addition, an economic analysis of using the different solvents was performed. Finally, a case study was solved to illustrate the use of the proposed metrics and the selection of solvents based on safety and techno-economic criteria.

Hamad, Natalie

2011-12-01T23:59:59.000Z

328

Developing a Comprehensive Software Suite for Advanced Reactor Performance and Safety Analysis  

SciTech Connect

This paper provides an introduction to the reactor analysis capabilities of the nuclear power reactor simulation tools that are being developed as part of the U.S. Department of Energy s Nuclear Energy Advanced Modeling and Simulation (NEAMS) Toolkit. The NEAMS Toolkit is an integrated suite of multi-physics simulation tools that leverage high-performance computing to reduce uncertainty in the prediction of performance and safety of advanced reactor and fuel designs. The Toolkit effort is comprised of two major components, the Fuels Product Line (FPL), which provides tools for fuel performance analysis, and the Reactor Product Line (RPL), which provides tools for reactor performance and safety analysis. This paper provides an overview of the NEAMS RPL development effort.

Pointer, William David [ORNL; Bradley, Keith S [ORNL; Fischer, Paul F [ORNL; Smith, Micheal A [ORNL; Tautges, Timothy J [ORNL; Ferencz, Robert M [ORNL; Martineau, Richard C [ORNL; Jain, Rajeev [ORNL; Obabko, Aleksandr [Argonne National Laboratory (ANL); Billings, Jay Jay [ORNL

2013-01-01T23:59:59.000Z

329

Office of Health & Safety - Mission and Functions  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Beryllium Chemical Safety Biological Safety Radiation Safety Rules 10 CFR 707 10 CFR 835 10 CFR 850 10 CFR 851 OHS Document Collection Site Medical Clinics REACTS EEOICPA...

330

CHRG Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Documents Documents Benefit Value Manual Davis-Bacon Act Desk Guide Davis-Bacon Act of 1931 DEAR 970.5204-81 Diversity Plan - Acquisition Letter Directory of Classifications DOE Acquisition Regulations (Chapter 970) DOE F 350.1 - Contractor Salary-Wage Increase Expenditure Report DOE O 311.1A Equal Opportunity and Diversity Program DOE O 350.1 "Contractor Human Resources Programs" DOE O 442.1 Employee Concerns Program Equal Employment Opportunity Preaward Clearance Request Form Mandatory Guidelines for Federal Workplace Drug Testing Programs Procurement Policy Flashes Service Contract Act of 1965 Wage Determination Request Form Wage Determinations On-line Workplace Substance Abuse Programs at DOE Sites Reports Annual Payroll & Residence Report for Oak Ridge Area

331

Untitled Document  

NLE Websites -- All DOE Office Websites (Extended Search)

Remote-Handled Transuranic Waste Study - Remote-Handled Transuranic Waste Study - Main Menu DOE/CAO 95-1095 REMOTE-HANDLED TRANSURANIC WASTE STUDY U.S. Department of Energy Carlsbad Area Office Carlsbad, New Mexico October 1995 This document has been reproduced directly from the best possible copy. It is available to DOE and DOE contractors at the following address: Office of Scientific and Technical Information P. O. Box 62 Oak Ridge, TN 37831 For prices contact (615) 576-8401 The local WIPP contact for this document is George Basabilvazo (pronounced Baasa-bill-vaaso) (505) 234-7488 or E-Mail George.Basabilvazo@wipp.ws TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS (See below) EXECUTIVE SUMMARY (See below) 1.0 INTRODUCTION 1.1 Objectives 1.2 Background 2.0 THE TRANSURANIC WASTE DISPOSAL STRATEGY 2.1 Room Configuration

332

NEPA Documentation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Note for: Cynthia Quarterman Note for: Cynthia Quarterman Keith Harper From: Carol Borgstrom Subject: NEPA Documentation Date: December 3, 2008 Attached, per your request, are two lists: (1) DOE environmental assessments (EAs) issued since 12/1/2006 and (2) DOE environmental impact statements (EISs) issued since 12/1/2006. Also, per your request, is a copy of a general NEPA briefing provided to the Acting Deputy Secretary in May 2008. Please let me know if you have any further questions (carol.borgstrom @hq.doe.gov; 202-586-4600). cc: Ingrid Kolb, MA-1 (without attachments) Janet Barsy, GC-1 EA Database Listing Document Start FONSI Months Total NEPA Cost Program Number Title Date Date Complete Ops Office Office DOE/EA-1389 Charlie Creek-Williston Transmission 3/20/2001 2/20/2008 83.2 $345,236.21 WAPA

333

Superconducting x-ray lithography source Phase 1 (XLS) safety analysis report  

SciTech Connect

This paper discusses safety aspects associated with the superconducting x-ray lithography source. The policy, building systems safety and storage ring systems safety are specifically addressed. (LSP)

Blumberg, L. (ed.)

1990-07-01T23:59:59.000Z

334

Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR  

SciTech Connect

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

1983-08-01T23:59:59.000Z

335

Regulatory guidance document  

SciTech Connect

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

NONE

1994-05-01T23:59:59.000Z

336

Advanced techniques for safety analysis applied to the gas turbine control system of ICARO co-generative plant  

E-Print Network (OSTI)

The paper describes two complementary and integrable approaches, a probabilistic one and a deterministic one, based on classic and advanced modelling techniques for safety analysis of complex computer based systems. The probabilistic approach is based on classical and innovative probabilistic analysis methods. The deterministic approach is based on formal verification methods. Such approaches are applied to the gas turbine control system of ICARO co generative plant, in operation at ENEA CR Casaccia. The main difference between the two approaches, behind the underlining different theories, is that the probabilistic one addresses the control system by itself, as the set of sensors, processing units and actuators, while the deterministic one also includes the behaviour of the equipment under control which interacts with the control system. The final aim of the research, documented in this paper, is to explore an innovative method which put the probabilistic and deterministic approaches in a strong relation to overcome the drawbacks of their isolated, selective and fragmented use which can lead to inconsistencies in the evaluation results. 1.

Ro Bologna; Ester Ciancamerla; Piero Incalcaterra; Michele Minichino; Andrea Bobbio; Universit Del Piemonte Orientale; Enrico Tronci

2001-01-01T23:59:59.000Z

337

Technical and Analytical Support Services to the Office of Environmental Analysis, Office of Environment, Safety and Health. Final report  

SciTech Connect

The primary purpose of this contract was to provide technical analyses, studies, and reviews related to land use/water issues and energy resource development in support of the activities of the Office of Environmental Analysis, Office of Environment, Safety and Health. Tasks under this contract included: Issue Papers. Energetics provided issue papers on a number of specific energy and environmental issue areas. Each issue paper consisted of a systematic review and analysis of major factors (technical, legal, environmental, economic, energy, health and social) that could enter into DOE`s environmental/energy policy decisions; Special Analyses. Energetics conducted special in-depth technical analyses as requested by the Contracting Officer`s Technical Representative (COTR); and Critical Review and Evaluation of Program Reports. Energetics performed critical reviews of a number of technical reports arising from DOE program activities. These documents included issue papers and reports resulting from special technical analyses of specific issues, technologies, or broad areas of concern. Reviews focused on both the technical and programmatic impact of the report. Energetics made recommendations and gave input to assist DOE in determining the environmental impacts of energy policies and projects.

NONE

1995-02-01T23:59:59.000Z

338

2011 Annual Workforce Analysis and Staffing Plan Report - NNSA for Safety and Health  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Annual Workforce Analysis and Staffing Plan Report Annual Workforce Analysis and Staffing Plan Report As of December 31, 2011 Reporting Office: NNSA NA-SH Section One: Current Mission(s) of the Organization and Potential Changes The Office of the Associate Administrator for Safety and Health (NA-SH) provides mission enabling support to the NNSA Administrator, Central Technical Authority (CTA), Acquisition Executives, senior NNSA officials, program officers and site offices. NA-SH enables other NNSA organizations to fulfill NNSA missions while protecting the environment and safeguarding the safety and health of the public and the workforce. Section Two: SITE CHARACTERISTICS TABLE 1 Number of Hazard Category 1, 2, or 3 Nuclear Facilities: HC 1: 0; HC 2: 0; HC 3: 0 Number of Radiological Facilities

339

Architecture for Interlock Systems Reliability Analysis with Regard to Safety and Availability  

E-Print Network (OSTI)

In the design of interlock loops for the signal exchange in machine protection systems, the choice of the hardware architecture impacts on machine safety and availability. The reliable performance of a machine stop (leaving the machine in a safe state) in case of an emergency, is an inherent requirement. The constraints in terms of machine availability on the other hand may differ from one facility to another. Spurious machine stops, lowering machine availability, may to a certain extent be tolerated in facilities where they do not cause undue equipment wearout. In order to compare various interlock loop architectures in terms of safety and availability, the occurrence frequencies of related scenarios have been calculated in a reliability analysis, using a generic analytical model. This paper presents the results and illustrates the potential of the analysis method for supporting the choice of interlock system architectures.

Wagner, S; Schmidt, R; Zerlauth, M; Vergara-Fernandez, A

2011-01-01T23:59:59.000Z

340

NIF special equipment construction health and safety plan  

SciTech Connect

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

Sawicki, R.H.

1997-07-28T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

[DOCUMENT TITLE  

NLE Websites -- All DOE Office Websites (Extended Search)

ACQUISITION STRATEGY TEAM SUPPORT Y-12, PANTEX, AND SRS OPTION ANALYSIS SUMMARY REPORT: 2009 Report Findings & 2010 Analysis Update June 9, 2011 Prepared for: U.S. Department of...

342

Ehron Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Ehron Documents Ehron Documents 1993 S-F-1325.12 CORRESPONDENCE CONTROL FORM (11-90) OFFICE OF THE EXECLTIVE SECRETARIAT ACTIVITY ADD DO NOT DETACH FROM ORIGINAL CORRESPONDENCE 01/19/93 10:17 SOURCE CODE pM PUBLIC MAIL SPEC INT: _ CONTROL N( S93-000578 DATE CORR: 01/13/93 DATERECD: 01/19/93 DATECNTRL: 01/19/93 -DATE DUE: LETTER: MEMO: TWX: _OTHER: MOTION TO:SECY: X DEPSEC: UN SEC: OTHER: ROM:FLOWERS,G PATRICK TX O REMARKS: ENRON CORP. UB J : LEGAL -=--_- LITIGATION FOR USE fY ACT N OFFICE ONLY MOTION FOR LEAVE TO INTERVENE ACTION REFERRED TO DATE RETURN TO DUE OF NORTHERN NATURAL GAS CO., DATE TRANSWESTERN PIPELINE CO., 2 FLORIDA GAS TRANSMISSION CO... _3-_ ACTION TO: rr - TYPE ACTION: Appropriate action SIG OF: 3NCURRENCE: i NFORMATION:DS US EP FE ES1 D02 FILE CODE:PMFLOWFRS-ES930'00578 CONTROL ANALYST: B ATCHERSON 6-2255

343

Flammable gas tank safety program: Technical basis for gas analysis and monitoring  

DOE Green Energy (OSTI)

Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms.

