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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  

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

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

CRAD, Nuclear Safety Delegations for Documented Safety Analysis...  

Office of Environmental Management (EM)

Nuclear Safety Delegations for Documented Safety Analysis Approval - January 8, 2015 (EA CRAD 31-09, Rev. 0) CRAD, Nuclear Safety Delegations for Documented Safety Analysis...

3

B PLANT DOCUMENTED SAFETY ANALYSIS  

SciTech Connect (OSTI)

This document provides the documented safety analysis (DSA) and Central Plateau Remediation Project (CP) requirements that apply to surveillance and maintenance (S&M) activities at the 221-B Canyon Building and ancillary support structures (B Plant). The document replaces BHI-010582, Documented Safety Analysis for the B-Plant Facility. The B Plant is non-operational, deactivated and undergoing long term S&M prior to decontamination and decommissioning (D&D). This DSA is compliant with 10 CFR 830, Nuclear Safety Management, Subpart B, ''Safety Basis Requirements.'' The DSA was developed in accordance with U.S. Department of Energy (DOE) standard DOE-STD-1120-98, Integration of Environment, Safety, and Health into Facility Disposition Activities (DOE 1998) per Table 2 of 10 CFR 830 Appendix A, DOE Richland Operation Office (RL) direction (02-ABD-0053, Fluor Hanford Nuclear Safety Basis Strategy and Criteria) for facilities in long term S&M, and RL Direction (02-ABD-0091, ''FHI Nuclear Safety Expectations for Nuclear Facilities in Surveillance and Maintenance''). A crosswalk was prepared to identify potential inconsistencies between the previous B Plant safety analysis and DOE-STD-1120-98 guidance. In general, the safety analysis met the criteria of DOE-STD-1120-98. Some format and content changes have been made, including incorporating recent facility modifications and updating the evaluation guidelines and control selection criteria in accordance with RL direction (02-ABD-0053). The facility fire hazard analysis (FHA) and Technical Safety Requirements (TSR) are appended to this DSA as an aid to the users, to minimize editorial redundancy, and to provide an efficient basis for update.

DODD, E.N.; KERR, N.R.

2003-08-01T23:59:59.000Z

4

CRAD, Facility Safety- Documented Safety Analysis  

Broader source: Energy.gov [DOE]

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 Documented Safety Analysis.

5

CRAD, New Nuclear Facility Documented Safety Analysis and Technical...  

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

New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements - December 2, 2014 (EA CRAD 31-07, Rev. 0) CRAD, New Nuclear Facility Documented Safety Analysis...

6

CRAD, Preliminary Documented Safety Analysis - July 25, 2014...  

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

Preliminary Documented Safety Analysis - July 25, 2014 (IEA CRAD 31-2, REV. 0) CRAD, Preliminary Documented Safety Analysis - July 25, 2014 (IEA CRAD 31-2, REV. 0) July 25, 2014...

7

CRAD, Documented Safety Analysis Development- April 23, 2013  

Broader source: Energy.gov [DOE]

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

8

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

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

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

9

SNF fuel retrieval sub project safety analysis document  

SciTech Connect (OSTI)

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

10

CRAD, Nuclear Safety Delegations for Documented Safety Analysis Approval January 8, 2015 (EA CRAD 31-09, Rev. 0)  

Broader source: Energy.gov [DOE]

CRAD, Nuclear Safety Delegations for Documented Safety Analysis Approval January 8, 2015 (EA CRAD 31-09, Rev. 0)

11

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

SciTech Connect (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

12

CRAD, Preliminary Documented Safety Analysis- July 25, 2014 (IEA CRAD 31-2, REV. 0)  

Broader source: Energy.gov [DOE]

This Criteria Review and Approach Document (IEA CRAD 31-2, REV. 0) provides objectives, criteria, and approaches for reviewing Nuclear Facility Preliminary Documented Safety Analysis.

13

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

SciTech Connect (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

14

K West integrated water treatment system subproject safety analysis document  

SciTech Connect (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

15

Planning Document for an NBSR Conversion Safety Analysis Report  

SciTech Connect (OSTI)

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

16

CRAD, New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements- December 2, 2014 (EA CRAD 31-07, Rev. 0)  

Broader source: Energy.gov [DOE]

New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements Criteria Review and Approach Document (EA CRAD 31-07, Rev. 0)

17

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

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

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

DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis, Roll Out Training  

Broader source: Energy.gov [DOE]

The Office of Nuclear Safety is performing a series of site visits to provide roll-out training and assistance to Program and Site Offices and their contractors on effective implementation of the new revision to DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis.

19

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

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

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

20

Spent nuclear fuel project - criteria document spent nuclear fuel final safety analysis report  

SciTech Connect (OSTI)

The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building).

MORGAN, R.G.

1999-02-23T23:59:59.000Z

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.


21

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

SciTech Connect (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

22

Complete Experiment Safety Documentation  

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

Complete Experiment Safety Documentation  

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

24

Complete Experiment Safety Documentation  

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

25

Complete Experiment Safety Documentation  

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

26

Preliminary Safety Assessment Document  

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

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

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

SciTech Connect (OSTI)

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

29

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  

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

30

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  

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

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

31

Complete Experiment Safety Documentation  

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

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, and Hazardous...

32

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

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

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;

33

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

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

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;

34

Reactor operation safety information document  

SciTech Connect (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

35

Safety and Emergency Management Evaluations - Guidance Documents  

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

36

Expectations on Documented Safety Analysis for Deactivated Inactive Nuclear Facilities in a State of Long Term Surveillance & Maintenance or Decommissioning  

SciTech Connect (OSTI)

DOE promulgated 10 CFR 830 ''Nuclear Safety Management'' on October 10, 2000. Section 204 of the Rule requires that contractors at DOE hazard category 1, 2, and 3 nuclear facilities develop a ''Documented Safety Analysis'' (DSA) that summarizes the work to be performed, the associated hazards, and hazard controls necessary to protect workers, the public, and the environment. Table 2 of Appendix A to the rule has been provided to ensure that DSAs are prepared in accordance with one of the available predetermined ''safe harbor'' approaches. The table presents various acceptable safe harbor DSAs for different nuclear facility operations ranging from nuclear reactors to decommissioning activities. The safe harbor permitted for decommissioning of a nuclear facility encompasses methods described in DOE-STD-1 120-98, ''Integration of Environment, Safety and Health into Facility Disposition Activities,'' and provisions in 29 CFR 1910.120 or 29 CFR 1926.65 (HAZWOPER). Additionally, an evaluation of public safety impacts and development of necessary controls is required when the facility being decommissioned contains radiological inventory or contamination exceeding the Rule's definition for low-level residual fixed radioactivity. This document discusses a cost-effective DSA approach that is based on the concepts of DOE-STD-I 120 and meets the 10 CFR 830 safe harbor requirements for both transition surveillance and maintenance as well as decommissioning. This DSA approach provides continuity for inactive Hanford nuclear facilities that will eventually transition into decommissioning. It also uses a graded approach that meets the expectations of DOE-STD-3011 and addresses HAZWOPER requirements to provide a sound basis for worker protection, particularly where intrusive work is being conducted.

JACKSON, M.W.

2002-05-01T23:59:59.000Z

37

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)  

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

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

38

Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report. Revision 3  

SciTech Connect (OSTI)

Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals.

Herborn, D.I.

1993-11-01T23:59:59.000Z

39

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

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

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.

40

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

SciTech Connect (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

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

Nuclear Safety Enforcement Documents | Department of Energy  

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

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

42

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

Broader source: Energy.gov [DOE]

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.

43

Safety Basis Criteria & Review Approach Documents | Department of Energy  

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

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

44

Occupational Safety & Health Criteria & Review Approach Documents |  

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

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

45

Documentation Integrity for Safety-Critical Applications: The COHERE Project  

E-Print Network [OSTI]

. Keywords Authoring interface, documentation integrity, consistency 1. INTRODUCTION This paper reportsDocumentation Integrity for Safety-Critical Applications: The COHERE Project David G. Novick-critical systems. Following a set of documentation integrity maxims, the project developed two generations

Novick, David G.

46

ACCELERATOR TEST FACILITY SAFETY ASSESSMENT DOCUMENT TABLE OF...  

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

Revised: March 1, 2010 i ACCELERATOR TEST FACILITY SAFETY ASSESSMENT DOCUMENT TABLE OF CONTENTS 1. INTRODUCTION AND DESCRIPTION OF THE FACILITY ......

47

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

Broader source: Energy.gov [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.

48

Hanford safety analysis and risk assessment handbook (SARAH)  

SciTech Connect (OSTI)

The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 1,2, and 3 U.S. Department of Energy (DOE) nuclear facilities. SARAH describes currently acceptable methodology for development of a Documented Safety Analysis (DSA) and derivation of technical safety requirements (TSR) based on 10 CFR 830, ''Nuclear Safety Management,'' Subpart B, ''Safety Basis Requirements,'' and provides data to ensure consistency in approach.

GARVIN, L.J.

2003-01-20T23:59:59.000Z

49

Nuclear Safety Enforcement Documents | Department of Energy  

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

2001 Issued to CH2M Hill Hanford Group, Inc., related to Nuclear Safety Management at the Hanford Site Tank Farms March 19, 2001 Preliminary Notice of Violation, BNFL, Inc -...

50

Test Protocol Document, Hydrogen Safety Sensor Testing; Phase...  

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

Test Protocol Document, Hydrogen Safety Sensor Testing Phase I: Non-Flammable Mixtures R. Burgess, C. Blake, and C.E. Tracy Technical Report NRELTP-560-42666 September 2008 NREL...

51

Classification of Aeronautics System Health and Safety Documents  

E-Print Network [OSTI]

1 Classification of Aeronautics System Health and Safety Documents Nikunj Oza, Member, IEEE, J to support tracking trends in problem categories over time. A decision support system that performs consistent document classification quickly and over large repositories would be very useful. We discuss

Oza, Nikunj C.

52

Nuclear Safety Enforcement Documents | Department of Energy  

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

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

53

Worker Safety and Health Enforcement Documents | Department of Energy  

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

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

54

Technical Standards, Safety Analysis Toolbox Codes - November...  

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

Standards, Safety Analysis Toolbox Codes - November 2003 November 2003 Software Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes Safety analysis...

55

Technical Standards, Safety Analysis Toolbox Codes - November 2003 |  

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

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

56

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

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

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

57

Hanford Site Wide Transportation Safety Document [SEC 1 Thru 3  

SciTech Connect (OSTI)

This safety evaluation report (SER) documents the basis for the US Department of Energy (DOE), Richland Operations Office (RL) to approve the Hanford Sitewide Transportation Safety Document (TSD) for onsite Transportation and Packaging (T&P) at Hanford. Hanford contractors, on behalf of DOE-RL, prepared and submitted the Hanford Sitewide Transportation Safety Document, DOE/RL-2001-0036, Revision 0, (DOE/RL 2001), dated October 4, 2001, which is referred to throughout this report as the TSD. In the context of the TSD, Hanford onsite shipments are the activities of moving hazardous materials, substances, and wastes between DOE facilities and over roadways where public access is controlled or restricted and includes intra-area and inter-area movements. The TSD sets forth requirements and standards for onsite shipment of radioactive and hazardous materials and wastes within the confines of the Hanford Site on roadways where public access is restricted by signs, barricades, fences, or other means including road closures and moving convoys controlled by Hanford Site security forces.

MCCALL, D L

2002-06-01T23:59:59.000Z

58

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

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

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:

59

H:\\Transfer\\My Documents\\Cleary Fire Report\\Annual Fire Safety Report 2013.doc Annual Fire Safety Report  

E-Print Network [OSTI]

and Fire Protection (Cal Fire) responds to the State Response Area of campus, including the outlyingH:\\Transfer\\My Documents\\Cleary Fire Report\\Annual Fire Safety Report 2013.doc Annual Fire Safety #12;H:\\Transfer\\My Documents\\Cleary Fire Report\\Annual Fire Safety Report 2013.doc Fire and Life

Sze, Lawrence

60

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

E-Print Network [OSTI]

and Fire Protection (Cal Fire) responds to the State Response Area of campus, including the outlyingH:\\Transfer\\My Documents\\Cleary Fire Report\\Annual Fire Safety Report 2012.doc Annual Fire Safety #12;H:\\Transfer\\My Documents\\Cleary Fire Report\\Annual Fire Safety Report 2012.doc Fire and Life

Sze, Lawrence

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

Patterns and Reuse in Document Engineering Keywords: Document Engineering, Document Analysis, Data Analysis, Data Modeling, Patterns, Reuse,  

E-Print Network [OSTI]

to business processes via Web-based services. The essence of Document Engineering is the analysis and designPatterns and Reuse in Document Engineering Keywords: Document Engineering, Document Analysis, Data and an Engineering Fellow at Commerce One. He founded or co-founded three companies, the last of which was Veo

Glushko, Robert J.