Estey, S.D.

1998-04-22T23:59:59.000Z

344

Office of Nuclear Safety | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety Office of Nuclear Safety Organization Office of Health and Safety Office of Environmental Protection, Sustainability Support & Corporate Safety Analysis Office of...

345

Safety analysis of the CSTR-1 bench-scale coal liquefaction unit  

SciTech Connect

The objective of the program reported herein was to provide a Safety Analysis of the CSTR-1 bench scale unit located in Building 167 at the Pittsburgh Energy Technology Center. It was apparent that considerable effort was expended in the design and construction of the unit, and in the development of operating procedures, with regard to safety. Exhaust ventilation, H/sub 2/ and H/sub 2/S monitoring, overpressure protection, overtemperature protection, and interlock systems have been provided. Present settings on the pressure and temperature safety systems are too high, however, to insure prevention of vessel deformation or damage in all cases. While the occurrence of catastrophic rupture of a system pressure vessel (e.g., reactor, high pressure separators) is unlikely, the potential consequences to personnel are severe. Feasibility of providing shielding for these components should be considered. A more probable mode of vessel failure in the event of overpressure or overtemperature and failure of the safety system is yielding of the closure bolts followed by high pressure flow across the mating surfaces. As a minimum, shielding should be designed to restrict travel of resultant spray. The requirements for personal protective equipment are presently stated in rather broad and general terms in the operating procedures. Safe practices and procedures would be more assured if specific requirements were stated and included for each operational step. Recommendations were developed for all hazards triggered by the guidelines.

Hulburt, D.A.

1981-05-01T23:59:59.000Z

346

Statistically based uncertainty analysis for ranking of component importance in the thermal-hydraulic safety analysis of the Advanced Neutron Source Reactor  

SciTech Connect

The Analytic Hierarchy Process (AHP) has been used to help determine the importance of components and phenomena in thermal-hydraulic safety analyses of nuclear reactors. The AHP results are based, in part on expert opinion. Therefore, it is prudent to evaluate the uncertainty of the AHP ranks of importance. Prior applications have addressed uncertainty with experimental data comparisons and bounding sensitivity calculations. These methods work well when a sufficient experimental data base exists to justify the comparisons. However, in the case of limited or no experimental data the size of the uncertainty is normally made conservatively large. Accordingly, the author has taken another approach, that of performing a statistically based uncertainty analysis. The new work is based on prior evaluations of the importance of components and phenomena in the thermal-hydraulic safety analysis of the Advanced Neutron Source Reactor (ANSR), a new facility now in the design phase. The uncertainty during large break loss of coolant, and decay heat removal scenarios is estimated by assigning a probability distribution function (pdf) to the potential error in the initial expert estimates of pair-wise importance between the components. Using a Monte Carlo sampling technique, the error pdfs are propagated through the AHP software solutions to determine a pdf of uncertainty in the system wide importance of each component. To enhance the generality of the results, study of one other problem having different number of elements is reported, as are the effects of a larger assumed pdf error in the expert ranks. Validation of the Monte Carlo sample size and repeatability are also documented.

Wilson, G.E.

1992-01-01T23:59:59.000Z

347

Materials Reliability Program: South Texas Project Unit 1 Bottom Mounted Instrumentation Nozzles (#1 and #46) Analysis Reports and R elated Documentation (MRP-102)  

Science Conference Proceedings (OSTI)

This technical update documents analysis of two nozzles at South Texas Project Unit 1 that were found to be leaking during a visual inspection of the bottom head of the reactor vessel. The first two sections of this report document research completed by BWXT Services Inc. for Framatome ANP on behalf of South Texas Project Nuclear Operating Company and the EPRI Materials Reliability Program Alloy 600 Issue Task Group. The first section is the analysis of bottom mounted instrument nozzle samples #1 and #46...

2003-12-19T23:59:59.000Z

348

Operating Experience Level 1, 2, and 3 Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Protection, Sustainability Support & Corporate Safety Analysis HS-20 Home Mission & Functions Office of Sustainability, Environment, Safety and Anaylsis (SESA) ...

349

Enron Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enron Documents 1994 U.S. DEPARTMENT OF ENERGY 13S. 12 CORRESPONDENCE CONTROL FORM 1) OFFICE OF THE EXECUTIVE SECRETARIAT 8CTIVITY ADD DO NOT DETACH FROM ORIGINAL CORRESPONDENCE 0/03/Y4 10: O0 5OURCECODE PM PUBLIC MAIL :?EC INT: CONTROL NO: ES94-012853 ,ATE CORR: 04/25/94 DATE RECD: 05/02/94 DATE CNTRL: 05/03/94 DATE DUE: NONE :TTER: X MEMO: TWX: _ OTHER: TO: SECY: X DEP SEC: _ UN SEC: OTHER: )M:LAY,KENNETH L \ TX O REMARKS: RELATES TO ES94-009882. i ENRON CORP. J: PUBLIC INFORMATION NATIONAL PETROLEUM COUNCIL ---- FOR USE BY ACTION OFFICE ONLY- ACCEPTS INV ITATION TO CONTINUE DUE ACTION REFERRED TO DATE RETURN TO TO SERVE AS A MEMBER OF THE DATE NATIONAL PETROLEUM COUNCIL I ___ 21 3 I .CTION TO: FE TYPE ACTION: Appropriate action SIG OF: _ CURRENCE: ORMATION: ES D04

350

AFFECTED DOCUMENT  

Office of Legacy Management (LM)

rr-osams rr-osams ADMIN RCD _ RESPONSE TRACKING INFORMATION I 'OWED BY: (ORG) I TARGET DATE { I CLOSING CCN COMPL. DATE { CLOSING REF I I lOWED BY: (ORG) { { I { { TARGET DATE I CLOSING CCN COMPL DATE CLOSING REF TECHNICAL SERVICES DIVISION (TSD) BACKFIT (Documents dated prior to 1 November 1988) FUSRAP COMMUNICATIONS DISTRIBUTION DOEIORO TECHNICAL SERVICES DIVISION (CE·53) BECHTEL NATIONAL, INC. -JOB 14501 _-....Iome....:.-R..%.JI&~S::....:::S.::...- TO_---.,!5~Z~IJ~u..~ COMM DATE &6 tlJ t.e ADDR CODE I I I I CLOSES CCN WBS _....:,;},=(J ........ 2._--- _ NUMBER ST SUBJECT CODE 70()O DOE FILE NO. _ SUBJECT NFs S RESIDIJAl.J OIJR;T 1tJ/UL t2U /DffG-./NE.5 ~..:ll..Jll~~l...3Io.,;~..:ll..Jll~~Io....JIo,.;~~~~Io....JIo,.;~~~~Io....JIo,.;:Io....1.~~~"""";:Io....1.~CCN _

351

Enron Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 6 ,. OFC OU.S. DEPARTMENT OF ENERGY OFFICE OF THE EXECUTIVE SECRETARIAT CORRESPONDENCE CONTROL TICKET IMPORTANT ES NUMBER:- ES96-000274 EXTERNAL kTE OF DOC: 12/28/95 REC'D: 01/04/96 CONTROLLED: 01/04/96 DUE: 01/26/96 FROM: I HAVE A DREAM NOTE REA: SUBJECT INFORMS SECRETARY THAT ENRON SUMMARY: GORP HAS MADE A CONTRIBUTION TO "I HAVE A DREAM - HOUSTON" IN THE SECRETARY HONOR SOURCE: PUBLIC MAIL DOCUMENT TYPE: LETTER ADDRESSED TO: SECRETARY FOR SIGNATURE OF: SECRETARY ACTION TO: OFFICE OF THE SECRETARY ACTION TYPE: Prepare final reply ACTION OFFICER: WALLACE ONCURRENCE COPIES TO: NFORMATION COPIES TO: ES1 TEAM NCURRENCES COMPLETED: EMARKS: :XECUTIVE SECRETARIAT CONTACT: G Holloway -------------------------- EXEC SEC INTERNAL USE ----------------- SUBJECT CROSS REF: SPECIAL INT. CODE:

352

OCR Document  

Office of Legacy Management (LM)

Desk Guide 6-2 GSA Lease Procurement Principal Steps Requirement Planning Prepare SFO Market Survey Solicitation Potential Offerors Proposals Analysis Negotiations BAFO Final...

353

Lawrence Livermore National Laborotory Safety Basis Assessment...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and implementation of safety basis documentation and execution of the unreviewed safety question (USQ) process. SCOPE The scope of this assessment includes the plans,...

354

Security, Emergency Planning & Safety Records | Department of...  

NLE Websites -- All DOE Office Websites (Extended Search)

Security, Emergency Planning & Safety Records Security, Emergency Planning & Safety Records ADM 180.pdf More Documents & Publications ADMINISTRATIVE RECORDS SCHEDULE 18: SECURITY,...

355

New challenges in the safety analysis of DOE`s high-level waste tanks  

Science Conference Proceedings (OSTI)

Tank 241-SY-101, located at the Department of Energy Hanford Site, has periodically released up to 283 m{sup 3} (10,000 ft{sup 3}) of flammable gas. This release has been one of the highest priority DOE operational safety problems because of potential consequences if the gas were ignited during one of these releases. The gases include hydrogen and ammonia (fuels) and nitrous oxide (oxidizer). There have been many opinions regarding the controlling mechanisms for these releases, but demonstrating an adequate understanding of the problem, selecting a mitigation methodology, and preparing the safety analysis have presented numerous new challenges. The purpose of this report is to present an overview of the problem, the main issues, the method selected to mitigate this hazard, and the results of the mitigation program.

Edwards, J.N.; Pasamehmetoglu, K.O.; White, J.R. [Los Alamos National Lab., NM (United States). Technology and Safety Assessment Div.

1994-09-01T23:59:59.000Z

356

2012 Annual Workforce Analysis and Staffing Plan Report - NNSA for Safety and Health  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1 1 Annual Workforce Analysis and Staffing Plan Report as of December 31, 2012 Reporting Office: NNSA NA-SH Section 1: Current Mission(s) of the Organization and Potential Changes The Office of the Associate Administrator for Safety and Health (NA-SH) provides mission enabling support to the NNSA Administrator, Central Technical Authority (CTA), Acquisition Executives, senior NNSA officials, program officers and site offices. NA-SH enables other NNSA organizations to fulfill NNSA missions while protecting the environment and safeguarding the safety and health of the public and the workforce. Section 2: SITE CHARACTERISTICS TABLE 1 Number of Hazard Category 1, 2, or 3 Nuclear Facilities: HC 1:_0_; HC 2: _0_; HC 3: _0_. Number of Radiological Facilities

357

Senior Technical Safety Manager Qualification Program Self-Assessment -  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Senior Technical Safety Manager Qualification Program Senior Technical Safety Manager Qualification Program Self-Assessment - Chief of Nuclear Safety Senior Technical Safety Manager Qualification Program Self-Assessment - Chief of Nuclear Safety A self-assessment of the CNS Senior Technical Safety Manager (STSM) Qualification Program was conducted during the week of July 8, 2013, when all STSM-qualified staff members were present in Germantown, Maryland. This was the first self-assessment that CNS has conducted. In accordance CNS Standard Operating Procedure SOP-016, Senior Technical Safety Manager Qualification Program, a self-assessment is required once every four years. Chief of Nuclear Safety STSM Self-Assessment, August 2013 More Documents & Publications 2010 Annual Workforce Analysis and Staffing Plan Report - Chief of Nuclear

358

Nuclear Facility Safety Basis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Basis Safety Basis FUNCTIONAL AREA GOAL: A fully compliant Nuclear Facility Safety Basis. Program is implemented and maintained across the site. REQUIREMENTS:  10 CFR 830 Subpart B Guidance:  DOE STD 3009  DOE STD 1104  DOE STD  DOE G 421.1-2 Implementation Guide For Use in Developing Documented Safety Analyses To Meet Subpart B Of 10 CFR 830  DOE G 423.1-1 Implementation Guide For Use In Developing Technical Safety Requirements  DOE G 424.1-1 Implementation Guide For Use In Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation The site contractor has developed an up-to-date, comprehensive, compliant, documented nuclear facility safety basis and associated implementing mechanisms and procedures for all required nuclear facilities and activities (10 CFR

359

Decision Level Data Fusion for Routing of Documents in the TREC3 Context: A Best Case Analysis of Worst Case Results.  

E-Print Network (OSTI)

Decision Level Data Fusion for Routing of Documents in the TREC3 Context: A Best Case Analysis of decision level data fusion in the routing (filtering) task of the Text Retrieval Conference is summarized and analyzed. The relatively poor results of an approach in which a specific fusion rule was selected for each

360

Development of Guidance for Analysis of Beyond Design Basis Events |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development of Guidance for Analysis of Beyond Design Basis Events Development of Guidance for Analysis of Beyond Design Basis Events Development of Guidance for Analysis of Beyond Design Basis Events Wednesday, September 19 Presenter: Dr. James O'Brien, Director, Office of Nuclear Safety, Office of Health, Safety and Security, US Department of Energy Topics covered: Types of DOE Facilities ◦ Research Reactors; ◦ Weapons disassembly, maintenance, and testing facilities; ◦ Nuclear material storage facilities; ◦ Processing facilities; and waste disposal facilities. Safety Analysis Framework ◦ DOE Nuclear Safety Policy ◦ Nuclear Safety Rule ◦ Nuclear Safety Analysis Standards ◦ Documented Safety Analysis Guide Development of Guidance for Analysis of Beyond Design Basis Events More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP  

SciTech Connect

With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified i

Kessler, S

2009-04-21T23:59:59.000Z

362

CRAD, Facility Safety - Nuclear Facility Safety Basis | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Nuclear Facility Safety Basis More Documents & Publications CRAD, Facility Safety - Unreviewed Safety Question Requirements Site Visit Report, Livermore Site Office - February 2011 FAQS Job Task Analyses - Nuclear Safety Specialist

363

Scanned Document  

Office of Legacy Management (LM)

EPA-402-R-04-006 EPA-402-R-04-006 Environmental Protection Indoor Air November 2004 Agency Washington, DC 20460 Annual Water Sampling and Analysis, Calendar Year 2004: SHOAL Test Site Area FAULTLESS Test Site Area RULISON Test Site Area RIO BLANCO Test Site Area GASBUGGY Test Site Area GNOME Test Site Area Annual Water Sampling and Analysis, Calendar Year 2004 SHOAL Test Site Area FAULTLESS Test Site Area RULISON Test Site Area RIO BLANCO Test Site Area GASBUGGY Test Site Area GNOME Test Site Area Max G. Davis Rose (Kitty) Houston Prepared for the U.S. Department of Energy under Interagency Agreement DE-AI08-96NV 1 1969 RADIATION AND INDOOR ENVIRONMENTS NATIONAL LABORATORY OFFICE OF RADIATION AND INDOOR AIR U.S. ENVIRONMENTAL PROTECTION AGENCY P.O. BOX 98517

364

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

June 13, 2008 June 13, 2008 Preliminary Notice of Violation, Babcock & Wilcox Teclmical Services Y-12, LLC - NEA-2008-01 Preliminary Notice of Violation issued to Babcock & Wilcox Technical Services Y-12, LLC, related to a Uranium Chip Fire at the Y-12 National Security Complex March 17, 2008 Enforcement Letter , Bechtel BWXT Idaho LLC - March 17, 2008 Enforcement Letter issued to Bechtel BWXT Idaho, LLC, related to Procedural Adequacy and Adherence in Transuranic Waste Characterization and Shipping at the Idaho National Laboratory January 4, 2008 Special Report Order, Los Alamos National Security, LLC - January 4, 2008 Issued to Los Alamos National Security, LLC related to Glovebox Activities at TA-55 and Chemistry and Metallurgy Research Facilities at the Los Alamos

365

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

November 16, 1998 November 16, 1998 Preliminary Notice of Violation, Babcock & Wilcox of Ohio, Inc - EA-98-12 Preliminary Notice of Violation issued to Babcock & Wilcox of Ohio, Inc., related to Radiological Work Controls and Bioassay Program Deficiencies at the Mound Site, November 16, 1998 (EA-98-12) September 21, 1998 Preliminary Notice of Violation, Los Alamos National Laboratory - EA-98-10 Preliminary Notice of Violation issued to the University of California related to Multiple Events involving Radiation Protection and Quality Control Requirements at the Chemistry and Metallurgy Research Facility at the Los Alamos National Laboratory, (EA-98-10) September 21, 1998 Preliminary Notice of Violation, MK-Ferguson of Oak Ridge Company - EA-98-08 Preliminary Notice of Violation issued to MK-Ferguson of Oak Ridge Company,

366

Documenting Targeted Behaviors Associated with Pedestrian Safety  

E-Print Network (OSTI)

light. Was in street when light turns red. Stopped andthey began crossing the street before the light for parallelLight FIGURE 6. Percent of Pedestrians Using a Mobile Device while Crossing the Street

Cooper, Jill F.; Schneider, Robert J.; Ryan, Sherry; Co, Sean

2013-01-01T23:59:59.000Z

367

Breach and safety analysis of spills over water from large liquefied natural gas carriers.  

SciTech Connect

In 2004, at the request of the Department of Energy, Sandia National Laboratories (Sandia) prepared a report, ''Guidance on the Risk and Safety Analysis of Large Liquefied Natural Gas (LNG) Spills Over Water''. That report provided framework for assessing hazards and identifying approaches to minimize the consequences to people and property from an LNG spill over water. The report also presented the general scale of possible hazards from a spill from 125,000 m3 o 150,000 m3 class LNG carriers, at the time the most common LNG carrier capacity.

Hightower, Marion Michael; Luketa-Hanlin, Anay Josephine; Attaway, Stephen W.

2008-05-01T23:59:59.000Z

368

Technical Safety Requirements  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Requirements Safety Requirements FUNCTIONAL AREA GOAL: Contractor has developed, maintained, and received DOE Field Office Approval for the necessary operating conditions of a facility. The facility has also maintained an inventory of safety class and safety significant systems and components. REQUIREMENTS:  10 CFR 830.205, Nuclear Safety Rule.  DOE-STD-3009-2002, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses.  DOE-STD-1186-2004, Specific Administrative Controls. Guidance:  DOE G 423.1-1, Implementation Guide for Use in Developing Technical Safety Requirements.  NSTP 2003-1, Use of Administrative Controls for Specific Safety Functions. Performance Objective 1: Contractor Program Documentation

369

Appendix G Supporting Documentation  

Office of Legacy Management (LM)

Supporting Documentation Supporting Documentation for Focused Feasibility Study This page intentionally left blank Contents Section Ground Water Models for Alternatives 3 and 4 ........................................................................ G .O Human Health Risk Assessment Calculations ........................................................................... G2.0 Cost Analysis ........................................................................................................................... G3.0 This page intentionally left blank Section G1.0 Ground Water Models for Alternatives 3 and 4 This page intentionally left blank D o c o l ~ ~ e n t Nurt~her Q0029500 Appendix G MMTS OU 111 Feasibility Study Ground Water Modeling for Alternative 3: PRB Treatment Objective

370

Technical Review Report for the Safety Analysis Report for Packaging Model 9977 S-SARP-G-00001 Revision 2  

SciTech Connect

This Technical Review Report (TRR) summarizes the review findings for the Safety Analysis Report for Packaging (SARP) for the Model 9977 B(M)F-96 shipping container. The content analyzed for this submittal is Content Envelope C.1, Heat Sources, in assemblies of Radioisotope Thermoelectric Generators or food-pack cans. The SARP under review, i.e., S-SARP-G-00001, Revision 2 (August 2007), was originally referred to as the General Purpose Fissile Material Package. The review presented in this TRR was performed using the methods outlined in Revision 3 of the Department of Energy's (DOE's) Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's, Regulatory Guide 7.9, i.e., Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9977 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. The Model 9977 Package design includes a single, 6-inch diameter, stainless steel pressure vessel containment system (i.e., the 6CV) that was designed and fabricated in accordance with Section III, Subsection NB, of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code. The earlier package designs, i.e., the Model 9965, 9966, 9967 and 9968 Packages, were originally designed and certified in the 1980s. In the 1990s, updated package designs that incorporated design features consistent with new safety requirements, based on International Atomic Energy Agency guidelines, were proposed. The updated package designs were the Model 9972, 9973, 9974 and 9975 Packages, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. Differences between the Model 9975 Package and the Model 9977 Package include: (1) The lead shield present in the Model 9975 Package is absent in the Model 9977 Package; (2) The Model 9975 Package has eight allowable contents, while the Model 9977 Package has a single allowable content. (3) The 6CV of the Model 9977 Package is similar in design to the outer Containment Vessel of the Model 9975 Package that also incorporates a 5-inch Containment Vessel as the inner Containment Vessel. (4) The Model 9975 Package uses a Celotex{reg_sign}-based impact limiter while the Model 9977 Package uses Last-A-Foam{reg_sign}, a polyurethane foam, for the impact limiter. (5) The Model 9975 Package has two Containment Vessels, while the Model 9977 Package has a single Containment Vessel.