62

Health and Safety Policy This Health and Safety Policy document comprises a Policy Statement and details the  

E-Print Network [OSTI]

) The Corporate Manslaughter and Corporate Homicide Act and (ii) The Health & Safety at Work etc. Act. UnderHealth and Safety Policy UHSP/0/10 This Health and Safety Policy document comprises a Policy for implementing and monitoring them (UEP/0/10). The University has a Food Safety Policy Statement that covers all

Birmingham, University of

63

Events Beyond Design Safety Basis Analysis | Department of Energy  

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

Events Beyond Design Safety Basis Analysis Events Beyond Design Safety Basis Analysis March 23, 2011 Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis This Safety...

64

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

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

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 ..........................................................................................................................

65

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

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

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.

66

Safety System Oversight Staffing Analysis (Instructions, Blank...  

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

Safety System Oversight Staffing Analysis (Instructions, Blank Sheet and Example Sheet) Safety System Oversight Staffing Analysis (Instructions, Blank Sheet and Example Sheet) This...

67

Integration of Safety Culture Attributes into the EFCOG WP&C Program Guideline Document  

Broader source: Energy.gov [DOE]

Slide Presentation by Steele Coddington, NSTec, Las Vegas and John McDonald, WRPS, Hanford. Integration of Safety Culture Attributes into EFCOG Work Planning and Control Guidance Document.

68

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

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

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

69

Waste Isolation Pilot Plant Safety Analysis Report  

SciTech Connect (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

70

Volume II - Accident and Operational Safety Analysis Handbook  

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

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

71

Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20  

SciTech Connect (OSTI)

This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

Not Available

1994-09-01T23:59:59.000Z

72

Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk  

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

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

73

Worker Safety and Health Enforcement Documents | Department of...  

Office of Environmental Management (EM)

Portsmouth, LLC June 20, 2014 Preliminary Notice of Violation, Battelle Energy Alliance, LLC Worker Safety and Health Preliminary Notice of Violation issued to Battelle...

74

Corporate Analysis of DOE Safety Performance | Department of...  

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

Analysis of DOE Safety Performance Current Safety Performance Trends The Office of Environment, Health, Safety and Security, Office of Analysis provides analysis of Department of...

75

Tracking discourse and qualitative document analysis  

Science Journals Connector (OSTI)

New information bases pose challenges and opportunities for researchers seeking to enhance content analysis and chart cultural shifts using public documents such as newspapers and magazines. A qualitative approach to media analysis is combined with a specific application, tracking discourse, to demonstrate how research questions can be transformed into a research design that permits rich textual interpretive and thematic analysis, as well as provide quantitative information about trends and emphases over time, across media, and across topics. Materials from an ongoing project on the discourse of fear illustrate a shift in major American newspapers' coverage toward more extensive use of crime, fear, and victim. Implications for cultural researchers are discussed.

David L. Altheide

2000-01-01T23:59:59.000Z

76

Monthly Analysis of Electrical Safety Occurrences - February...  

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

2 Monthly Analysis of Electrical Safety Occurrences - February 2012 February 2012 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by...

77

Monthly Analysis of Electrical Safety Occurrences - November...  

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

1 Monthly Analysis of Electrical Safety Occurrences - November 2011 November 2011 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by...

78

Implementation Guide for Use in Developing Documented Safety Analyses to Meet Subpart B of 10 CFR 830  

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

This Guide elaborates on the documented safety analysis (DSA) development process and the safe harbor provisions of the Appendix to10 CFR 830 Subpart B. Title 10 Code of Federal Regulations (CFR) Part 830, Subpart B, 'Safety Basis Requirements,' requires the contractor responsible for a Department of Energy (DOE) nuclear facility to analyze the facility, the work to be performed, and the associated hazards and to identify the conditions, safe boundaries, and hazard controls necessary to protect workers, the public, and the environment from adverse consequences. Canceled by DOE G 421.1-2A

2001-10-24T23:59:59.000Z

79

Worker Safety and Health Enforcement Documents | Department of Energy  

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

, 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

80

Worker Safety and Health Enforcement Documents | Department of Energy  

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

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

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

Safety assessment document for the Dynamic Test Complex B854  

SciTech Connect (OSTI)

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

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

1981-12-11T23:59:59.000Z

82

ASD Facility Hazard Analysis Document - Building 382  

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

NA 6 ESH119 ESH145 NA NA NA A ESH108382 Thin Film Chamber Electrical Compressed gas Cryogenic vacuum Grounded vacuum chamber Safety interlocks on chamber door Safety committee...

83

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  

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

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

84

Monthly Analysis of Electrical Safety Occurrences - March 2011...  

Energy Savers [EERE]

Monthly Analysis of Electrical Safety Occurrences - March 2011 Monthly Analysis of Electrical Safety Occurrences - March 2011 March 2011 An analysis of the Occurrence Reporting and...

85

Safe Handling of Cryogenic Liquids This document describes the principal hazards and appropriate safety procedures associated  

E-Print Network [OSTI]

92 Safe Handling of Cryogenic Liquids This document describes the principal hazards and appropriate safety procedures associated with three cryogenic liquids that are commonly used in the College: liquid N2, He and O2.. The safe handling of cryogenic liquids involves understanding the unique properties

Cohen, Ronald C.

86

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

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

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

87

Evaluation of safety assessment methodologies in Rocky Flats Risk Assessment Guide (1985) and Building 707 Final Safety Analysis Report (1987)  

SciTech Connect (OSTI)

FSARs. Rockwell International, as operating contractor at the Rocky Flats plant, conducted a safety analysis program during the 1980s. That effort resulted in Final Safety Analysis Reports (FSARs) for several buildings, one of them being the Building 707 Final Safety Analysis Report, June 87 (707FSAR) and a Plant Safety Analysis Report. Rocky Flats Risk Assessment Guide, March 1985 (RFRAG85) documents the methodologies that were used for those FSARs. Resources available for preparation of those Rocky Flats FSARs were very limited. After addressing the more pressing safety issues, some of which are described below, the present contractor (EG&G) intends to conduct a program of upgrading the FSARs. This report presents the results of a review of the methodologies described in RFRAG85 and 707FSAR and contains suggestions that might be incorporated into the methodology for the FSAR upgrade effort.

Walsh, B.; Fisher, C.; Zigler, G.; Clark, R.A. [Science and Engineering Associates, Inc., Albuquerque, NM (United States)

1990-11-09T23:59:59.000Z

88

Safety analysis report for packaging (onsite) multicanister overpack cask  

SciTech Connect (OSTI)

This safety analysis report for packaging (SARP) documents the safety of shipments of irradiated fuel elements in the MUlticanister Overpack (MCO) and MCO Cask for a highway route controlled quantity, Type B fissile package. This SARP evaluates the package during transfers of (1) water-filled MCOs from the K Basins to the Cold Vacuum Drying Facility (CVDF) and (2) sealed and cold vacuum dried MCOs from the CVDF in the 100 K Area to the Canister Storage Building in the 200 East Area.

Edwards, W.S.

1997-07-14T23:59:59.000Z

89

Fuel Storage Facility Final Safety Analysis Report. Revision 1  

SciTech Connect (OSTI)

The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

Linderoth, C.E.

1984-03-01T23:59:59.000Z

90

ASD Facility Hazard Analysis Document - Building 400  

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

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

ASD Facility Hazard Analysis Document - Building 413  

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

93

ASD Facility Hazard Analysis Document - Building 412  

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

94

Rapid Exploitation and Analysis of Documents  

SciTech Connect (OSTI)

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

95

Documentation  

Science Journals Connector (OSTI)

Documentation has a bad reputation among software developers. Just mention documentation, and those of us who were raised on traditional waterfall software project methods remember weighty requirements docum...

Patrick Cimolini; Karen Cannell

2012-01-01T23:59:59.000Z

96

Autoclave nuclear criticality safety analysis  

SciTech Connect (OSTI)

Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

D`Aquila, D.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Tayloe, R.W. Jr. [Battelle, Columbus, OH (United States)

1991-12-31T23:59:59.000Z

97

Document  

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

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

98

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

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

99

Documents  

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

100

Document  

Office of Environmental Management (EM)

the safety, security, and reliability of existing nuclear warheads without the use of nuclear testing. Throughout the 1990s, DOE also took steps to consolidate the Complex from...

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

On the Integration of Requirements Analysis and Safety Analysis for Safety-Critical Software  

E-Print Network [OSTI]

this is acceptable within the context of system risk. The advantage of conducting the safety analysis during is acceptable within the overall #12;2 system risk. If the risk is not acceptable the safety specification has analysis is to determine the risk associated with requirements specifications and assess whether

Newcastle upon Tyne, University of

102

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

103

Document  

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

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

104

Document  

National Nuclear Security Administration (NNSA)

various sources, and in view of the time needed to promulgate a rule, then-Secretary of Energy Pen a directed the Office of Environment, Safety and Health to publish a new DOE...

105

Document  

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

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

106

SAFETY AND RELIABILITY ANALYSIS OF NUCLEAR REACTORS  

Science Journals Connector (OSTI)

Abstract A survey of the various aspects of safety and reliability analysis of nuclear reactors is presented with particular emphasis on the interrelation between structural reliability and systems reliability. In reactor design this interrelation is of overriding importance since it is the task of the control, protective and containment systems to protect the mechanical system and the structure from accidental overloading.

T.A. JAEGER

1972-01-01T23:59:59.000Z

107

Safety Analysis, Hazard and Risk Evaluations [Nuclear Waste Management  

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

108

GENII Guidance Document  

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

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.

109

Document  

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

110

Document Reviews  

Broader source: Energy.gov [DOE]

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...

111

Policy and Guidance Documents  

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

112

Document  

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

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]

113

Document  

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

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

114

Document  

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

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

115

Document  

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

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,

116

H:\\Transfer\\My Documents\\Cleary Fire Report\\Annual Fire Safety Report 2010.doc Annual Fire Safety Report  

E-Print Network [OSTI]

. Building Sprinkler System? % Sprinkler Monitored Fire Alarm? Smoke Detection Extinguisher Devices Placards of vehicle parts, fuel and oil is prohibited. l. Hallways must remain clear at all times for safety in case Safety Systems The following table describes each on-campus residential facility fire safety system

Sze, Lawrence

117

Document  

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

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

118

Document  

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

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

119

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

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

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

120

Document  

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

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

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.


121

Document  

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

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,

122

Document  

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

123

Document  

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

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/

124

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

125

Document  

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

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

126

Document  

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

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,

127

Document  

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

128

Document  

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

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

129

Document  

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

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

130

Document  

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

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

131

Document  

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

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

132

Document  

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

133

Document  

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

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.

134

Rankine bottoming cycle safety analysis. Final report  

SciTech Connect (OSTI)

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

135

Oak Ridge National Laboratory site data for safety-analysis report  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs.

Fitzpatrick, F.C.

1982-12-01T23:59:59.000Z

136

Hazard Analysis Database report  

SciTech Connect (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

137

242-A evaporator safety analysis report  

SciTech Connect (OSTI)

This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR.

CAMPBELL, T.A.

1999-05-17T23:59:59.000Z

138

Overheads, Safety Analysis and Engineering FY 1995 Site Support Program Plan WBS 6.3.5  

SciTech Connect (OSTI)

The Safety Analysis & Engineering (SA&E) department provides core competency for safety analysis and risk documentation that supports achievement of the goals and mission as described in the Hanford Mission Plan, Volume I, Site Guidance (DOE-RL 1993). SA&E operations are integrated into the programs that plan and conduct safe waste management, environmental restoration, and operational activities. SA&E personnel are key members of task teams assigned to eliminate urgent risks and inherent threats that exist at the Hanford Site. Key to ensuring protection of public health and safety, and that of onsite workers, are the products and services provided by the department. SA&E will continue to provide a leadership role throughout the DOE complex with innovative, cost-effective approaches to ensuring safety during environmental cleanup operations. The SA&E mission is to provide support to direct program operations through safety analysis and risk documentation and to maintain an infrastructure responsive to the evolutionary climate at the Hanford Site. SA&E will maintain the appropriate skills mix necessary to fulfill the customers need to conduct all operations in a safe and cost-effective manner while ensuring the safety of the public and the onsite worker.