DiSabatino, A; Hafner, R; West, M

2007-10-04T23:59:59.000Z

371

Cold Vacuum Drying Facility hazard analysis report  

SciTech Connect

This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports.

Krahn, D.E.

1998-02-23T23:59:59.000Z

372

Enron Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8 8 :. Thursday, March 14, 2002 3:10 PM Profile Page: 1 Folder Profile Control # 1998000752 Name letter to the Deputy Secretary from the Northeast States for Priority Important Folder Trigger Letter DOE Addressee Source PM-0 Elizabeth Moler I ___I |_______________ Correspondence Date 1/16/98 Subject Text e RE:AIR POLLUTION IMPACTS OF RIDS Information ead of Agency INCREASED DEREGULATION IN THE J ELECTRIC POWER INDUSTRY: AN INITIAL Sensitivity Not Applicable ANALYSIS - 1115/98 l Classification None Topical Index Point of Contact LOHRM -- i-na--u--e--Ap --- o--al 202 586-0471 Lohr, Michael Signature/Approval l _______________________________ _ . A ction O ffice # I l Action Requested Assigned To Appropriate Action _ PO Special Instructions Date Due I I Date Completed 1121/98

373

SC Categorical Exclusions and NEPA Documents | U.S. DOE Office...  

Office of Science (SC) Website

Safety & Health Organization Chart .pdf file (82KB) Phone Listing .pdf file (129KB) SC Categorical Exclusions and NEPA Documents SLI & SS Budget Contact Information Safety,...

374

Understanding waste phenomenology to reduce the amount of sampling and analysis required to resolve Hanford waste tank safety issues  

SciTech Connect

Safety issues associated with Hanford Site waste tanks arose because of inadequate safety analyses and high levels of uncertainty over the release of radioactivity resulting from condensed phase exothermic chemical reactions (organic solvent fires, organic complexant-nitrate reactions, and ferrocyanide-nitrate reactions). The approach to resolving the Organic Complexant, Organic Solvent, and Ferrocyanide safety issues has changed considerably since 1990. The approach formerly utilized core sampling and extensive analysis of the samples with the expectation the data would provide insight into the hazard. This resulted in high costs and the generation of a large amount of data that was of limited value in resolving the safety issues. The new approach relies on an understanding of the hazard phenomenology to focus sampling and analysis on those analytes that are key to ensuring safe storage of the waste.

Meacham, J.E.; Babad, H.

1996-02-01T23:59:59.000Z

375

Probabilistic cost-benefit analysis of enhanced safety features for strategic nuclear weapons at a representative location  

Science Conference Proceedings (OSTI)

We carried out a demonstration analysis of the value of developing and implementing enhanced safety features for nuclear weapons in the US stockpile. We modified an approach that the Nuclear Regulatory Commission (NRC) developed in response to a congressional directive that NRC assess the ``value-impact`` of regulatory actions for commercial nuclear power plants. Because improving weapon safety shares some basic objectives with NRC regulations, i.e., protecting public health and safety from the effects of accidents involving radioactive materials, we believe the NRC approach to be appropriate for evaluating weapons-safety cost-benefit issues. Impact analysis includes not only direct costs associated with retrofitting the weapon system, but also the expected costs (or economic risks) that are avoided by the action, i.e., the benefits.

Stephens, D.R.; Hall, C.H.; Holman, G.S.; Graham, K.F.; Harvey, T.F.; Serduke, F.J.D.

1993-10-01T23:59:59.000Z

376

Analysis and comparison of five contractor safety and health manuals (EG and G, SR II, ORNL, Ashland, and MLGW)  

DOE Green Energy (OSTI)

An analysis is presented of five safety and health contractor manuals against the requirements of the FE OSH Manual (FE 5480.1), and a breakdown in chart form of how the manuals compare to each other is given. It is pointed out that the manuals are inadequate, but that site visits will be necessary to determine the actual comprehensiveness of the facilities' safety and health programs.

Crowder, C.; Hurley, T.

1981-03-01T23:59:59.000Z

377

High-level waste tank farm set point document  

Science Conference Proceedings (OSTI)

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

Anthony, J.A. III

1995-01-15T23:59:59.000Z

378

Documents: Final PEIS  

NLE Websites -- All DOE Office Websites (Extended Search)

Final PEIS Search Documents: Search PDF Documents View a list of all documents Final Programmatic EIS DOEEIS-0269 Final Programmatic Environmental Impact Statement for...

379

Documents: NEPA Support  

NLE Websites -- All DOE Office Websites (Extended Search)

Search Documents: Search PDF Documents View a list of all documents NEPA Support PDF Icon Depleted Uranium Hexafluoride Management Program: Data Compilation for the Paducah Site...

380

ARM - XDC Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Documentation External Data Center Order Data Description of External Data Streams Data Viewers and Plots (selected data sets) XDC Documentation XDC Documentation BNL's ARM Related...

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

ZeptoOS // Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Documentation Visit the ZeptoOS Documentation Wiki for a complete ZeptoOS documentation, including a list of features, requirements, limitations, and changes from previous...

382

Facilities Services and Environmental Health and Safety  

E-Print Network (OSTI)

Facilities Services and Environmental Health and Safety Laboratory Ventilation Management Program Guidance Document Facilities Services and Environmental Health and Safety This group is comprised of support staff from Facilities Services and Environmental Health and Safety who make observations

Pawlowski, Wojtek

383

Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Culture in the US Nuclear Regulatory Commission's Reactor Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process September 19, 2012 Presenter: Undine Shoop, Chief, Health Physics and Human Performance Branch, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission Topics covered: Purpose of the Reactor Oversight Process (ROP) ROP Framework Safety Culture within the ROP Safety Culture Assessments Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process More Documents & Publications A Commissioner's Perspective on USNRC Actions in Response to the Fukushima Nuclear Accident Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11

384

Perry Safety Book for Web  

NLE Websites -- All DOE Office Websites (Extended Search)

1 Before using this product, read, understand and follow the Assembly and Safe Use Instruc- tions. Save this document for future reference. It contains important safety...

385

Facility Disposition Safety Strategy RM  

Energy.gov (U.S. Department of Energy (DOE))

The Facility Disposition Safety Strategy (FDSS) Review Module is a tool that assists DOE federal project review teams in evaluating the adequacy of the facility documentation, preparations or...

386

SAFETY EVALUATION OF OXALIC ACID WASTE RETRIEVAL IN SINGLE SHELL TANK (SST) 241-C-106  

Science Conference Proceedings (OSTI)

This report documents the safety evaluation of the process of retrieving sludge waste from single-shell tank 241-C-106 using oxalic acid. The results of the HAZOP, safety evaluation, and control allocation/decision are part of the report. This safety evaluation considers the use of oxalic acid to recover residual waste in single-shell tank (SST) 241-C-106. This is an activity not addressed in the current tank farm safety basis. This evaluation has five specific purposes: (1) Identifying the key configuration and operating assumptions needed to evaluate oxalic acid dissolution in SST 241-C-106. (2) Documenting the hazardous conditions identified during the oxalic acid dissolution hazard and operability study (HAZOP). (3) Documenting the comparison of the HAZOP results to the hazardous conditions and associated analyzed accident currently included in the safety basis, as documented in HNF-SD-WM-TI-764, ''Hazard Analysis Database Report''. (4) Documenting the evaluation of the oxalic acid dissolution activity with respect to Accident analyses described in HNF-SD-WM-SAR-067, ''Tank Farms Final Safety Analysis Report'' (FSAR). (5)Controls specified in HNF-SD-WM-TSR-006, ''Tank Farms Technical Safety Requirements'' (TSR). Documenting the process and results of control decisions as well as the applicability of preventive and/or mitigative controls to each oxalic acid addition hazardous condition.

GOETZ, T.G.

2003-07-21T23:59:59.000Z

387

Exploration of High-Dimensional Scalar Function for Nuclear Reactor Safety Analysis and Visualization  

SciTech Connect

The next generation of methodologies for nuclear reactor Probabilistic Risk Assessment (PRA) explicitly accounts for the time element in modeling the probabilistic system evolution and uses numerical simulation tools to account for possible dependencies between failure events. The Monte-Carlo (MC) and the Dynamic Event Tree (DET) approaches belong to this new class of dynamic PRA methodologies. A challenge of dynamic PRA algorithms is the large amount of data they produce which may be difficult to visualize and analyze in order to extract useful information. We present a software tool that is designed to address these goals. We model a large-scale nuclear simulation dataset as a high-dimensional scalar function defined over a discrete sample of the domain. First, we provide structural analysis of such a function at multiple scales and provide insight into the relationship between the input parameters and the output. Second, we enable exploratory analysis for users, where we help the users to differentiate features from noise through multi-scale analysis on an interactive platform, based on domain knowledge and data characterization. Our analysis is performed by exploiting the topological and geometric properties of the domain, building statistical models based on its topological segmentations and providing interactive visual interfaces to facilitate such explorations. We provide a users guide to our software tool by highlighting its analysis and visualization capabilities, along with a use case involving dataset from a nuclear reactor safety simulation.

Dan Maljovec; Bei Wang; Valerio Pascucci; Peer-Timo Bremer; Michael Pernice; Robert Nourgaliev

2013-05-01T23:59:59.000Z

388

Seabrook Station probabilistic safety assessment. Main report, volumes 1-6 and summary report  

SciTech Connect

This report documents an independent probabilistic safety assessment of the twin nuclear power plants under construction near Seabrook, New Hampshire. This assessment quantified the risk to public health and safety associated with potential accidents during the period of operation of the station. The main report contains the technical analyses of the Seabrook plant and site, the risk modeling and data analysis.

Not Available

1983-12-01T23:59:59.000Z

389

Yucca Mountain Project Document Suspension, OAS-M-08-07 | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Yucca Mountain Project Document Suspension, OAS-M-08-07 Yucca Mountain Project Document Suspension, OAS-M-08-07 Yucca Mountain Project Document Suspension, OAS-M-08-07 The Department or Energy's Office of Civilian Radioaztivc Waste Management (OCRWM) is preparing to obtain a license from the Nuclear Regulatory Commission to construct a permanent repository at Yucca Mountain for the disposal of high-level radioactive waste and spent nuclear fuel. In December 2005, OCRWM identified design process inadequacies and suspended the appro\lal of new7 documents 'important to waste isolation' or safety analysis that were subject to quality assurance procedures. Waste isolation refers to limiting radioactive exposure to the public after the waste is placed in the repository; while safety refers to limiting exposure prior to

390

Yucca Mountain Project Document Suspension, OAS-M-08-07 | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Yucca Mountain Project Document Suspension, OAS-M-08-07 Yucca Mountain Project Document Suspension, OAS-M-08-07 Yucca Mountain Project Document Suspension, OAS-M-08-07 The Department or Energy's Office of Civilian Radioaztivc Waste Management (OCRWM) is preparing to obtain a license from the Nuclear Regulatory Commission to construct a permanent repository at Yucca Mountain for the disposal of high-level radioactive waste and spent nuclear fuel. In December 2005, OCRWM identified design process inadequacies and suspended the appro\lal of new7 documents 'important to waste isolation' or safety analysis that were subject to quality assurance procedures. Waste isolation refers to limiting radioactive exposure to the public after the waste is placed in the repository; while safety refers to limiting exposure prior to

391

Technical Review Report for the Model 9978-96 Package Safety Analysis Report for Packaging (S-SARP-G-00002, Revision 1, March 2009)  

Science Conference Proceedings (OSTI)

This Technical Review Report (TRR) documents the review, performed by Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the Department of Energy (DOE), on the 'Safety Analysis Report for Packaging (SARP), Model 9978 B(M)F-96', Revision 1, March 2009 (S-SARP-G-00002). The Model 9978 Package complies with 10 CFR 71, and with 'Regulations for the Safe Transport of Radioactive Material-1996 Edition (As Amended, 2000)-Safety Requirements', International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9978 Packaging is designed, analyzed, fabricated, and tested in accordance with Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME B&PVC). The review presented in this TRR was performed using the methods outlined in Revision 3 of the DOE's 'Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages'. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's Regulatory Guide 7.9, i.e., 'Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material'. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9978 Packaging is a single containment package, using a 5-inch containment vessel (5CV). It uses a nominal 35-gallon drum package design. In comparison, the Model 9977 Packaging uses a 6-inch containment vessel (6CV). The Model 9977 and Model 9978 Packagings were developed concurrently, and they were referred to as the General Purpose Fissile Material Package, Version 1 (GPFP). Both packagings use General Plastics FR-3716 polyurethane foam as insulation and as impact limiters. The 5CV is used as the Primary Containment Vessel (PCV) in the Model 9975-96 Packaging. The Model 9975-96 Packaging also has the 6CV as its Secondary Containment Vessel (SCV). In comparison, the Model 9975 Packagings use Celotex{trademark} for insulation and as impact limiters. To provide a historical perspective, it is noted that the Model 9975-96 Packaging is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then-newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The Model 9978 Package has six Content Envelopes: C.1 ({sup 238}Pu Heat Sources), C.2 ( Pu/U Metals), C.3 (Pu/U Oxides, Reserved), C.4 (U Metal or Alloy), C.5 (U Compounds), and C.6 (Samples and Sources). Per 10 CFR 71.59 (Code of Federal Regulations), the value of N is 50 for the Model 9978 Package leading to a Criticality Safety Index (CSI) of 1.0. The Transport Index (TI), based on dose rate, is calculated to be a maximum of 4.1.

West, M

2009-03-06T23:59:59.000Z

392

Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory. Volume 2, Appendices  

DOE Green Energy (OSTI)

To ensure the continued safety of SERI`s employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMS). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance. This document contains the appendices to the NREL safety analysis report.

Crandall, R.S.; Nelson, B.P.; Moskowitz, P.D.; Fthenakis, V.M.

1992-07-01T23:59:59.000Z

393

Plutonium Finishing Plant safety evaluation report  

SciTech Connect

The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

Not Available

1995-01-01T23:59:59.000Z

394

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual  

Science Conference Proceedings (OSTI)

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Dr. Bradley J Schrader

2009-03-01T23:59:59.000Z

395

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users Manual  

SciTech Connect

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Dr. Bradley J Schrader

2010-10-01T23:59:59.000Z

396

CLASSIFICATION OF THE MGR HEALTH SAFETY SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) health safety system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

J.A. Ziegler

1999-08-31T23:59:59.000Z

397

Environment/Health/Safety (EHS): Laser Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Laser Safety Home Whom to Call Analysis of Laser Safety Occurrences: 2005-2011 Laser Bio-effects Laser Classification Laser Disposal Guide Laser Forms Laser Newsletter Laser Lab...

398

Document Control Process  

NLE Websites -- All DOE Office Websites (Extended Search)

1 Document Control Process 11_0304 Page 1 of 7 1 Document Control Process 11_0304 Page 1 of 7 EOTA - Business Process Document Title: Document Control Process Document Number: P-001 Rev 11_0304 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: Q-001, Quality Manual Notify of Changes: EOTA Employees Referenced Document(s): F-001 Document Control Template - Process, F-002 Document Control Template - Instruction, F-003 Document Control Template - Screenshot, F-004 Document Control Template - Form, F-005 Document Control Template - Form - Excel, MGTP-002 Skill Set Model, Q-003 EOTA Processes: Sequence and Interaction, P-003, Control of Records P-001 Document Control Process 11_0304 Page 2 of 7 Revision History: Rev. Description of Change

399

Safety Basis Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Analysis (SESA) SESA Home Mission & Functions Office of Sustainability, Environment, Safety and Anaylsis (SESA) Sustainability Support Environmental Policy & Assistance ...

400

Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility  

SciTech Connect

The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable.

Johnson, D.J.; Brehm, J.R.

1994-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

FAQS Job Task Analyses - DOE AVIATION SAFETY OFFICER (ASO)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SAFETY OFFICER (ASO) - JOB TASK ANALYSIS SAFETY OFFICER (ASO) - JOB TASK ANALYSIS Job Analysis Worksheet for Task DOE AVIATION SAFETY OFFICER Task Source Importance Frequency A Gathers, trends, and analyzes aviation safety performance data to ensure the safety of the field aviation program. DOE O 440.2C, chng 1 4 3 B Conducts periodic assessments of aviation activities to ensure that requirements, policies, and procedures are implemented and followed and prepares reports documenting assessment findings, concerns, and recommendations and tracks corrective actions to help prevent similar occurrences. DOE O 440.2C, chng 1 4 3 C Participates as directed in aviation accident or incident investigations and provides assistance to accident investigation boards during their investigations.

402

Letter from Nuclear Energy Institute regarding Integrated Safety Analysis: Why it is Appropropriate for Fuel Recycling Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

082 l F: 202.533.0166 l rxm@nei.org l www.nei.org 082 l F: 202.533.0166 l rxm@nei.org l www.nei.org Rod McCullum DIRECTOR FUEL CYCLE PROJECTS NUCLEAR GENERATION DIVISION September 10, 2010 Ms. Catherine Haney Director Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689 Dear Ms. Haney: Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is intended as an information source for the NRC and should serve as a foundation for discussion with industry representatives on the issue.

403

Guidance on risk analysis and safety implications of a large liquefied natural gas (LNG) spill over water.  

Science Conference Proceedings (OSTI)

While recognized standards exist for the systematic safety analysis of potential spills or releases from LNG (Liquefied Natural Gas) storage terminals and facilities on land, no equivalent set of standards or guidance exists for the evaluation of the safety or consequences from LNG spills over water. Heightened security awareness and energy surety issues have increased industry's and the public's attention to these activities. The report reviews several existing studies of LNG spills with respect to their assumptions, inputs, models, and experimental data. Based on this review and further analysis, the report provides guidance on the appropriateness of models, assumptions, and risk management to address public safety and property relative to a potential LNG spill over water.

Wellman, Gerald William; Melof, Brian Matthew; Luketa-Hanlin, Anay Josephine; Hightower, Marion Michael; Covan, John Morgan; Gritzo, Louis Alan; Irwin, Michael James; Kaneshige, Michael Jiro; Morrow, Charles W.

2004-12-01T23:59:59.000Z

404

Challenges and methodology for safety analysis of a high-level waste tank with large periodic releases of flammable gas  

SciTech Connect

Tank 241-SY-101, located at the Department of Energy Hanford Site, has periodically released up to 10,000 ft{sup 3} of flammable gas. This release has been one of the highest-priority DOE operational safety problems. The gases include hydrogen and ammonia (fuels) and nitrous oxide (oxidizer). There have been many opinions regarding the controlling mechanisms for these releases, but demonstrating an adequate understanding of the problem, selecting a mitigation methodology, and preparing the safety analysis have presented numerous new challenges. The mitigation method selected for the tank was to install a pump that would mix the tank contents and eliminate the sludge layer believed to be responsible for the gas retention and periodic releases. This report will describe the principal analysis methodologies used to prepare the safety assessment for the installation and operation of the pump, and because this activity has been completed, it will describe the results of pump operation.

Edwards, J.N.; Pasamehmetoglu, K.O.; White, J.R. [Los Alamos National Lab., NM (United States); Stewart, C.W. [Pacific Northwest Lab., Richland, WA (United States)

1994-07-01T23:59:59.000Z

405

Decommissioning Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Documents Decommissioning Documents Decommissioning Documents More Documents & Publications CX-002246: Categorical Exclusion Determination Decommissioning Handbook CX-003134:...

406

Decommissioning Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Documents Decommissioning Documents Decommissioning Documents More Documents & Publications CX-002246: Categorical Exclusion Determination Decommissioning Handbook CX-000018:...

407

CRITICALITY SAFETY (CS)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Objective CS.1 - A criticality safety program is established, sufficient numbers of qualified personnel are provided, and adequate facilities and equipment are available to ensure criticality safety support services are adequate for safe operations. (Core Requirements 1, 2, and 6) Criteria * Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented. * Operations support personnel for the criticality safety area are adequately staffed and trained. Approach Record Review: Review the documentation that establishes the Criticality Safety Requirements (CSRs) for appropriateness and completeness. Review for adequacy and completion the criticality safety personnel training records that indicate training on facility procedures and systems under

408

Safety problems of water-development works designed for land reclamation  

SciTech Connect

A safety declaration is a fundamental document assuring the safety of water-development works, their correspondence to safety criteria, the design, and active technical regulations and rules.

Shchedrin, V. N. [Russian Academy of Agriculture Sciences (Russian Federation); Kosichenko, Yu. M. [FGNU RocNIIPM, Novocherkassk (Russian Federation)

2011-11-15T23:59:59.000Z

409

Safety Basis Report  

SciTech Connect

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

R.J. Garrett

2002-01-14T23:59:59.000Z

410

Methodology assessment and recommendations for the Mars science laboratory launch safety analysis.  