DiVincenzo, E.P.

1994-09-27T23:59:59.000Z

139

Document  

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

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

140

Document:  

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

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

Document  

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

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

142

Document  

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

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

143

Document  

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

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;

144

Document  

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

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

145

Safety analysis of in-use vehicle wrapping cylinder  

Broader source: Energy.gov [DOE]

The focus of this presentation is on the security analysis for wrapped cylinders used in vehicles and analyzing safety conditions and environmental effects through testing.

146

Monthly Analysis of Electrical Safety Occurrences April 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

147

Monthly Analysis of Electrical Safety Occurrences March 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

148

Monthly Analysis of Electrical Safety Occurrences August 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

149

Monthly Analysis of Electrical Safety Occurrences November 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

150

Monthly Analysis of Electrical Safety Occurrences June 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

151

Monthly Analysis of Electrical Safety Occurrences April 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

152

Monthly Analysis of Electrical Safety Occurrences December 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

153

Monthly Analysis of Electrical Safety Occurrences July 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

154

Monthly Analysis of Electrical Safety Occurrences August 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

155

Monthly Analysis of Electrical Safety Occurrences May 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

156

Monthly Analysis of Electrical Safety Occurrences October 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

157

Monthly Analysis of Electrical Safety Occurrences September 2011  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

158

Monthly Analysis of Electrical Safety Occurrences October 2011  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

159

Monthly Analysis of Electrical Safety Occurrences September 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

160

Monthly Analysis of Electrical Safety Occurrences February 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

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

Monthly Analysis of Electrical Safety Occurrences June 2011  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

162

Monthly Analysis of Electrical Safety Occurrences May 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

163

Monthly Analysis of Electrical Safety Occurrences December 2011  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

164

Monthly Analysis of Electrical Safety Occurrences August 2011  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

165

Monthly Analysis of Electrical Safety Occurrences March 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

166

Monthly Analysis of Electrical Safety Occurrences July 2011  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

167

Monthly Analysis of Electrical Safety Occurrences September 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

168

Monthly Analysis of Electrical Safety Occurrences January 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

169

Monthly Analysis of Electrical Safety Occurrences July 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

170

Monthly Analysis of Electrical Safety Occurrences June 2013  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

171

Monthly Analysis of Electrical Safety Occurrences January 2012  

Broader source: Energy.gov [DOE]

An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

172

Comparison of Intergrated Safety Analysis (ISA) and Probabilistic...  

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

Commission Washington, DC 20555-0001 SUBJECT: COMPARISON OF INTEGRATED SAFETY ANALYSIS (ISA) AND PROBABILISTIC RISK ASSESSMENT (PRA) FOR FUEL CYCLE FACILITIES Dear Chairman...

173

Safety Analysis (SA) of the decontamination facility, Building 419, at the Lawrence Livermore National Laboratory  

SciTech Connect (OSTI)

This safety analysis was performed for the Manager, Plant Services at LLNL and fulfills the requirements of DOE Order 5481.1. The analysis was based on field inspections, document review, computer calculations, and extensive input from Waste Management personnel. It was concluded that the maximum quantities of radioactive materials that safety procedures allow to be handled in this building do not pose undue risks on- or off-site even in postulated severe accidents. Risk from the various hazards at this facility vary from low to moderate as specified in DOE Order 5481.1. Recommendations are made for improvements that will reduce risks even further.

Odell, B.N.

1980-06-17T23:59:59.000Z

174

Hazard screening application guide. Safety Analysis Report Update Program  

SciTech Connect (OSTI)

The basic purpose of hazard screening is to group precesses, facilities, and proposed modifications according to the magnitude of their hazards so as to determine the need for and extent of follow on safety analysis. A hazard is defined as a material, energy source, or operation that has the potential to cause injury or illness in human beings. The purpose of this document is to give guidance and provide standard methods for performing hazard screening. Hazard screening is applied to new and existing facilities and processes as well as to proposed modifications to existing facilities and processes. The hazard screening process evaluates an identified hazards in terms of the effects on people, both on-site and off-site. The process uses bounding analyses with no credit given for mitigation of an accident with the exception of certain containers meeting DOT specifications. The process is restricted to human safety issues only. Environmental effects are addressed by the environmental program. Interfaces with environmental organizations will be established in order to share information.

none,

1992-06-01T23:59:59.000Z

175

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

SciTech Connect (OSTI)

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

176

A Domain-Specific Safety Analysis for Digital Nuclear Plant Protection Systems  

E-Print Network [OSTI]

Tree Analysis), FMEA (Failure Mode and Effect Analysis), HAZOP (Hazard and Operability study). · Safety

177

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

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

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

178

Improving the Production and Presentation of Safety Cases through the use of Intranet Technology  

Science Journals Connector (OSTI)

A Safety Case requires that a large number of links are made between requirements, analysis and design documentation, and the safety analysis itself. Working in a paper based environment leads to a documentation ...

Rupert Brown

1998-01-01T23:59:59.000Z

179

Software FMEA analysis for safety-related application software  

Science Journals Connector (OSTI)

Abstract A method of a software safety analysis is described in this paper for safety-related application software. The target software system is a software code installed at an Automatic Test and Interface Processor (ATIP) in a digital reactor protection system (DRPS). For the ATIP software safety analysis, at first, an overall safety or hazard analysis is performed over the software architecture and modules, and then a detailed safety analysis based on the software FMEA (Failure Modes and Effect Analysis) method is applied to the ATIP program. For an efficient analysis, the software FMEA analysis is carried out based on the so-called failure-mode template extracted from the function blocks used in the function block diagram (FBD) for the ATIP software. The software safety analysis by the software FMEA analysis, being applied to the ATIP software code, which has been integrated and passed through a very rigorous system test procedure, is proven to be able to provide very valuable results (i.e., software defects) that could not be identified during various system tests.

Gee-Yong Park; Dong Hoon Kim; Dong Young Lee

2014-01-01T23:59:59.000Z

180

Oversight Documents | Department of Energy  

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

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

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

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

SciTech Connect (OSTI)

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

182

SAFETY ANALYSIS FOR TANK 241-AZ-101 MIXER PUMP PROCESS TEST  

SciTech Connect (OSTI)

This document contains the completed safety analysis which establishes the safety envelope for performing the mixer pump process test in Tank 241-AZ-101. This process test is described in TF-210-OTP-001. All equipment necessary for the mixer pump test has been installed by Project W-151. The purpose of this document is to describe and analyze the mixer pump test for Aging Waste Facility (AWF) Tank 241-AZ-101 and to address the 'yes/maybe' responses marked for evaluation questions identified in Unreviewed Safety Question Evaluation (USQE) TF-94-0266. The scope of this document is limited to the performance of the mixer pump test for Tank 241-AZ-101. Unreviewed Safety Question Determination (USQD) TF-96-0018 verified that the installation of two mixer pumps into Tank 241-AZ-101 was within the current Tank Waste Remediation System (TWRS) Authorization Basis. USQDs TF-96-0461, TF-96-0448, and TF-96-0805 verified that the installation of the in-tank video camera, thermocouples, and Ultrasonic Interface Level Analyzer (URSILLA), respectively, were within the current TWRS Authorization Basis. USQD TF-96-1041 verified that the checkout testing of the installed equipment was within the current TWRS Authorization Basis. Installation of the pumps and equipment has been completed. An evaluation of safety considerations associated with operation of the mixer pumps for the mixer pump test is provided in this document. This document augments the existing AWF authorization basis as defined in the Interim Safety Basis (Stahl 1997), and as such, will use the existing Interim Operational Safety Requirements (IOSRs) of Heubach 1996 to adequately control the mixer pump test. The hazard and accident analysis is limited to the scope and impact of the mixer pump test, and therefore does not address hazards already addressed by the current AWF authorization basis. This document does not evaluate removal of the mixer pumps. Safety considerations for removal of the pumps will be addressed by separate safety documentation once that portion of the mission is defined. The mixer pump test has been evaluated to cover the use of either the existing ventilation system (241-A-702) or the ventilation system upgrade provided by Project W-030. Analysis of Project W-030 is outside of the scope of this document and is addressed in HNF-SD-WM-SARR-039 (Draft) which, should the W-030 system be in service at the time of the mixer pump test, will have been approved and made a part of the TWRS authorization basis. The test will use two high-capacity mixer pumps in various configurations and modes to demonstrate solids mobilization of waste in Tank 241-AZ-101. The information and experience gained during the test will provide data for comparison with sludge mobilization prediction models; provide data to estimate the number, location, and cycle times of the mixer pumps; and provide indication of the effects of mixer pump operation on the AWF tank systems and components. The slurry produced will be evaluated for future pretreatment processing. This process test does not transfer waste from the tank; the waste is mixed and confined within the existing system. At the completion of the mixer pump test, the mixer pumps will be stopped and normal tank operations, maintenance, and surveillance will continue. Periodic rotation of the mixer pumps and motor shafts, along with bearing greasing, is required to maintain the pumps following the mixer pump test.

HAMMOND DM; HARRIS JP; MOUETTE P

1997-06-09T23:59:59.000Z

183

C:\\Documents and Settings\\lm.SU-4155CABB2178\\Desktop\\LabSafety\\SA04002 Evaluation.DOC Date: November 9, 2004  

E-Print Network [OSTI]

C:\\Documents and Settings\\lm.SU-4155CABB2178\\Desktop\\LabSafety\\SA04002 Evaluation.DOC Date cultures capable of producing Alpha-Hemolysin Toxin be possessed by Dr. #12;C:\\Documents and Settings\\lm

Movileanu, Liviu

184

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

SciTech Connect (OSTI)

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

185

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

......System for Research Reactor (IRSRR). Available...System for Research Reactor (IRSRR). Available...76. 7 Manual on reliability data collection for research reactor PSAs. (1992) IAEA...probabilistic safety analysis of incidents in nuclear......

Valdir Maciel Lopes; Gian Maria Agostinho Angelo Sordi; Mauricio Moralles; Tufic Madi Filho

2012-06-01T23:59:59.000Z

186

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

SciTech Connect (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

187

Criteria Review and Approach Documents | Department of Energy  

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

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

188

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

SciTech Connect (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

189

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

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

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

190

ASD Facility Hazard Analysis Document - Building 400-EAA  

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

191

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

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

<: <: 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

192

Assessment of the Performance of Fuzzy Cluster Analysis in the Classification of RFC Documents  

E-Print Network [OSTI]

on a relevance measure of other documents to the ones that are part of the defined tracks. The questionAssessment of the Performance of Fuzzy Cluster Analysis in the Classification of RFC Documents M. E of finding knowledge from meta-data. A collection of RFC documents has been used to analyse the behaviour

Haddadi, Hamed

193

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;Project Cost Escalation Standards, document IEAB 2007-2 Page 2 Third, managers are often asked to forecast

194

Facility Safety  

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

DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

2013-06-21T23:59:59.000Z

195

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.  

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

196

Software safety analysis of function block diagrams using fault trees , Junbeom Yoob,*, Sungdeok Chab  

E-Print Network [OSTI]

requirements written in natural language and performing safety analysis techniques such as FMEA [5] and HAZOP

197

Safety analysis for Shippingport Station Decommissioning Project. Vol. 9. Pt. 1. Rev. 1  

SciTech Connect (OSTI)

Information is presented concerning the safety analysis for the decommissioning project; and permitting plan.