DOE Green Energy (OSTI)

The Department of Energy has assigned to Sandia National Laboratories the responsibility of producing a Safety Analysis Report (SAR) for the plutonium-dioxide fueled Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) proposed to be used in the Mars Science Laboratory (MSL) mission. The National Aeronautic and Space Administration (NASA) is anticipating a launch in fall of 2009, and the SAR will play a critical role in the launch approval process. As in past safety evaluations of MMRTG missions, a wide range of potential accident conditions differing widely in probability and seventy must be considered, and the resulting risk to the public will be presented in the form of probability distribution functions of health effects in terms of latent cancer fatalities. The basic descriptions of accident cases will be provided by NASA in the MSL SAR Databook for the mission, and on the basis of these descriptions, Sandia will apply a variety of sophisticated computational simulation tools to evaluate the potential release of plutonium dioxide, its transport to human populations, and the consequent health effects. The first step in carrying out this project is to evaluate the existing computational analysis tools (computer codes) for suitability to the analysis and, when appropriate, to identify areas where modifications or improvements are warranted. The overall calculation of health risks can be divided into three levels of analysis. Level A involves detailed simulations of the interactions of the MMRTG or its components with the broad range of insults (e.g., shrapnel, blast waves, fires) posed by the various accident environments. There are a number of candidate codes for this level; they are typically high resolution computational simulation tools that capture details of each type of interaction and that can predict damage and plutonium dioxide release for a range of choices of controlling parameters. Level B utilizes these detailed results to study many thousands of possible event sequences and to build up a statistical representation of the releases for each accident case. A code to carry out this process will have to be developed or adapted from previous MMRTG missions. Finally, Level C translates the release (or ''source term'') information from Level B into public risk by applying models for atmospheric transport and the health consequences of exposure to the released plutonium dioxide. A number of candidate codes for this level of analysis are available. This report surveys the range of available codes and tools for each of these levels and makes recommendations for which choices are best for the MSL mission. It also identities areas where improvements to the codes are needed. In some cases a second tier of codes may be identified to provide supporting or clarifying insight about particular issues. The main focus of the methodology assessment is to identify a suite of computational tools that can produce a high quality SAR that can be successfully reviewed by external bodies (such as the Interagency Nuclear Safety Review Panel) on the schedule established by NASA and DOE.

Sturgis, Beverly Rainwater; Metzinger, Kurt Evan; Powers, Dana Auburn; Atcitty, Christopher B.; Robinson, David B; Hewson, John C.; Bixler, Nathan E.; Dodson, Brian W.; Potter, Donald L.; Kelly, John E.; MacLean, Heather J.; Bergeron, Kenneth Donald (Sala & Associates); Bessette, Gregory Carl; Lipinski, Ronald J.

2006-09-01T23:59:59.000Z

411

Nuclear Criticality Safety - Nuclear Engineering Division (Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

Criticality Safety Nuclear Criticality Safety Overview Experience Analysis Tools Current NCS Activities Current R&D Activities DOE Criticality Safety Support Group (CSSG) Other...

412

An overview of severe accident modeling and analysis work for the ANS reactor conceptual safety analysis report  

Science Conference Proceedings (OSTI)

ORNL`s Advanced Neutron Source (ANS) will be a new user facility for all kinds of neutron research, centered around a research reactor of unprecedented neutron beam flux. A defense-in-depth philosophy has been adopted. In response to this commitment, ANS Project management has initiated severe accident analysis and related technology development efforts early-on in the design phase itself. Early consideration of severe accident issues will aid in designing a sufficiently robust containment for retention and controlled release of radionuclides in the event of such an accident. It will also provide a means for satisfying on- and off-site regulatory requirements and provide containment response and source term analyses for level-2 and -3 Probabilistic Risk Analyses (PRAs) that will be produced. Moreover, it will provide the best possible understanding of the ANS under severe accident conditions, and consequently provide insights for the development of strategies and design philosophies for accident management, mitigation, and emergency preparedness. This paper presents a perspective overview of the severe accident modeling and analysis work for the ANS Conceptual Safety Analysis Report (CSAR)

Taleyarkhan, R.P.

1992-12-31T23:59:59.000Z

413

Safety for Users  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety for Users Safety for Users Safety for Users Print Safety at the ALS The mission of the ALS is "Support users in doing outstanding science in a safe environment." All users and staff participate in creating a culture and environment where performing research using the proper safeguards and fulfilling all safety requirements result in the success of the facility and its scientific program. The documents and guidance below will assist users and staff to achieve these goals. How Do I...? A series of fact sheets that explain what users need to know and do when preparing to conduct experiments at the ALS. Complete Experiment Safety Documentation? Work with Biological Materials? Work with Chemicals? Work with Regulated Soil? Bring and Use Electrical Equipment at the ALS?

414

The Office of Health, Safety and Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainability, Environment, Safety and Anaylsis (SESA) Sustainability Support Environmental Policy & Assistance Corporate Safety Programs Analysis Program Contacts...

415

Control of External Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

2 Control of External Documents Process 11_0304 Page 1 of 5 2 Control of External Documents Process 11_0304 Page 1 of 5 EOTA - Business Process Document Title: Control of External Documents Process Document Number P-002 Rev 11_0304 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: Q-001, Quality Manual Notify of Changes: EOTA Employees Referenced Document(s): REG-002, External Document Register P-002 Control of External Documents Process 11_0304 Page 2 of 5 Revision History: Rev. Description of Change A Initial Release 11_0304 Changed revision format from alpha character to numbers; modified process to include a step directing addition to REG-002 External Document Register and changed verbiage to clarify and more accurately reflect current process.

416

Criticality Safety Controls Implementation, May 31, 2013 (HSS...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy Office of Safety and Emergency Management Evaluations Criteria and Review Approach Document 1.0 PURPOSE Subj ect: Criticality Safety Controls lmplementation - Criteria and...

417

2012 Annual Planning Summary for Health, Safety and Security...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Impact Statements for 2012 and 2013 within Health, Safety and Security. APS-2012-HSS.pdf More Documents & Publications 2011 Annual Planning Summary for Health, Safety and...

418

Review of the Portsmouth Gaseous Diffusion Plant Integrated Safety...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criteria, Review and Approach Document DNFSB Defense Nuclear Facilities Safety Board DOE U.S. Department of Energy ESH&Q Environment, Safety, Health, and Quality FBP...

419

Criticality Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Left Tab EVENTS Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical...

420

Pantex Plant final safety analysis report, Zone 4 magazines. Staging or interim storage for nuclear weapons and components: Issue D  

SciTech Connect

This Safety Analysis Report (SAR) contains a detailed description and evaluation of the significant environmental, safety, and health (ES&H) issues associated with the operations of the Pantex Plant modified-Richmond and steel arch construction (SAC) magazines in Zone 4. It provides (1) an overall description of the magazines, the Pantex Plant, and its surroundings; (2) a systematic evaluations of the hazards that could occur as a result of the operations performed in these magazines; (3) descriptions and analyses of the adequacy of the measures taken to eliminate, control, or mitigate the identified hazards; and (4) analyses of potential accidents and their associated risks.

Not Available

1993-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Edison Systems Technology Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Technology Documentation Systems Technology Documentation Downloads CrayXC30Networking.pdf | Adobe Acrobat PDF file Cray XC30 Networking SonexionBrochure.pdf | Adobe Acrobat PDF...

422

SAFETY EVALUATION OF OXALIC ACID WASTE RETRIEVAL IN SINGLE SHELL TANK (SST) 241-C-106  

Science Conference Proceedings (OSTI)

This report documents the safety evaluation of the process of retrieving sludge waste from single-shell tank 241-C-106 using oxalic acid. The results of the HAZOP, safety evaluation, and control allocation/decision are part of the report. This safety evaluation considers the use of oxalic acid to recover residual waste in single-shell tank (SST) 241-C-106. This is an activity not addressed in the current tank farm safety basis. This evaluation has five specific purposes: (1) Identifying the key configuration and operating assumptions needed to evaluate oxalic acid dissolution in SST 241-C-106. (2) Documenting the hazardous conditions identified during the oxalic acid dissolution hazard and operability study (HAZOP). (3) Documenting the comparison of the HAZOP results to the hazardous conditions and associated analyzed accident currently included in the safety basis, as documented in HNF-SD-WM-TI-764, Hazard Analysis Database Report. (4) Documenting the evaluation of the oxalic acid dissolution activity with respect to: (A) Accident analyses described in HNF-SD-WM-SAR-067, Tank Farms Final Safety Analysis Report (FSAR), and (B) Controls specified in HNF-SD-WM-TSR-006, Tank Farms Technical Safety Requirements (TSR). (5) Documenting the process and results of control decisions as well as the applicability of preventive and/or mitigative controls to each oxalic acid addition hazardous condition. This safety evaluation is not intended to be a request to authorize the activity. Authorization issues are addressed by the unreviewed safety question (USQ) evaluation process. This report constitutes an accident analysis.

SHULTZ, M.V.

2003-06-11T23:59:59.000Z

423

PDF Document (1628k)  

National Nuclear Security Administration (NNSA)

... 6 4.1 Integrated Safety Management (ISM), Integrated Safeguards and Security Management (ISSM), Environmental...

424

Electrical Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE HANDBOOK ELECTRICAL SAFETY DOE-HDBK-1092-2013 July 2013 Superseding DOE-HDBK-1092-2004 December 2004 U.S. Department of Energy AREA SAFT Washington, D.C.20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1092-2013 Available on the Department of Energy Technical Standards Program Web site at http://www.hss.doe.gov/nuclearsafety/techstds/ ii DOE-HDBK-1092-2013 FOREWORD 1. This Department of Energy (DOE) Handbook is approved for use by the Office of Health, Safety and Security and is available to all DOE components and their contractors. 2. Specific comments (recommendations, additions, deletions, and any pertinent data) to enhance this document should be sent to: Patrick Tran

425

FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter  

NLE Websites -- All DOE Office Websites (Extended Search)

H2 Safety Snapshot H2 Safety Snapshot Newsletter to someone by E-mail Share FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Facebook Tweet about FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Twitter Bookmark FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Google Bookmark FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Delicious Rank FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Digg Find More places to share FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on AddThis.com... Home Basics Current Approaches to Safety, Codes & Standards DOE Activities Quick Links Hydrogen Production Hydrogen Delivery Hydrogen Storage Fuel Cells Technology Validation Manufacturing Education Systems Analysis

426

Spent Nuclear Fuel project integrated safety management plan  

SciTech Connect

This document is being revised in its entirety and the document title is being revised to ``Spent Nuclear Fuel Project Integrated Safety Management Plan.

Daschke, K.D.