Not Available

1983-09-01T23:59:59.000Z

198

Safety analysis report for packaging (onsite) steel drum  

SciTech Connect (OSTI)

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

199

Machine Learning for Digital Document Processing: From Layout Analysis To  

E-Print Network [OSTI]

Floriana Esposito1 , Stefano Ferilli1 , Teresa M.A. Basile1 , and Nicola Di Mauro1 Universit`a degli Studi and N. Di Mauro focused on principles and techniques for setting up and managing document collections

Di Mauro, Nicola

200

A new DOE standard for transuranic waste nuclear safety analysis  

SciTech Connect (OSTI)

The DOE Office of Environmental Management (EM) observed through onsite assessments and a review of site-specific lessons learned that transuranic (TRU) waste operations could benefit from standardization of assumptions and approaches used to analyze hazards and select controls. EM collected and compared safety analysis information from DOE sites, including a comparison of the type of TRU waste accidents evaluated and controls selected, as well as specific Airborne Release Fractions (ARFs), Respirable Fractions (RFs), and Damage Ratios (DRs) assumed in accident analyses. This paper recounts the efforts by the DOE and its contractors to bring consistency to the safety analysis process supporting TRU waste operations through an integrated re-engineering effort. EM embarked on a process to re-engineer and standardize TRU safety analysis activities complex-wide. The effort involved DOE headquarters, field offices, and contractors. Five teams were formed to analyze and develop the necessary technical basis for a DOE Technical Standard. The teams looked at general issues including Safety Basis (SB), drum integrity and inspection criteria, hazard controls and analysis, safety analysis review and approval process, and implementation of hazard controls. (authors)

Triay, I.; Chung, D. [U.S. Department of Energy, Washington, D.C. (United States); Woody, J. [Atlas Consulting, Knoxville, TN (United States); Foppe, T. [Carlsbad Technical Assistance Contractor, Carlsbad, NM (United States); Mewhinney, C. [Sandia National Laboratories, Carlsbad, NM (United States); Jennings, S. [Los Alamos National Laboratories, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

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

Safety Bulletin  

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

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.

202

RISMC ADVANCED SAFETY ANALYSIS WORKING PLAN FY 2015 FY 2019  

SciTech Connect (OSTI)

SUMMARY In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: 1. A value proposition (why is this important?) that will make the case for stakeholders use of the ASAP research and development (R&D) products. 2. An identification of likely end users and pathway to adoption of enhanced tools by the end-users. 3. A proposed set of practical and achievable use case demonstrations. 4. A proposed plan to address ASAP verification and validation (V&V) needs. 5. A proposed schedule for the multi-year ASAP.

Ronaldo H. Szilard; Curtis L. Smith

2014-09-01T23:59:59.000Z

203

Technical support document: Survey data used in revising the energy conservation requirements in the manufactured home construction and safety standards  

SciTech Connect (OSTI)

This report documents data used in the development of revised energy conservation standards for manufactured housing. The approach used in developing the proposed standard revision is a cost-benefit analysis in which the costs of energy conservation measures (ECM) are balanced against the benefits of energy savings. The analysis used to develop the recommendations for revision of the US Department of Housing and Urban Development (HUD) energy conservation standards for manufactured housing requires information on specific ECMs. This technical support document contains the data from two of the three surveys that were used primarily to characterize the available ECMs and their associated costs. The analyses of these data are provided in separate reports. 5 refs.

Lee, A.D.; Conner, C.C.

1992-02-01T23:59:59.000Z

204

System safety analysis of an autonomous mobile robot  

SciTech Connect (OSTI)

Analysis of the safety of operating and maintaining the Stored Waste Autonomous Mobile Inspector (SWAMI) II in a hazardous environment at the Fernald Environmental Management Project (FEMP) was completed. The SWAMI II is a version of a commercial robot, the HelpMate{trademark} robot produced by the Transitions Research Corporation, which is being updated to incorporate the systems required for inspecting mixed toxic chemical and radioactive waste drums at the FEMP. It also has modified obstacle detection and collision avoidance subsystems. The robot will autonomously travel down the aisles in storage warehouses to record images of containers and collect other data which are transmitted to an inspector at a remote computer terminal. A previous study showed the SWAMI II has economic feasibility. The SWAMI II will more accurately locate radioactive contamination than human inspectors. This thesis includes a System Safety Hazard Analysis and a quantitative Fault Tree Analysis (FTA). The objectives of the analyses are to prevent potentially serious events and to derive a comprehensive set of safety requirements from which the safety of the SWAMI II and other autonomous mobile robots can be evaluated. The Computer-Aided Fault Tree Analysis (CAFTA{copyright}) software is utilized for the FTA. The FTA shows that more than 99% of the safety risk occurs during maintenance, and that when the derived safety requirements are implemented the rate of serious events is reduced to below one event per million operating hours. Training and procedures in SWAMI II operation and maintenance provide an added safety margin. This study will promote the safe use of the SWAMI II and other autonomous mobile robots in the emerging technology of mobile robotic inspection.

Bartos, R.J.

1994-08-01T23:59:59.000Z

205

Motorway Safety in Europe and Greece: A Comparative Analysis  

Science Journals Connector (OSTI)

Motorways offer a high level of road safety as compared to other road types. In most EU member states, motorways represent a percentage of all primary and secondary roads varying between 1% and 12% (EU15). In Greece this figure has been significantly lower until 2004 and since then it has been sharply increased. Road safety levels have been also improved as a consequence of that. The paper provides a comparative analysis of motorway safety among Greece and the EU and furthermore among Greek motorways. To achieve this, it makes use of certain safety indicators such as fatality and accident rates. In addition, for the Greek motorways, it makes use of additional data which are available from the motorway operators data bases including incidents and their causes. Association of accidents to drivers behavior is sought where possible. Finally, a more in depth investigation takes place concerning accidents in the Greek motorways, mainly in the ATTICA TOLLWAY and in EGNATIA ODOS.

Dimitrios Papaioannou; Alexandros Kokkalis

2012-01-01T23:59:59.000Z

206

FAQS Gap Analysis Qualification Card Occupational Safety  

Broader source: Energy.gov [DOE]

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

207

Analysis of different approaches for storing GML documents  

Science Journals Connector (OSTI)

The fact that GML is an XML encoding allows it to be queried. In order to query a GML document we have designed a query language over GML/XML enriched with spatial operators. This query language has an underlying data model and algebra that supplies ... Keywords: GML, spatial queries

J. E. Crcoles; P. Gonzlez

2002-11-01T23:59:59.000Z

208

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

SciTech Connect (OSTI)

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

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

1981-03-03T23:59:59.000Z

209

COMPARATIVE SAFETY ANALYSIS DAT! 16 June 1972  

E-Print Network [OSTI]

thermal battery prematurely". The trees were developed down to events that could not be further developed in the safe arm slide timer and battery timer designs. The analysis shows the new timers do not, in fact (rachet release) design against the new (direct drive) design for both safe arm timer and battery timer

Rathbun, Julie A.

210

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

SciTech Connect (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

211

Nuclear criticality safety guide  

SciTech Connect (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

212

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

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

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

213

SCALE 6: Comprehensive Nuclear Safety Analysis Code System  

SciTech Connect (OSTI)

Version 6 of the Standardized Computer Analyses for Licensing Evaluation (SCALE) computer software system developed at Oak Ridge National Laboratory, released in February 2009, contains significant new capabilities and data for nuclear safety analysis and marks an important update for this software package, which is used worldwide. This paper highlights the capabilities of the SCALE system, including continuous-energy flux calculations for processing multigroup problem-dependent cross sections, ENDF/B-VII continuous-energy and multigroup nuclear cross-section data, continuous-energy Monte Carlo criticality safety calculations, Monte Carlo radiation shielding analyses with automated three-dimensional variance reduction techniques, one- and three-dimensional sensitivity and uncertainty analyses for criticality safety evaluations, two- and three-dimensional lattice physics depletion analyses, fast and accurate source terms and decay heat calculations, automated burnup credit analyses with loading curve search, and integrated three-dimensional criticality accident alarm system analyses using coupled Monte Carlo criticality and shielding calculations.

Bowman, Stephen M [ORNL

2011-01-01T23:59:59.000Z

214

Criterion Functions for Document Clustering Experiments and Analysis  

E-Print Network [OSTI]

on the Internet, digital libraries, news sources, and company-wide intranets. This has led to an increased different datasets, as well as an analysis of the characteristics of the various criterion functions

Karypis, George

215

Methods and criteria for safety analysis (FIN L2535)  

SciTech Connect (OSTI)

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.

Not Available

1992-12-01T23:59:59.000Z

216

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

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

217

Deconvolution of variability and uncertainty in the Cassini safety analysis  

SciTech Connect (OSTI)

The standard method for propagation of uncertainty in a risk analysis requires rerunning the risk calculation numerous times with model parameters chosen from their uncertainty distributions. This was not practical for the Cassini nuclear safety analysis, due to the computationally intense nature of the risk calculation. A less computationally intense procedure was developed which requires only two calculations for each accident case. The first of these is the standard 'best-estimate' calculation. In the second calculation, variables and parameters change simultaneously. The mathematical technique of deconvolution is then used to separate out an uncertainty multiplier distribution, which can be used to calculate distribution functions at various levels of confidence.

Kampas, Frank J.; Loughin, Stephen [Lockheed Martin Missiles and Space, P.O. Box 8555, Philadelphia, Pennsylvania 19101 (United States); WAM Systems, 650 Loraine Street, Ardmore, Pennsylvania 19003 (United States)

1998-01-15T23:59:59.000Z

218

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

SciTech Connect (OSTI)

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

219

FAQS Qualification Card - Criticality Safety | Department of Energy  

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

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

220

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

SciTech Connect (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

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

Safety Analysis of Requirements for a Product Family Robyn R. Lutz  

E-Print Network [OSTI]

Safety Analysis of Requirements for a Product Family Robyn R. Lutz Iowa State University and Jet, destatez@collins.rockwell.com Abstract A safety analysis was performed on the software re- quirements for a family of ight instrumentation dis- plays of commercial aircraft. First, an existing Safety Checklist

Lutz, Robyn R.

222

Safety Analysis of Requirements for a Product Family Robyn R. Lutz \\Lambda  

E-Print Network [OSTI]

Safety Analysis of Requirements for a Product Family Robyn R. Lutz \\Lambda Iowa State University and Communication srtockey, destatez@collins.rockwell.com Abstract A safety analysis was performed on the software, an existing Safety Checklist was extended to apply to four­variable models and used to analyze

Lutz, Robyn R.

223

Safety analysis of software product lines using state-based modeling q , Josh Dehlinger a  

E-Print Network [OSTI]

Safety analysis of software product lines using state-based modeling q Jing Liu a , Josh Dehlinger of managing variations and their potential interactions across an entire product line currently hinders safety analysis in safety-critical, software product lines. The work described here contributes to a solution

Lutz, Robyn R.

224

Department Safety Representatives Department Safety Representative  

E-Print Network [OSTI]

Department Safety Representatives Overview Department Safety Representative Program/Operations Guidance Document The Department Safety Representative (DSR) serves a very important role with implementation of safety, health, and environmental programs on campus. The role of the DSR is to assist

Pawlowski, Wojtek

225

Battery Lifetime Analysis and Simulation Tool (BLAST) Documentation  

SciTech Connect (OSTI)

The deployment and use of lithium-ion batteries in automotive and stationary energy storage applications must be optimized to justify their high up-front costs. Given that batteries degrade with use and storage, such optimizations must evaluate many years of operation. As the degradation mechanisms are sensitive to temperature, state-of-charge histories, current levels, and cycle depth and frequency, it is important to model both the battery and the application to a high level of detail to ensure battery response is accurately predicted. To address these issues, the National Renewable Energy Laboratory has developed the Battery Lifetime Analysis and Simulation Tool (BLAST) suite of tools. This suite of tools pairs NREL's high-fidelity battery degradation model with a battery electrical and thermal performance model, application-specific electrical and thermal performance models of the larger system (e.g., an electric vehicle), application-specific system use data (e.g., vehicle travel patterns and driving data), and historic climate data from cities across the United States. This provides highly realistic, long-term predictions of battery response and thereby enables quantitative comparisons of varied battery use strategies.

Neubauer, J.

2014-12-01T23:59:59.000Z

226

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

......errors, computational models (software), management, communication, safety culture, plant ageing, maintenance...Energy Power Plants Probability Radiation Monitoring Radiation Protection Radioactive Hazard Release Safety Management...

Valdir Maciel Lopes; Gian Maria Agostinho Angelo Sordi; Mauricio Moralles; Tufic Madi Filho

2012-06-01T23:59:59.000Z

227

DOE's Approach to Nuclear Facility Safety Analysis and Management  

Broader source: Energy.gov [DOE]

Presenter: Dr. James O'Brien, Director, Office of Nuclear Safety, Office of Health, Safety and Security, US Department of Energy

228

The Zion integrated safety analysis for NUREG-1150  

SciTech Connect (OSTI)

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

229

Fast Flux Test Facility final safety analysis report. Amendment 73  

SciTech Connect (OSTI)

This report provides Final Safety Analysis Report (FSAR) Amendment 73 for incorporation into the Fast Flux Test Facility (FFTR) FSAR set. This page change incorporates Engineering Change Notices (ECNs) issued subsequent to Amendment 72 and approved for incorparoration before May 6, 1993. These changes include: Chapter 3, design criteria structures, equipment, and systems; chapter 5B, reactor coolant system; chapter 7, instrumentation and control systems; chapter 9, auxiliary systems; chapter 11, reactor refueling system; chapter 12, radiation protection and waste management; chapter 13, conduct of operations; chapter 17, technical specifications; chapter 20, FFTF criticality specifications; appendix C, local fuel failure events; and appendix Fl, operation at 680{degrees}F inlet temperature.

Gantt, D.A.

1993-08-01T23:59:59.000Z

230

Enforcement Documents | Department of Energy  

Energy Savers [EERE]

Documents Enforcement Documents RSS December 2, 2014 Consent Order, Battelle Energy Alliance - NCO-2014-02 Nuclear Safety Enforcement Consent Order issued to Battelle Energy...

231

PHYSICS AND SAFETY ANALYSIS FOR THE NIST RESEARCH REACTOR.  

SciTech Connect (OSTI)

Detailed reactor physics and safety analyses have been performed for the 20 MW D{sub 2}O moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The analyses provide an update to the Final Safety Analysis Report (FSAR) and employ state-of-the-art calculational methods. Three-dimensional Monte Carlo neutron and photon transport calculations were performed with the MCNP code to determine the safety parameters for the NBSR. The core depletion and determination of the fuel compositions were performed with MONTEBURNS. MCNP calculations were performed to determine the beginning, middle, and end-of-cycle power distributions, moderator temperature coefficient, and shim safety arm, beam tube and void reactivity worths. The calculational model included a plate-by-plate description of each fuel assembly, axial mid-plane water gap, beam tubes and the tubular geometry of the shim safety arms. The time-dependent analysis of the primary loop was determined with a RELAP5 transient analysis model that includes the pump, heat exchanger, fuel element geometry, and flow channels for both the six inner and twenty-four outer fuel elements. The statistical analysis used to assure protection from critical heat flux (CHF) was performed using a Monte Carlo simulation of the uncertainties contributing to the CHF calculation. The power distributions used to determine the local fuel conditions and margin to CHF were determined with MCNP. Evaluations were performed for the following accidents: (1) the control rod withdrawal startup accident, (2) the maximum reactivity insertion accident, (3) loss-of-flow resulting from loss of electrical power, (4) loss-of-flow resulting from a primary pump seizure, (5) loss-of-flow resulting from inadvertent throttling of a flow control valve, (6) loss-of-flow resulting from failure of both shutdown cooling pumps and (7) misloading of a fuel element. In both the startup and maximum reactivity insertion accidents, the core power transient is terminated by a reactor trip at 26 MW. The calculations show that both the peak reactor power and the excursion energy depend on the negative reactivity insertion from reactor trip. In one of the loss-of-flow accidents offsite electrical power is assumed lost to the three operating primary pumps. A slightly delayed reactor scram is initiated as a result of primary flow coast down. The RELAP5 results indicate that there is adequate margin to CHF and no damage to the fuel will occur, because of the momentum of the coolant flowing through the fuel channels and the negative scram reactivity insertion. For both the primary pump seizure and inadvertent throttling of a flow control valve, the RELAP5 analyses indicate that the reduction in power following the trip is sufficient to ensure that there is adequate margin to CHF and that the fuel cladding does not fail. The analysis of the loss-of-flow accident in the extremely unlikely case where both shutdown pumps fail, shows that the cooling provided by the D{sub 2}O is sufficient to ensure the cladding does not fail. The power distributions were examined for a set of fuel misloadings in which a fresh fuel element is moved from a peripheral low-reactivity location to a central high-reactivity location. The calculations show that there is adequate margin to CHF and the cladding does not fail. An additional analysis was performed to simulate the operation at low power (500 kW) without forced flow cooling. The result indicates that natural convection cooling is adequate for operation of the NBSR at a power level of 500 kW.

CHENG,L.HANSON,A.DIAMOND,D.XU,J.CAREW,J.RORER,D.

2004-03-31T23:59:59.000Z

232

New enhancements to SCALE for criticality safety analysis  

SciTech Connect (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

233

Deconvolution of variability and uncertainty in the Cassini safety analysis  

SciTech Connect (OSTI)

The standard method for propagation of uncertainty in a risk analysis requires rerunning the risk calculation numerous times with model parameters chosen from their uncertainty distributions. This was not practical for the Cassini nuclear safety analysis, due to the computationally intense nature of the risk calculation. A less computationally intense procedure was developed which requires only two calculations for each accident case. The first of these is the standard {open_quotes}best-estimate{close_quotes} calculation. In the second calculation, variables and parameters change simultaneously. The mathematical technique of deconvolution is then used to separate out an uncertainty multiplier distribution, which can be used to calculate distribution functions at various levels of confidence. {copyright} {ital 1998 American Institute of Physics.}

Kampas, F.J. [Lockheed Martin Missiles and Space, P.O. Box 8555, Philadelphia, Pennsylvania 19101 (United States); Loughin, S. [WAM Systems, 650 Loraine Street, Ardmore, Pennsylvania 19003 (United States)

1998-01-01T23:59:59.000Z

234

Safety and Technical Services  

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

235

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.

236

Software Approach to Hazard Detection Using On-line Analysis of Safety Constraints  

E-Print Network [OSTI]

Software Approach to Hazard Detection Using On-line Analysis of Safety Constraints Beth Schroedey. The research here addresses the problem of enhancing software safety through hazard detection. The premise.gatech.edu Abstract Hazard situations in safety-critical systems are typically complex, so there is a need for means

Plale, Beth

237

A Conceptual Framework for Semantic Case-based Safety Analysis Olawande Daramola, Tor Stlhane  

E-Print Network [OSTI]

.biffl}@tuwien.ac.at Abstract Hazard and Operability (HAZOP) Analysis and Fail- ure Mode and Effect Analysis (FMEA) are among-based framework for safety analy- sis, which facilitates the reuse of previous HAZOP and FMEA experiences in order application. Key words: Safety analysis, HAZOP, FMEA, ontology, requirements, case-based reasoning, natural

238

Object Oriented Safety Analysis of an Extra High Voltage Substation Bay  

Science Journals Connector (OSTI)

Experiences of application of the object oriented approach to safety analysis of an extra high voltage substation bay are presented. As the first step...

Bartosz Nowicki; Janusz Grski

1998-01-01T23:59:59.000Z

239

Automation of System Safety Analysis: Possibilities and Pitfalls Andrew Galloway, University of York, Heslington, York YO10 5DD UK  

E-Print Network [OSTI]

evolved to support safety analysis work (in this paper, we use the term "safety analysis" to encompass all, safety engineers may only achieve closure at the end of a system's working life, when it is possibleAutomation of System Safety Analysis: Possibilities and Pitfalls Andrew Galloway, University

Pumfrey, David

240

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

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

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

Fault tree synthesis for software design analysis of PLC based safety-critical systems  

SciTech Connect (OSTI)

As a software verification and validation should be performed for the development of PLC based safety-critical systems, a software safety analysis is also considered in line with entire software life cycle. In this paper, we propose a technique of software safety analysis in the design phase. Among various software hazard analysis techniques, fault tree analysis is most widely used for the safety analysis of nuclear power plant systems. Fault tree analysis also has the most intuitive notation and makes both qualitative and quantitative analyses possible. To analyze the design phase more effectively, we propose a technique of fault tree synthesis, along with a universal fault tree template for the architecture modules of nuclear software. Consequently, we can analyze the safety of software on the basis of fault tree synthesis. (authors)

Koo, S. R.; Cho, C. H. [Corporate R and D Inst., Doosan Heavy Industries and Construction Co., Ltd., 39-3, Seongbok-Dong, Yongin-Si, Gyeonggi-Do 449-795 (Korea, Republic of); Seong, P. H. [Dept. of Nuclear and Quantum Engineering, Korea Advanced Inst. of Science and Technology, 373-3 Guseong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

2006-07-01T23:59:59.000Z

242

PHYSICS AND SAFETY ANALYSIS FOR THE NIST RESEARCH REACTOR.  

SciTech Connect (OSTI)

Detailed reactor physics and safety analyses have been performed for the 20 MW D{sub 2}O moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The analyses provide an update to the Final Safety Analysis Report (FSAR) and employ state-of-the-art calculational methods. Three-dimensional MCNP Monte Carlo neutron and photon transport calculations were performed to determine the safety parameters for the NBSR. The core depletion and determination of the fuel compositions were performed with MONTEBURNS. MCNP calculations were performed to determine the beginning, middle, and end-of-cycle power distributions, moderator temperature coefficient, and shim arm, beam tube and void reactivity worths. The calculational model included a plate-by-plate description of each fuel assembly, axial mid-plane water gap, beam tubes and the tubular geometry of the shim arms. The time-dependent analysis of the primary loop was determined with a RELAP5 transient analysis model including the pump, heat exchanger, fuel element geometry, and flow channels for both the six inner and twenty-four outer fuel elements. The statistical analysis used to assure protection from critical heat flux (CHF) was performed using a Monte Carlo simulation of the uncertainties contributing to the CHF calculation. The power distributions used to determine the local fuel conditions and margin to CHF were determined with MCNP. Evaluations were performed for the following accidents: (1) the control rod withdrawal startup accident, (2) the maximum reactivity insertion accident, (3) loss-of-flow resulting from loss of electrical power, (4) loss-of-flow resulting from a primary pump seizure, (5) loss-of-flow resulting from inadvertent throttling of a flow control valve, (6) loss-of-flow resulting from failure of both shutdown cooling pumps and (7) misloading of a fuel element. In both the startup and maximum reactivity insertion accidents, the core power transient is terminated by a reactor trip at 30 MW. The calculations show that both the peak reactor power and the excursion energy depend on the negative reactivity insertion from reactor trip. Two cases were considered for loss of electrical power. In the first case offsite power is lost, resulting in an immediate scram caused by loss of power to the control rod system. In the second case power is lost to only the three operating primary pumps, resulting in a slightly delayed scram when loss-of-flow is detected as the pumps coast down. In both instances, RELAP5 results indicate that there is adequate margin to CHF and no damage to the fuel will occur, because of the momentum of the coolant flowing through the fuel channels and the negative scram reactivity insertion. For both the primary pump seizure and inadvertent throttling of a flow control valve, the RELAP5 analyses indicate that the reduction in power following the trip is sufficient to ensure that there is adequate margin to CHF and the fuel cladding does not fail. The analysis of the loss-of-flow accident in the extremely unlikely case where both shutdown pumps fail shows that the cooling provided by the D{sub 2}O is sufficient to ensure the cladding does not fail. The power distributions were examined for a set of fuel misloadings in which a fresh fuel element is moved from a peripheral low-reactivity location to a central high-reactivity location. The calculations show that there is adequate margin to CHF and the cladding does not fail.

CAREW,J.CHENG,L.HANSON,AXU,J.RORER,D.DIAMOND,D.

2003-08-26T23:59:59.000Z

243

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

Office of Environmental Management (EM)

20-2005 Volume 1 of 2 April 2005 DOE STANDARD INTEGRATION OF ENVIRONMENT, SAFETY, AND HEALTH INTO FACILITY DISPOSITION ACTIVITIES Volume 1 of 2: Documented Safety Analysis for...

244

OF-FMEA: an approach to safety analysis of object-oriented software intensive systems  

Science Journals Connector (OSTI)

The paper presents an extension to the common FMEA method in such a way that it can be applied to safety analysis of systems (hardware and software) that are developed using a recently popular object oriented approach. The method makes use of the object ... Keywords: FMEA, formal analysis, safety critical systems

Tadeusz Cichocki; Janusz Grski

2003-01-01T23:59:59.000Z

245

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

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

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

246

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

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

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),

247

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

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

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),

248

Implementation Guide for Use in Developing Documented Safety Analyses to Meet Subpart B of 10 CFR 830  

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

Title 10 Code of Federal Regulations (CFR) Part 830, Subpart B, Safety Basis Requirements, requires the contractor responsible for a Department of Energy (DOE) nuclear facility to analyze the facility, the work to be performed, and the associated hazards and to identify the conditions, safe boundaries, and hazard controls necessary to protect workers, the public, and the environment from adverse consequences. Cancels DOE G 421.1-2.