1996-09-17T23:59:59.000Z

427

A Comparison of the Safety Analysis Process and the Generation IV Proliferation Resistance/Physical Protection Assessment Methodology  

SciTech Connect

The Generation IV International Forum (GIF) is a vehicle for the cooperative international development of future nuclear energy systems. The Generation IV program has established primary objectives in the areas of sustainability, economics, safety and reliability, and Proliferation Resistance and Physical Protection (PR&PP). In order to help meet the latter objective a program was launched in December 2002 to develop a rigorous means to assess nuclear energy systems with respect to PR&PP. The study of Physical Protection of a facility is a relatively well established methodology, but an approach to evaluate the Proliferation Resistance of a nuclear fuel cycle is not. This paper will examine the Proliferation Resistance (PR) evaluation methodology being developed by the PR group, which is largely a new approach and compare it to generally accepted nuclear facility safety evaluation methodologies. Safety evaluation methods have been the subjects of decades of development and use. Further, safety design and analysis is fairly broadly understood, as well as being the subject of federally mandated procedures and requirements. It is therefore extremely instructive to compare and contrast the proposed new PR evaluation methodology process with that used in safety analysis. By so doing, instructive and useful conclusions can be derived from the comparison that will help to strengthen the PR methodological approach as it is developed further. From the comparison made in this paper it is evident that there are very strong parallels between the two processes. Most importantly, it is clear that the proliferation resistance aspects of nuclear energy systems are best considered beginning at the very outset of the design process. Only in this way can the designer identify and cost effectively incorporate intrinsic features that might be difficult to implement at some later stage. Also, just like safety, the process to implement proliferation resistance should be a dynamic, iterative process that continually evolves with the design.

T. A. Bjornard; M. D. Zentner

2006-05-01T23:59:59.000Z

428

A hazard analysis of human factors in safety-critical systems engineering  

Science Conference Proceedings (OSTI)

Safety incident studies often cite human factors as a major cause of accidents. At Bhopal in 1984 human error - the failure to follow safe operating procedures - instigated the deaths of thousands of people from cyanide poisoning. In this case, human ... Keywords: EN50128, IEC 61508, human factors, safety-critical systems engineering

Les Chambers

2006-04-01T23:59:59.000Z

429

Quality Assurance requirements - Safety Analysis Reports for Packaging. An effective approach in developing QA requirements  

SciTech Connect

Application of QA requirements for packaging and transportation of radioactive materials should not be solely based on safety-related considerations. The operability of items, components, and systems must be considered as equally important. The nuclear industry has begun to recognize operability considerations along with safety concerns. This has resulted in a new approach in establishing QA requirements for packaging.

Fabian, R.R.

1986-01-01T23:59:59.000Z

430

Technical support document: Energy conservation standards for consumer products: Dishwashers, clothes washers, and clothes dryers including: Environmental impacts; regulatory impact analysis  

SciTech Connect

The Energy Policy and Conservation Act as amended (P.L. 94-163), establishes energy conservation standards for 12 of the 13 types of consumer products specifically covered by the Act. The legislation requires the Department of Energy (DOE) to consider new or amended standards for these and other types of products at specified times. This Technical Support Document presents the methodology, data and results from the analysis of the energy and economic impacts of standards on dishwashers, clothes washers, and clothes dryers. The economic impact analysis is performed in five major areas: An Engineering Analysis, which establishes technical feasibility and product attributes including costs of design options to improve appliance efficiency. A Consumer Analysis at two levels: national aggregate impacts, and impacts on individuals. The national aggregate impacts include forecasts of appliance sales, efficiencies, energy use, and consumer expenditures. The individual impacts are analyzed by Life-Cycle Cost (LCC), Payback Periods, and Cost of Conserved Energy (CCE), which evaluate the savings in operating expenses relative to increases in purchase price; A Manufacturer Analysis, which provides an estimate of manufacturers' response to the proposed standards. Their response is quantified by changes in several measures of financial performance for a firm. An Industry Impact Analysis shows financial and competitive impacts on the appliance industry. A Utility Analysis that measures the impacts of the altered energy-consumption patterns on electric utilities. A Environmental Effects analysis, which estimates changes in emissions of carbon dioxide, sulfur oxides, and nitrogen oxides, due to reduced energy consumption in the home and at the power plant. A Regulatory Impact Analysis collects the results of all the analyses into the net benefits and costs from a national perspective. 47 figs., 171 tabs. (JF)

1990-12-01T23:59:59.000Z

431

Technical support document: Energy conservation standards for consumer products: Dishwashers, clothes washers, and clothes dryers including: Environmental impacts; regulatory impact analysis  

SciTech Connect

The Energy Policy and Conservation Act as amended (P.L. 94-163), establishes energy conservation standards for 12 of the 13 types of consumer products specifically covered by the Act. The legislation requires the Department of Energy (DOE) to consider new or amended standards for these and other types of products at specified times. This Technical Support Document presents the methodology, data and results from the analysis of the energy and economic impacts of standards on dishwashers, clothes washers, and clothes dryers. The economic impact analysis is performed in five major areas: An Engineering Analysis, which establishes technical feasibility and product attributes including costs of design options to improve appliance efficiency. A Consumer Analysis at two levels: national aggregate impacts, and impacts on individuals. The national aggregate impacts include forecasts of appliance sales, efficiencies, energy use, and consumer expenditures. The individual impacts are analyzed by Life-Cycle Cost (LCC), Payback Periods, and Cost of Conserved Energy (CCE), which evaluate the savings in operating expenses relative to increases in purchase price; A Manufacturer Analysis, which provides an estimate of manufacturers' response to the proposed standards. Their response is quantified by changes in several measures of financial performance for a firm. An Industry Impact Analysis shows financial and competitive impacts on the appliance industry. A Utility Analysis that measures the impacts of the altered energy-consumption patterns on electric utilities. A Environmental Effects analysis, which estimates changes in emissions of carbon dioxide, sulfur oxides, and nitrogen oxides, due to reduced energy consumption in the home and at the power plant. A Regulatory Impact Analysis collects the results of all the analyses into the net benefits and costs from a national perspective. 47 figs., 171 tabs. (JF)

Not Available

1990-12-01T23:59:59.000Z

432

Portsmouth DUF6 Conversion Final EIS - Volume 2: Comment and Response Document: Chapter 2: Comment Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Portsmouth DUF Portsmouth DUF 6 Conversion Final EIS 2 COMMENT DOCUMENTS This section provides copies of the actual letters or other documents containing public comments on the draft EISs that were submitted to DOE, including comments extracted from the transcripts of the public hearings. Table 2.1 contains an index of the comment documents by document number. Table 2.2 provides an index of comment documents by the commentors last name. Table 2.3 contains an index of comment documents by company or organization. Individual comments are denoted with vertical lines in the right margin. TABLE 2.1 Index of Commentors by Document Number Document Number Name Company/Organization Page D0001 Driver, Charles M. Individual 2-5 D0002 Kilrod, John Individual 2-7 D0003 Colley, Vina Portsmouth/Piketon Residents for Environmental Safety and Security

433

CY 2012 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2 2 Reporting Office: Chief of Nuclear Safety . Section One: Current Mission(s) of the Organization and Potential Changes Revision 2 of U.S. Department of Energy Implementation Plan for DNFSB Recommendation 2004-1 established the seven core CTA responsibilities. The Office of the Chief of Nuclear Safety (CNS) performs to following functions in support of the CTA meeting these responsibilities: 1. Nuclear Safety Requirement Concurrence and Exemption * Concur with the determination of the applicability of DOE directives involving nuclear safety included in Energy and Science contracts pursuant to Department of Energy Acquisition Regulation (DEAR), 48 CFR 970.5204-2, Laws, regulations, and DOE directives, item (b). * Concur with nuclear safety requirements included in Energy and Science contracts pursuant to

434

CY 2011 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1 1 Reporting Office: Chief of Nuclear Safety . Section One: Current Mission(s) of the Organization and Potential Changes Revision 2 of U.S. Department of Energy Implementation Plan for DNFSB Recommendation 2004-1 established the seven core CTA responsibilities. The Office of the Chief of Nuclear Safety (CNS) performs to following functions in support of the CTA meeting these responsibilities: 1. Nuclear Safety Requirement Concurrence and Exemption * Concur with the determination of the applicability of DOE directives involving nuclear safety included in Energy and Science contracts pursuant to Department of Energy Acquisition Regulation (DEAR), 48 CFR 970.5204-2, Laws, regulations, and DOE directives, item (b). * Concur with nuclear safety requirements included in Energy and Science contracts pursuant to

435

Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module  

DOE Green Energy (OSTI)

The US is proposing a prototype of a dual coolant liquid lead-lithium (DCLL) DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER Test Blanket Module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER International Team (IT) to address specific reactor safety concerns, such as VV pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system, and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

Merrill, Brad; Reyes, Susana; Sawan, Mohamed; Wong, Clement

2006-07-01T23:59:59.000Z

436

Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 2, Rev. 14  

SciTech Connect

This appendix determines the effective G values for payload shipping categories of contact handled transuranic (CH-TRU) waste materials, based on the radiolytic G values for waste materials that are discussed in detail in Appendix 3.6.8 of the Safety Analysis Report for the TRUPACT-II Shipping Package. The effective G values take into account self-absorption of alpha decay energy inside particulate contamination and the fraction of energy absorbed by nongas-generating materials. As described in Appendix 3.6.8, an effective G value, G{sub eff}, is defined by: G{sub eff} - {Sigma}{sub M} (F{sub M} x G{sub M}) F{sub M}-fraction of energy absorbed by material maximum G value for a material where the sum is over all materials present inside a waste container. The G value itself is determined primarily by the chemical properties of the material and its temperature. The value of F is determined primarily by the size of the particles containing the radionuclides, the distribution of radioactivity on the various materials present inside the waste container, and the stopping distance of alpha particles in air, in the waste materials, or in the waste packaging materials.

NONE

1994-10-01T23:59:59.000Z

437

Quality System Documentation Management  

Science Conference Proceedings (OSTI)

Quality System Documentation Management. ... Minutes, summaries, or notes from Management Meetings of significance are archived here. ...