2011-12-19T23:59:59.000Z

249

Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings  

SciTech Connect (OSTI)

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

250

Setting clear expectations for safety basis development  

SciTech Connect (OSTI)

DOE-RL has set clear expectations for a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (10 CFR 830, Nuclear Safety Rule) which will ensure long-term benefit to Hanford. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development resulting in a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was issued to standardized methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was issued for the evaluation of radiological consequences for accident scenarios often postulated for Hanford. A standard Site Documented Safety Analysis (DSA) detailing the safety management programs was issued for use as a means of compliance with a majority of 3009 Standard chapters. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. As a result of setting expectations and providing safety analysis tools, the four Hanford Site waste management nuclear facilities were able to integrate into one Master Waste Management Documented Safety Analysis (WM-DSA).

MORENO, M.R.

2003-05-03T23:59:59.000Z

251

A risk-informed approach to safety margins analysis  

SciTech Connect (OSTI)

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

252

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

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

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

253

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

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

254

Multi-Experts Analytic Hierarchy Process for the Sensitivity Analysis of Passive Safety Systems  

E-Print Network [OSTI]

Multi-Experts Analytic Hierarchy Process for the Sensitivity Analysis of Passive Safety Systems YU systems to increase their safety and reliability. However, during accidental scenarios, uncertainties Residual Heat Removal system (RHRs) of the High Temperature Reactor-Pebble Modular (HTR-PM). Key words

Paris-Sud XI, Université de

255

Aspects of environmental and safety analysis of fusion reactors  

E-Print Network [OSTI]

This report summarizes the progress made between October 1976 and September 1977 in studies of some environmental and safety considerations in fusion reactor plants. A methodology to assess the admissible occurrence rate ...

Kazimi, Mujid S.

1977-01-01T23:59:59.000Z

256

E-Print Network 3.0 - analysis documents volume Sample Search...  

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

Collection: Multidisciplinary Databases and Resources 15 AMIEDoT: An annotation model for document tracking and recommendation service Summary: or group of documents? Some of these...

257

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  

Broader source: Energy.gov [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,...

258

Hydrogen Safety Project chemical analysis support task: Window C'' volatile organic analysis  

SciTech Connect (OSTI)

This data package contains the results obtained by Pacific Northwest Laboratory (PNL) staff in the characterization of samples for the 101-SY Hydrogen Safety Project. The samples were submitted for analysis by Westinghouse Hanford Company (WHC) under the Technical Project Plan (TPP) 17667 and the Quality Assurance Plan MCS-027. They came from a core taken during Window C'' after the May 1991 gas release event. The analytical procedures required for analysis were defined in the Test Instructions (TI) prepared by the PNL 101-SY Analytical Chemistry Laboratory (ACL) Project Management Office in accordance with the TPP and the QA Plan. The requested analysis for these samples was volatile organic analysis. The quality control (QC) requirements for each sample are defined in the Test Instructions for each sample. The QC requirements outlined in the procedures and requested in the WHC statement of work were followed.

Gillespie, B.M.; Stromatt, R.W.; Ross, G.A.; Hoope, E.A.

1992-01-01T23:59:59.000Z

259

Hydrogen Safety Project chemical analysis support task: Window ``C`` volatile organic analysis  

SciTech Connect (OSTI)

This data package contains the results obtained by Pacific Northwest Laboratory (PNL) staff in the characterization of samples for the 101-SY Hydrogen Safety Project. The samples were submitted for analysis by Westinghouse Hanford Company (WHC) under the Technical Project Plan (TPP) 17667 and the Quality Assurance Plan MCS-027. They came from a core taken during Window ``C`` after the May 1991 gas release event. The analytical procedures required for analysis were defined in the Test Instructions (TI) prepared by the PNL 101-SY Analytical Chemistry Laboratory (ACL) Project Management Office in accordance with the TPP and the QA Plan. The requested analysis for these samples was volatile organic analysis. The quality control (QC) requirements for each sample are defined in the Test Instructions for each sample. The QC requirements outlined in the procedures and requested in the WHC statement of work were followed.

Gillespie, B.M.; Stromatt, R.W.; Ross, G.A.; Hoope, E.A.

1992-01-01T23:59:59.000Z

260

340 waste handling facility interim safety basis  

SciTech Connect (OSTI)

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

VAIL, T.S.

1999-04-01T23:59:59.000Z

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.


261

340 Waste handling facility interim safety basis  

SciTech Connect (OSTI)

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

Stordeur, R.T.

1996-10-04T23:59:59.000Z

262

SAFETY ANALYSIS AND INTEGRATION FOR ROBOTIC SYSTEMS -APPLICATION TO A  

E-Print Network [OSTI]

Analysis (FMEA) and Fault Tree Analysis (FTA) which identify potential unit errors resulting in hazards

Guiochet, Jérémie

263

Electrical Safety - Monthly Analyses of Electrical Safety Occurrences  

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

264

Use of Fault Tree Analysis for Automotive Reliability and Safety Analysis  

SciTech Connect (OSTI)

Fault tree analysis (FTA) evolved from the aerospace industry in the 1960's. A fault tree is deductive logic model that is generated with a top undesired event in mind. FTA answers the question, ''how can something occur?'' as opposed to failure modes and effects analysis (FMEA) that is inductive and answers the question, ''what if?'' FTA is used in risk, reliability and safety assessments. FTA is currently being used by several industries such as nuclear power and chemical processing. Typically the automotive industries uses failure modes and effects analysis (FMEA) such as design FMEAs and process FMEAs. The use of FTA has spread to the automotive industry. This paper discusses the use of FTA for automotive applications. With the addition automotive electronics for various applications in systems such as engine/power control, cruise control and braking/traction, FTA is well suited to address failure modes within these systems. FTA can determine the importance of these failure modes from various perspectives such as cost, reliability and safety. A fault tree analysis of a car starting system is presented as an example.

Lambert, H

2003-09-24T23:59:59.000Z

265

CORCON-MOD1 preliminary evaluation and application to safety analysis of a large LMFBR plant  

SciTech Connect (OSTI)

The CORCON-MOD1 core material-concrete interaction code, developed at the Sandia Laboratories for LWR safety analysis, was adapted for analyzing a postulated LMFBR core melt accident.

Chen, K.H.; Ray, K.S.

1981-06-30T23:59:59.000Z

266

Fuzzy Failure Rate for Nuclear Power Plant Probabilistic Safety Assessment by Fault Tree Analysis  

Science Journals Connector (OSTI)

Reliability data is essential for a nuclear power plant probabilistic safety assessment by fault tree analysis ... a failure possibility-based reliability algorithm to assess nuclear event reliability data from f...

Julwan Hendry Purba; Jie Lu; Guangquan Zhang

2012-01-01T23:59:59.000Z

267

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

SciTech Connect (OSTI)

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

268

Development of a safety analysis system for the offshore personnel and equipment transfer process  

E-Print Network [OSTI]

and Effect Analysis (FMEA) was performed. With the FMEA the question "What if?" is asked for each component. For example, "What if the lifting cable fails' ?". Each component was evaluated for failure mode, failure effects on other components... swell or waves stood out as primary factors in the safety of the transfer process. Failure Mode and Effect Anal sis With component failure a recognized factor in the safety of the transfer process, more in-depth analysis was merited. The FMEA...

McKenna, Michael George

2012-06-07T23:59:59.000Z

269

Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports  

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

he purpose of this DOE Standard is to establish guidance for the preparation and review of hazard categorization and accident analyses techniques as required in DOE Order 5480.23, Nuclear Safety Analysis Reports.

1997-12-12T23:59:59.000Z

270

Formal Safety analysis of a radiobased railroad crossing using Deductive CauseConsequence  

E-Print Network [OSTI]

#ects analysis (FMEA) and fault tree analysis (FTA). We apply the method to a real world case study: a radio (DCCA). This technique is a formal generalization of well­known safety analysis methods like FMEA [10 by analyzed) than traditional FMEA. We show, that the results of DCCA have the same semantics as those

Reif, Wolfgang

271

A semiotic analysis of biotechnology and food safety photographs  

E-Print Network [OSTI]

This study evaluated photographs used in Time, Newsweek, and U.S. News and World Report in stories about biotechnology and food safety issues from the years 2000 and 2001. This study implemented a semiotic methodology to determine if the messages...

Norwood, Jennifer Lynn

2006-04-12T23:59:59.000Z

272

OCCUPATIONAL & ENVIRONMENTAL SAFETY SERVICES C:\\Documents and Settings\\sysdev\\Local Settings\\Temporary Internet Files\\OLK412\\Lab Equipment Release -New Format.doc  

E-Print Network [OSTI]

, autoclaves, centrifuges, refrigerators, freezers, incubators, BioSafety cabinets, and analytical equipment, refrigerators, freezers, incubators, etc. #12;OCCUPATIONAL & ENVIRONMENTAL SAFETY SERVICES C

Krovi, Venkat

273

Surveillance Guide - NSS 18.3 Verification of Authorization Basis Documentation  

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

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

274

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

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

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

275

Conventional Facilities Chapter 11: Environment, Safety and Health 11-1 NSLS-II Preliminary Design Report  

E-Print Network [OSTI]

Analysis 4. Fire Protection 5. Pressure Safety 6. Industrial Hygiene 7. Other ES&H Issues This document, the more stringent requirement will govern. 11.3.1 DOE O 420.1B ­ Facility Safety a) Fire protection system Program a) Fire protection b) Pressure safety c) Industrial hygiene d) Biological safety e) Electrical

Ohta, Shigemi

276

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

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

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,

277

Safety, Dependability and Performance Analysis of Extended AADL Models  

Science Journals Connector (OSTI)

......analysis Failure mode and effects analysis (FMEA) and fault tree analysis (FTA), model...Wesupporttwopopularhazardanalysistechniques:FMEA and FTA. Both techniques are realized...symbolic model checking [33, 34]. (i) FMEA is an inductive technique that starts by......

Marco Bozzano; Alessandro Cimatti; Joost-Pieter Katoen; Viet Yen Nguyen; Thomas Noll; Marco Roveri

2011-05-01T23:59:59.000Z

278

Integrating Safety into Design and Construction | Department...  

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

Integrating Safety into Design and Construction Integrating Safety into Design and Construction DepSecMemoIntegratingSafetyInDesignAndConstruction05Dec2005.pdf More Documents &...

279

Commercial Vehicle Safety Alliance | Department of Energy  

Office of Environmental Management (EM)

Commercial Vehicle Safety Alliance Commercial Vehicle Safety Alliance Commercial Vehicle Safety Alliance More Documents & Publications North American Standard Level VI Inspection...

280

FAQS JOB TASK ANALYSIS - Electrical Systems and Safety Oversight  

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

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

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

Implementation Guide for Use in Developing Technical Safety Requirements  

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

This Guide provides elaboration for the content of TSRs. Section 10 CFR 830.205 of the Nuclear Safety Management rule, requires Department of Energy (DOE) contractors responsible for category 1, 2, and 3 DOE nuclear facilities to develop Technical Safety Requirements (TSRs). These TSRs identify the limitations to each DOE owned, contractor operated nuclear facility based on the documented safety analysis (DSA) and any additional safety requirements established for the facility. Does not cancel other directives.

2010-11-03T23:59:59.000Z

282

Implementation Guide for Use in Developing Technical Safety Requirements  

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

This Guide provides elaboration for the content of TSRs. Section 10 CFR 830.205 of the Nuclear Safety Management rule, requires Department of Energy (DOE) contractors responsible for category 1, 2, and 3 DOE nuclear facilities to develop Technical Safety Requirements (TSRs). These TSRs identify the limitations to each DOE owned, contractor operated nuclear facility based on the documented safety analysis (DSA) and any additional safety requirements established for the facility. Cancels DOE G 423.1-1.

2010-11-03T23:59:59.000Z

283

Final report for confinement vessel analysis. Task 2, Safety vessel impact analyses  

SciTech Connect (OSTI)

This report describes two sets of finite element analyses performed under Task 2 of the Confinement Vessel Analysis Program. In each set of analyses, a charge is assumed to have detonated inside the confinement vessel, causing the confinement vessel to fail in either of two ways; locally around the weld line of a nozzle, or catastrophically into two hemispheres. High pressure gases from the internal detonation pressurize the inside of the safety vessel and accelerate the fractured nozzle or hemisphere into the safety vessel. The first set of analyses examines the structural integrity of the safety vessel when impacted by the fractured nozzle. The objective of these calculations is to determine if the high strength bolt heads attached to the nozzle penetrate or fracture the lower strength safety vessel, thus allowing gaseous detonation products to escape to the atmosphere. The two dimensional analyses predict partial penetration of the safety vessel beneath the tip of the penetrator. The analyses also predict maximum principal strains in the safety vessel which exceed the measured ultimate strain of steel. The second set of analyses examines the containment capability of the safety vessel closure when impacted by half a confinement vessel (hemisphere). The predicted response is the formation of a 0.6-inch gap, caused by relative sliding and separation between the two halves of the safety vessel. Additional analyses with closure designs that prevent the gap formation are recommended.

Murray, Y.D. [APTEK, Inc., Colorado Springs, CO (United States)

1994-01-26T23:59:59.000Z

284

Ferrocyanide safety program: Thermal analysis of ferrocyanide tanks, Group I  

SciTech Connect (OSTI)

The purpose of this report is to document the results of a series of analyses conducted to the heat loads of the first of two groups of tanks on the Ferrocyanide Watch List. The analyses use the fill/transfer history with a transient solution for the heat load determination. Nominal values of the heat load are determined, as well as the upper lower bounds of the heat load. Ranges of thermal conductivity of the tank waste are determined.

McLaren, J.M.

1994-06-01T23:59:59.000Z

285

Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counter Examples  

E-Print Network [OSTI]

Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counter Examples Failure mode and effects analysis (FMEA) is a technique to reason about possible system hazards that result from system or system component failures. Traditionally, FMEA does not take the probabilities

Leue, Stefan

286

Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counterexamples  

E-Print Network [OSTI]

Safety Analysis of an Airbag System using Probabilistic FMEA and Probabilistic Counterexamples H analysis (FMEA) is a technique to reason about possible system hazards that result from system or system component failures. Tradition- ally, FMEA does not take the probabilities with which these failures may

Leue, Stefan

287

Development of SRC-I product analysis. Volume 3. Documentation of procedures  

SciTech Connect (OSTI)

This section documents the BASIC computer program written to simulate Wilsonville's GC-simulated distillation (GCSD) results at APCI-CRSD Trexlertown. The GC conditions used at APCI for the Wilsonville GCSD analysis of coal-derived liquid samples were described in the SRC-I Quarterly Technical Report, April-June 1981. The approach used to simulate the Wilsonville GCSD results is also from an SRC-I Quarterly Technical Report and is reproduced in Appendix VII-A. The BASIC computer program is described in the attached Appendix VII-B. Analysis of gases produced during coal liquefaction generates key information needed to determine product yields for material balance and process control. Gas samples from the coal process development unit (CPDU) and tubing bombs are the primary samples analyzed. A Carle gas chromatographic system was used to analyze coal liquefaction gas samples. A BASIC computer program was written to calculate the gas chromatographic peak area results into mole percent results. ICRC has employed several analytical workup procedures to determine the amount of distillate, oils, asphaltenes, preasphaltenes, and residue in SRC-I process streams. The ASE procedure was developed using Conoco's liquid column fractionation (LC/F) method as a model. In developing the ASE procedure, ICRC was able to eliminate distillation, and therefore quantify the oils fraction in one extraction step. ASE results were shown to be reproducible within +- 2 wt %, and to yield acceptable material balances. Finally, the ASE method proved to be the least affected by sample composition.

Schweighardt, F.K.; Kingsley, I.S.; Cooper, F.E.; Kamzelski, A.Z.; Parees, D.M.

1983-09-01T23:59:59.000Z

288

Analysis of Fundamental NIST Sphere Experiments Related to Criticality Safety  

SciTech Connect (OSTI)

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

289

System Design and the Safety Basis  

SciTech Connect (OSTI)

The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination & decommissioning (D&D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities.

Ellingson, Darrel

2008-05-06T23:59:59.000Z

290

Station Blackout: A case study in the interaction of mechanistic and probabilistic safety analysis  

SciTech Connect (OSTI)

The ability to better characterize and quantify safety margins is important to improved decision making about nuclear power plant design, operation, and plant life extension. As research and development (R&D) in the light-water reactor (LWR) Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway R&D is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a station blackout wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario.

Curtis Smith; Diego Mandelli; Cristian Rabiti

2013-11-01T23:59:59.000Z

291

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

SciTech Connect (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

292

FAQS Gap Analysis Qualification Card Nuclear Safety Specialist  

Broader source: Energy.gov [DOE]

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

293

A documented analysis of renewable energy related research and development in Mexico  

Science Journals Connector (OSTI)

The research and development of renewable energy sources in Mexico has recently started to be considered as a form of contributing to solve the environmental problems caused by the irrational use of fossil fuels to meet the human and industrial energy requirements. The major areas of renewable energy research in Mexico are solar thermal energy, photovoltaic energy, wind energy, geothermal energy, materials for renewable energy, energy planning and economy and lately new programs such as hydrogen energy, fuel cells, etc. In Mexico, there are many important institutions such as universities, research centers and industries working on research, development and analysis of renewable energy sources. The industrial involvement is comparatively less in this kind of research. In this work we present results from a documented, statistical and analytical research carried out on the renewable energy related research and development activities in various important Mexican research and development institutions. Many factors affecting the complete understanding of the research and development of renewable energy sources are presented in this paper.

Ana Mar??a Ram??rez; P.J Sebastian; S.A Gamboa; M.A Rivera; O Cuevas; J Campos

2000-01-01T23:59:59.000Z

294

Office of Environmental Protection, Sustainability Support, and Corporate Safety Analysis  

Broader source: Energy.gov [DOE]

The Office of Environmental Protection, Sustainability Support and Analysis establishes environmental protection requirements and expectations for the Department to ensure protection of workers and the public and protection of the environment from the hazards associated with all Department operations.

295

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

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

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.

296

Functional reliability analysis of Safety Grade Decay Heat Removal System of Indian 500MWe PFBR  

Science Journals Connector (OSTI)

Passive systems are increasingly deployed in nuclear industry with an objective of increasing reliability and safety of operations with reduced cost. Methods for assessing the reliability of thermalhydraulic passive systems, that is systems with moving working fluid, address the issues in natural buoyancy-driven flow that could result in a failure to meet the design safety limits under accident scenarios. This is referred as design functional reliability. This paper presents the results of functional reliability analysis carried out for the passive Safety Grade Decay Heat Removal System (SGDHRS) of Indian Prototype Fast Breeder Reactor (PFBR). The analysis is carried out based on the overall approach reported in the Reliability Methods for Passive System (RMPS, European Commission) project. Functional failure probability is calculated using Monte-Carlo method and also with method of moments.

T. Sajith Mathews; M. Ramakrishnan; U. Parthasarathy; A. John Arul; C. Senthil Kumar

2008-01-01T23:59:59.000Z

297

Tank farms criticality safety manual  

SciTech Connect (OSTI)

This document defines the Tank Farms Contractor (TFC) criticality safety program, as required by Title 10 Code of Federal Regulations (CFR), Subpart 830.204(b)(6), ''Documented Safety Analysis'' (10 CFR 830.204 (b)(6)), and US Department of Energy (DOE) 0 420.1A, Facility Safety, Section 4.3, ''Criticality Safety.'' In addition, this document contains certain best management practices, adopted by TFC management based on successful Hanford Site facility practices. Requirements in this manual are based on the contractor requirements document (CRD) found in Attachment 2 of DOE 0 420.1A, Section 4.3, ''Nuclear Criticality Safety,'' and the cited revisions of applicable standards published jointly by the American National Standards Institute (ANSI) and the American Nuclear Society (ANS) as listed in Appendix A. As an informational device, requirements directly imposed by the CRD or ANSI/ANS Standards are shown in boldface. Requirements developed as best management practices through experience and maintained consistent with Hanford Site practice are shown in italics. Recommendations and explanatory material are provided in plain type.

FORT, L.A.

2003-03-27T23:59:59.000Z

298

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

SciTech Connect (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

299

NASA/TM-2007-214856 Safety and Performance Analysis of the  

E-Print Network [OSTI]

March 2007 NASA/TM-2007-214856 Safety and Performance Analysis of the Non-Radar Oceanic National Institute of Aerospace, Hampton, Virginia #12;The NASA STI Program Office . . . in Profile Since its founding, NASA has been dedicated to the advancement of aeronautics and space science. The NASA

Muñoz, César A.

300

NASA/TM-2009-215768 A Mathematical Basis for the Safety Analysis of  

E-Print Network [OSTI]

June 2009 NASA/TM-2009-215768 A Mathematical Basis for the Safety Analysis of Conflict Prevention, Virginia Gilles Dowek Ecole Polytechnique, France #12;NASA STI Program . . . in Profile Since its founding, NASA has been dedicated to the advancement of aeronautics and space science. The NASA scientific

Maddalon, Jeffrey M.

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

Combining Functional and Structural Reasoning for Safety Analysis of Electrical Designs  

E-Print Network [OSTI]

in detail. FLAME has been developed over several years, and is capable of composing an FMEA report for many Failure mode effects analysis (FMEA) of a design involves the investigation and assessment of the effects, electronic and mechanical systems are being combined in safety-critical applications. Automation of FMEA

Snooke, Neal

302

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...

Akboy, Serra

2012-02-14T23:59:59.000Z

303

Coiled Tubing Safety Manual  

SciTech Connect (OSTI)

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

304

Waste Tank Organic Safety Project: Analysis of liquid samples from Hanford waste tank 241-C-103  

SciTech Connect (OSTI)

A suite of physical and chemical analyses has been performed in support of activities directed toward the resolution of an Unreviewed Safety Question concerning the potential for a floating organic layer in Hanford waste tank 241-C-103 to sustain a pool fire. The analysis program was the result of a Data Quality Objectives exercise conducted jointly with staff from Westinghouse Hanford Company and Pacific Northwest Laboratory (PNL). The organic layer has been analyzed for flash point, organic composition including volatile organics, inorganic anions and cations, radionuclides, and other physical and chemical parameters needed for a safety assessment leading to the resolution of the Unreviewed Safety Question. The aqueous layer underlying the floating organic material was also analyzed for inorganic, organic, and radionuclide composition, as well as other physical and chemical properties. This work was conducted to PNL Quality Assurance impact level III standards (Good Laboratory Practices).

Pool, K.H.; Bean, R.M.

1994-03-01T23:59:59.000Z

305

Packaging review guide for reviewing safety analysis reports for packagings: Revision 1  

SciTech Connect (OSTI)

The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. The principal purpose of this document is to assure the quality and uniformity of PCS reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The Packaging Review Guide (PRG) also sets forth solutions and approaches determined to be acceptable in the past in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented. It is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 77 refs., 16 figs., 15 tabs.

Fisher, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

1988-10-01T23:59:59.000Z

306

Complete Safety Training  

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

307

Complete Safety Training  

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

308

Complete Safety Training  

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

309

Reactor Safety Planning for Prometheus Project, for Naval Reactors Information  

SciTech Connect (OSTI)

The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

P. Delmolino

2005-05-06T23:59:59.000Z

310

A case study on effectiveness of structural reliability analysis in nuclear reactor safety assessment  

Science Journals Connector (OSTI)

Problems on reliability of structural integrity occupy an important position in various aspects of nuclear reactor safety. In the present paper, an effective method for quantitative evaluation of structural reliability based on stress strength model is developed with the objectives of taking a larger number of factors into the evaluation than before and giving useful results within moderate computing time. The method is applied to the reliability analysis of PWR pressure vessels. The results show the relative importance of inspection as well as the parameter uncertainty for assuring the reliability of the structure, although analysis is limited within the scope of linear elastic fracture mechanics (LEFM). This case study also shows that the analysis of structural reliability is effective for safety assessment of nuclear power plants in general and possibly for the improvements of the consistency in the design code.

A. Yamaguchi; S. Kondo; Y. Togo

1983-01-01T23:59:59.000Z

311

Criticality safety analysis of a borated-concrete absorber  

SciTech Connect (OSTI)

Fuel cycle facilities use slab tanks to store fissile solutions, because these tanks have both a high volume-to-floorspace efficiency and an easily verifiable, criticality control (thickness). The results of preliminary criticality analyses using a validated computer code and cross-section library, indicate that a slab tank designed without a solid neutron absorber is not economical in view of process requirements (inventory) and space limitations (layout). A subsequent calculational study assessed the possible increase in the thickness of a single, isolated slab tank using a solid neutron absorber. Finally, an analysis was performed to evaluate the maximum slab thickness for an array of tank/absorbers. The result of these studies showed the potential for expansion of slab tank thickness. 7 refs., 5 figs., 7 tabs.