2012-08-21T23:59:59.000Z

438

SRS - ARRA General Provisions and Related Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

American Recovery and Reinvestment Act (ARRA) American Recovery and Reinvestment Act (ARRA) General Provisions and Related Documents General Provisions/Terms and Conditions Documents Certifications Solicitation/Subcontract Documents Focused Observation Safety Checklists Construction Subcontract Documents/Forms General Provisions/Terms and Conditions Documents DOCUMENT NUMBER TITLE REVISION # or DATE SRNS-MS-2009-00069 Fixed Price Orders 5 SRNS-MS-2009-00072 Construction Subcontract Exhibit A 7 SRNS-MS-2009-00073 Time and Material / Labor Hour 5 SRNS-MS-2009-00074 Commercial Terms and Conditions for Dismantling, Demolition, or Removal of Improvements 5 SRNS-MS-2009-00075 Corporate Professional Services 6 SRNS-MS-2009-00076 Individual Consultants 5 SRNS-MS-2010-00085 Cost Reimbursement Orders with Educational Institutions 4

439

FACILITY SAFETY (FS)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

FACILITY SAFETY (FS) FACILITY SAFETY (FS) OBJECTIVE FS.1 - (Core Requirement 7) Facility safety documentation in support of SN process operations,is in place and has been implemented that describes the safety envelope of the facility. The, safety documentation should characterize the hazards/risks associated with the facility and should, identify preventive and mitigating measures (e.g., systems, procedures, and administrative, controls) that protect workers and the public from those hazards/risks. (Old Core Requirement 4) Criteria 1. A DSA has been prepared by FWENC, approved by DOE, and implemented to reflect the SN process operations in the WPF. (10 CFR 830.200, DOE-STD-3009-94) 2. A configuration control program is in place and functioning such that the DSA is

440

Licensed reactor nuclear safety criteria applicable to DOE reactors  

SciTech Connect

This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

Not Available

1993-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "documented safety analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Analysis of Severe Accident Scenarios and Proposals for Safety Improvements for ADS Transmuters with Dedicated Fuel  

SciTech Connect

So-called dedicated fuels will be utilized to obtain maximum transmutation and incineration rates of minor actinides (MAs) in accelerator-driven systems (ADSs). These fuels are characterized by a high-MA content and the lack of the classical fertile materials such as {sup 238}U or {sup 232}Th. Dedicated fuels still have to be developed; however, programs are under way for their fabrication, irradiation, and testing. In Europe, mainly the oxide route is investigated and developed. A dedicated core will contain multiple 'critical' fuel masses, resulting in a certain recriticality potential under core degradation conditions. The use of dedicated fuels may also lead to strong deterioration of the safety parameters of the reactor core, such as, e.g., the void worth, Doppler or the kinetics quantities, neutron generation time, and {beta}{sub eff}. Critical reactors with this kind of fuel might encounter safety problems, especially under severe accident conditions. For ADSs, it is assumed that because of the subcriticality of the system, the poor safety features of such fuels could be coped with. Analyses reveal some safety problems for ADSs with dedicated fuels. Additional inherent and passive safety measures are proposed to achieve the required safety level. A safety strategy along the lines of a defense approach is presented where these measures can be integrated. The ultimate goal of these measures is to eliminate any mechanistic severe accident scenario and the potential for energetics.

Maschek, Werner [Forschungszentrum Karlsruhe Institute for Nuclear and Energy Technologies (Germany); Rineiski, Andrei [Forschungszentrum Karlsruhe Institute for Nuclear and Energy Technologies (Germany); Flad, Michael [Forschungszentrum Karlsruhe Institute for Nuclear and Energy Technologies (Germany); Morita, Koji [Kyushu University Institute of Environmental Systems (Japan); Coste, Pierre [Commissariat a l'Energie Atomique CE Grenoble (France)

2003-02-15T23:59:59.000Z

442

Literature review of environmental qualification of safety-related electric cables: Literature analysis and appendices. Volume 2  

Science Conference Proceedings (OSTI)

In support of the US NRC Environmental Qualification (EQ) Research Program, a literature review was performed to identify past relevant work that could be used to help fully or partially resolve issues of interest related to the qualification of low-voltage electric cable. A summary of the literature reviewed is documented in Volume 1 of this report. In this, Volume 2 of the report, dossiers are presented which document the issues selected for investigation in this program, along with recommendations for future work to resolve the issues, when necessary. The dossiers are based on an analysis of the literature reviewed, as well as expert opinions. This analysis includes a critical review of the information available from past and ongoing work in thirteen specific areas related to EQ. The analysis for each area focuses on one or more questions which must be answered to consider a particular issue resolved. Results of the analysis are presented, along with recommendations for future work. The analysis is documented in the form of a dossier for each of the areas analyzed.

Lofaro, R.; Bowerman, B.; Carbonaro, J. [Brookhaven National Lab., Upton, NY (United States)] [and others

1996-04-01T23:59:59.000Z

443

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747  

SciTech Connect

'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

RYAN GW

2007-09-24T23:59:59.000Z

444

Savannah River Site - Enforcement Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Enforcement Documents Enforcement Documents Savannah River Site Preliminary Notice of Violation issued to Savannah River Nuclear Solutions, LLC related to a Puncture Wound Injury resulting in a Radiological Uptake at the Savannah River Site, July 22, 2011 (NEA-2011-02) Consent Order issued to Parsons Infrastructure & Technology Group, Inc., related to Nuclear Facility Construction Deficiencies and Subcontractor Oversight at the Salt Waste Processing Facility at the Savannah River Site, April 13, 2010 Enforcement Letter issued to Amer Industrial Technologies, Inc. related to Weld Deficiencies at the Salt Waste Processing Facility at the Savannah River Site, April 13, 2010 Enforcement Letter issued to Parsons Technology Development & Fabrication Complex related to Deficiencies in the Fabrication of Safety Significant Embed Plates at the Salt Waste Processing Facility at the Savannah River Site, April 13, 2010

445

Argonne National Laboratory - Enforcement Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

Enforcement Documents Enforcement Documents Argonne National Laboratory Preliminary Notice of Violation issued to the University of Chicago related to Nuclear Safety Program Deficiencies at Argonne National Laboratory, March 7, 2006 (EA-2006-02) - University of Chicago/Argonne National Laboratory - Press Release, March 7, 2006 Preliminary Notice of Violation issued to the University of Chicago related to the Uncontrolled Release of Radioactive Material at Argonne National Laboratory-East, August 14, 2001 (EA-2001-05) - Argonne National Laboratory - Press Release, August 17, 2001 Preliminary Notice of Violation issued to the University of Chicago related to Programmatic Management Failures at Argonne National Laboratory-West, February 28, 2001 (EA-2001-01) - Argonne National Laboratory-West - Press Release, March 2, 2001

446

LNG Export Study - Related Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

LNG Export Study - Related Documents LNG Export Study - Related Documents Federal Register Notice of Availability of the LNG Export Study EIA Analysis (Study - Part 1) NERA...

447

Documents | Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

& simulation ---Nuclear fuel cycle ----Geology & disposal ---Reactors ----Nuclear reactor safety ----Nuclear reactor materials ----Nuclear system technologies & diagnostics...

448

Documents: DUF6 Conversion EIS Supporting Documents  

NLE Websites -- All DOE Office Websites (Extended Search)

DUF6 Conversion EIS DUF6 Conversion EIS Search Documents: Search PDF Documents View a list of all documents NEPA Compliance: DUF6 Conversion EIS Supporting Documents PDF Icon Notice of Change in National Environmental Policy Act (NEPA) Compliance Approach for the Depleted Uranium Hexafluoride (DUF6) Conversion Facilities Project 38 KB details PDF Icon Press Release: DOE Seeks Public Input for Depleted Uranium Hexafluoride Environmental Impact Statement 90 KB details PDF Icon Advance Notice of Intent To Prepare an Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities 52 KB details PDF Icon Notice of Intent to Prepare an Environmental Impact Statement for Depleted Uranium Hexafluoride Conversion Facilities 60 KB details PDF Icon Overview: Depleted Uranium Hexafluoride (DUF6) Management Program

449

Document Control Template-Form  

NLE Websites -- All DOE Office Websites (Extended Search)

5ADocument Control Template - ExcelForm EOTA - Business Form Document Title: P-001, Document Control Process Document Number: Document Control Template - Excel Form EOTA...

450

Document Control Template-Form  

NLE Websites -- All DOE Office Websites (Extended Search)

4Document Control Template - Form 110815.doc 110815 Page 1 of 5 EOTA - Business Form Document Title: Document Control Template - Form Document Number: F-004 Rev. 110815...

451

WIPP Documents - EPA Certification  

NLE Websites -- All DOE Office Websites (Extended Search)

(PCBs) at WIPP This document provides EPA approval for the disposal of TRU and TRU-Mixed waste containing PCBs at the WIPP. Attached to this document is a list of conditions...

452

DOE/EM Criticality Safety Needs Assessment  

SciTech Connect

The issue of nuclear criticality safety (NCS) in Department of Energy Environmental Management (DOE/EM) fissionable material operations presents challenges because of the large quantities of material present in the facilities and equipment that are committed to storage and/or material conditioning and dispositioning processes. Given the uncertainty associated with the material and conditions for many DOE/EM fissionable material operations, ensuring safety while maintaining operational efficiency requires the application of the most-effective criticality safety practices. In turn, more-efficient implementation of these practices can be achieved if the best NCS technologies are utilized. In 2002, DOE/EM-1 commissioned a survey of criticality safety technical needs at the major EM sites. These needs were documented in the report Analysis of Nuclear Criticality Safety Technology Supporting the Environmental Management Program, issued May 2002. Subsequent to this study, EM safety management personnel made a commitment to applying the best and latest criticality safety technology, as described by the DOE Nuclear Criticality Safety Program (NCSP). Over the past 7 years, this commitment has enabled the transfer of several new technologies to EM operations. In 2008, it was decided to broaden the basis of the EM NCS needs assessment to include not only current needs for technologies but also NCS operational areas with potential for improvements in controls, analysis, and regulations. A series of NCS workshops has been conducted over the past years, and needs have been identified and addressed by EM staff and contractor personnel. These workshops were organized and conducted by the EM Criticality Safety Program Manager with administrative and technical support by staff at Oak Ridge National Laboratory (ORNL). This report records the progress made in identifying the needs, determining the approaches for addressing these needs, and assimilating new NCS technologies into EM fissionable material operations. In addition, the report includes projections of future EM needs and associted recommendations.

Westfall, Robert Michael [ORNL; Hopper, Calvin Mitchell [ORNL

2011-02-01T23:59:59.000Z

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Safety and Security Enforcement Program  

NLE Websites -- All DOE Office Websites (Extended Search)

Enforcement Enforcement Enforcement Home Worker Safety and Health Enforcement Office of Nuclear Safety Enforcement Security Enforcement Notices of Violation Consent Orders / Settlement Agreements Compliance Orders Special Report Orders Enforcement Letters Regulatory Assistance Reviews Enforcement Program and Process Guidance and Information Non-Compliance Tracking System (NTS) Non-Compliance Reporting Thresholds Regulations and Directives Enforcement Staff Enforcement Coordinator Contact Information 2013 DOE Safety and Security Enforcement Workshop Request for Investigation or Inspection of Safety or Security Violations Archived Documents HSS Logo Safety and Security Enforcement Program Office of Enforcement and Oversight What's New: » Worker Safety and Health Enforcement Preliminary Notice of Violation issued to Brookhaven Science Associates, LLC

454

GTT Tranmission Workshop- Documents  

Energy.gov (U.S. Department of Energy (DOE))

Use the links below to download documents from the GTT Transmission Workshop, held November 1-2, 2012.

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PDF Document (1188k)  

Office of Legacy Management (LM)

Only critical information was scanned. Entire document is available upon request - Click here to email a request....