Funabashi, H.; Oka, T.; Matsumoto, T.; Smolen, G.R. (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan); Oak Ridge National Lab., TN (USA))

1989-01-01T23:59:59.000Z

312

Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports  

SciTech Connect (OSTI)

At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRCs assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978 and 1988. All of the reports reviewed were the regulators assessment of the PSR findings rather than the original PSR report, and all but one were English translations from the original language. In these reviews, it was found that most of the countries base their regulatory guidance to some extent (and often to a large extent) on U.S. design codes and standards, NRC regulatory guidance, and U.S. industry guidance. In addition, many of the observed operational technical issues and OpE events reported for U.S. reactors are also cited in the PSR reports. The PSR reports also identified a number of potential technical material/component performance issues and OpE events that are not commonly reported for U.S. plants.

Chopra, Omesh K. [Argonne National Lab., IL (United States). Environmental Science Division; Diercks, Dwight R. [Argonne National Lab., IL (United States). Nuclear Engineering Division; Ma, David Chia-Chiun [Argonne National Lab., IL (United States). Environmental Science Division; Garud, Yogendra S. [Argonne National Lab., IL (United States). Environmental Science Division

2013-12-17T23:59:59.000Z

313

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

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

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

314

A probabilistic safety analysis of UF{sub 6} handling at the Portsmouth Gaseous Diffusion Plant  

SciTech Connect (OSTI)

A probabilistic safety study of UF{sub 6} handling activities at the Portsmouth Gaseous Diffusion Plant has recently been completed. The analysis provides a unique perspective on the safety of UF{sub 6} handling activities. The estimated release frequencies provide an understanding of current risks, and the examination of individual contributors yields a ranking of important plant features and operations. Aside from the probabilistic results, however, there is an even more important benefit derived from a systematic modeling of all operations. The integrated approach employed in the analysis allows the interrelationships among the equipment and the required operations to be explored in depth. This paper summarizes the methods used in the study and provides an overview of some of the technical insights that were obtained. Specific areas of possible improvement in operations are described.

Boyd, G.J.; Lewis, S.R.; Summitt, R.L. [Safety and Reliability Optimization Services (SAROS), Inc., Knoxville, TN (United States)

1991-12-31T23:59:59.000Z

315

H2 Safety Snapshot - Vol. 2, Issue 2, July 2011 | Department...  

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

2, July 2011 H2 Safety Snapshot - Vol. 2, Issue 2, July 2011 This third issue describes hazard analysis in H2 facility design and operations. h2snapshotv2i2.pdf More Documents &...

316

Laser Safety and Hazardous Analysis for the ARES (Big Sky) Laser System  

SciTech Connect (OSTI)

A laser safety and hazard analysis was performed for the ARES laser system based on the 2000 version of the American National Standards Institute's (ANSI) Standard Z136.1,for Safe Use of Lasers and the 2000 version of the ANSI Standard Z136.6, for Safe Use of Lasers Outdoors. The ARES laser system is a Van/Truck based mobile platform, which is used to perform laser interaction experiments and tests at various national test sites.

AUGUSTONI, ARNOLD L.

2003-01-01T23:59:59.000Z

317

Safety analysis report for packaging, onsite, long-length contaminated equipment transport system  

SciTech Connect (OSTI)

This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks.

McCormick, W.A.

1997-05-09T23:59:59.000Z

318

E-Print Network 3.0 - accident analysis documentation Sample...  

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

and Data Analysis, 2000). This has... Research Record 1487, 68-74. Grder, P., 1994. Bicycle accidents in Maine: an analysis. Transportation... at signalized intersections,...

319

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

SciTech Connect (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

320

Document Reviews | Department of Energy  

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

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.

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

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

SciTech Connect (OSTI)

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

322

Development of Guidance for Analysis of Beyond Design Basis Events |  

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

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

323

Safety and Training | Advanced Photon Source  

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

Transportation Safety Waste Handling APS: (see also: centraldocs.aps.anl.gov) Conduct of Operations Manual PDF Managing Minor Work Projects PDF Safety Assessment Document (SAD)...

324

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

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

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

325

Organic Tanks Safety Program: Advanced organic analysis FY 1996 progress report  

SciTech Connect (OSTI)

Major focus during the first part of FY96 was to evaluate using organic functional group concentrations to screen for energetics. Fourier transform infrared and Raman spectroscopy would be useful screening tools for determining C-H and COO- organic content in tank wastes analyzed in a hot cell. These techniques would be used for identifying tanks of potential safety concern that may require further analysis. Samples from Tanks 241-C-106 and -C-204 were analyzed; the major organic in C-106 was B2EHPA and in C-204 was TBP. Analyses of simulated wastes were also performed for the Waste Aging Studies Task; organics formed as a result of degradation were identified, and the original starting components were monitored quantitatively. Sample analysis is not routine and required considerable methods adaptation and optimization. Several techniques have been evaluated for directly analyzing chelator and chelator fragments in tank wastes: matrix-assisted laser desorption/ionization time-of-flight mass spectrometry and liquid chromatography with ultraviolet detection using Cu complexation. Although not directly funded by the Tanks Safety Program, the success of these techniques have implications for both the Flammable Gas and Organic Tanks Safety Programs.

NONE

1996-09-01T23:59:59.000Z

326

Senior Technical Safety Manager Qualification Program Self-Assessment -  

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

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

327

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

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

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

328

Lawrence Livermore National Laborotory Safety Basis Assessment...  

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

in the WSF safety basis. The comprehensive review used a criteria and review approach document to guide the reviewers and examined documentation of controls and their...

329

CACI: The Cesium-137 Agricultural Commodities Irradiator. Final design report: Volume 7, Safety analysis, thermal analysis, and thermal testing  

SciTech Connect (OSTI)

This report provides a complete description of the final detailed design of the Cesium-137 Agricultural Commodities Irradiator (CACI). The design was developed and successfully completed by the Rocketdyne Division of Rockwell International for the US Department of Energy (DOE). The CACI project was initiated in April 1985 under DOE`s Byproducts Utilization Program, with the objectives of transferring food irradiation technology to the industry and thereby demonstrating a beneficial use for the 137 Cs nuclear by-product isotope. As designed, CACI will meet the intended requirements for research, development, and demonstration of irradiation processing of food. Further, as shown in the safety analyses performed during the project, the design conforms to all the safety and licensing requirements set forth for the project. The original scope of the CACI project included completion of its construction. However, the project was terminated for the convenience of the government during the final design phase in February 1986 for lack of a specific site. The CACI final design is described in eight volumes. This volume, Volume VII, describes Safety Analysis, Thermal Analysis, and Thermal Testing.

Not Available

1986-12-19T23:59:59.000Z

330

Reliability analysis of safety grade decay heat removal system of Indian prototype fast breeder reactor  

Science Journals Connector (OSTI)

The 500MW Indian pool type Prototype Fast Breeder Reactor (PFBR), is provided with two independent and diverse Decay Heat Removal (DHR) systems viz., Operating Grade Decay Heat Removal System (OGDHRS) and Safety Grade Decay Heat Removal System (SGDHRS). OGDHRS utilizes the secondary sodium loops and SteamWater System with special decay heat removal condensers for DHR function. The unreliability of this system is of the order of 0.10.01. The safety requirements of the present generation of fast reactors are very high, and specifically for DHR function the failure frequency should be less than ?1E-7/ry. Therefore, a passive SGDHR system using four completely independent thermo-siphon loops in natural convection mode is provided to ensure adequate core cooling for all Design Basis Events. The very high reliability requirement for DHR function is achieved mainly with the help of SGDHRS. This paper presents the reliability analysis of SGDHR system. Analysis is performed by Fault Tree method using CRAFT software developed at Indira Gandhi Centre for Atomic Research. This software has special features for compact representation and CCF analysis of high redundancy safety systems encountered in nuclear reactors. Common Cause Failures (CCF) are evaluated by ? factor method. The reliability target for SGDHRS arrived from DHR reliability requirement and the ultimate number of demands per year (7/y) on SGDHRS is that the failure frequency should be ?1.4E-8/de. Since it is found from the analysis that the unreliability of SGDHRS with identical loops is 5.2E-6/de and dominated by leak rates of components like AHX, DHX and sodium dump and isolation valves, options with diversity measures in important components were studied. The failure probability of SGDHRS for a design consisting of 2 types of diverse loops (Diverse AHX, DHX and sodium dump and isolation valves) is 2.1E-8/de, which practically meets the reliability requirement.

A. John Arul; C. Senthil Kumar; S. Athmalingam; Om Pal Singh; K. Suryaprakasa Rao

2006-01-01T23:59:59.000Z

331

Cold Vacuum Drying Facility hazard analysis report  

SciTech Connect (OSTI)

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

332

Technical support document: Energy conservation standards for consumer products: Refrigerators and furnaces including: environmental impacts regulatory impact analysis  

SciTech Connect (OSTI)

The National Appliance Energy Conversation Act (NAECA) of 1987 (P.L. 100-12) establishes energy efficiency standards for 13 types of consumer products. The legislation requires the Department of Energy (DOE) to consider new or amended standards on these and other types of products at specified times. DOE is currently selecting standards for two types of products: refrigerators, refrigerator-freezers, and freezers; and small gas furnaces. This Technical Support Document presents the methodology, data and results from the analysis of the energy and economic impacts of the proposed standards. 8 refs., 39 figs., 135 tabs.

Not Available

1989-11-01T23:59:59.000Z

333

Environmental Health and Safety  

E-Print Network [OSTI]

Environmental Health and Safety Approved by Document No. Version Date Replaces Page EHS EHS-FORM-072 1.0 15-May-2008 N/A 1 of 4 Laboratory Safety Orientation Checklist Name (Print) Department Supervisor Date (DD/MM/YY) A Laboratory Safety Orientation Checklist should be completed within one month

Shoubridge, Eric

334

SYSTEM SAFETY PROGRESS REPORT,  

E-Print Network [OSTI]

SYSTEM SAFETY PROGRESS REPORT, ALSEP Array E NO. ATM 1034 1 PAGE REV. NO. OF 3 DATE 26 July 1971 This A TM documents the progress of the System Safety Program for ALSEP Array E. -~/ Prepared by: · /~t:A~.., Approved by: W. · Lavin, Jr System Safety Engineer / /' J. P. ~/ es, Supervisor · , ALSEF Support

Rathbun, Julie A.

335

Nuclear Facility Safety Basis  

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

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

336

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP  

SciTech Connect (OSTI)

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

337

Electrical Safety Occurrences | Department of Energy  

Office of Environmental Management (EM)

Electrical Safety Occurrences Electrical Safety Occurrences June 26, 2014 Monthly Analysis of Electrical Safety Occurrences - April 2013 An analysis of the Occurrence Reporting and...

338

Electrical Safety Occurrences | Department of Energy  

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

Electrical Safety Occurrences Electrical Safety Occurrences September 20, 2011 Monthly Analysis of Electrical Safety Occurrences - August 2011 An analysis of the Occurrence...

339

CERCA LEU fuel assemblies testing in Maria Reactor - safety analysis summary and testing program scope.  

SciTech Connect (OSTI)

The presented paper contains neutronic and thermal-hydraulic (for steady and unsteady states) calculation results prepared to support annex to Safety Analysis Report for MARIA reactor in order to obtain approval for program of testing low-enriched uranium (LEU) lead test fuel assemblies (LTFA) manufactured by CERCA. This includes presentation of the limits and operational constraints to be in effect during the fuel testing investigations. Also, the scope of testing program (which began in August 2009), including additional measurements and monitoring procedures, is described.

Pytel, K.; Mieleszczenko, W.; Lechniak, J.; Moldysz, A.; Andrzejewski, K.; Kulikowska, T.; Marcinkowska, A.; Garner, P. L.; Hanan, N. A.; Nuclear Engineering Division; Institute of Atomic Energy (Poland)

2010-03-01T23:59:59.000Z

340

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

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

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

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

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

SciTech Connect (OSTI)

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

342

Technical Safety Requirements  

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

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

343

Supervisors` orientation to occupational safety in DOE  

SciTech Connect (OSTI)

This document presents OSHA regulations, safety and health guidelines pertinent to DOE and the first-line supervisor.

NONE

1993-10-01T23:59:59.000Z

344

Required Documents  

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

345

Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I  

SciTech Connect (OSTI)

This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems are analyzed, and the consequences of postulated accidents are presented. The risk associated with normal operations, abnormal operations, and natural phenomena are analyzed. The accident analysis presented shows that the impact of the facility will be acceptable for all foreseeable normal and abnormal conditions of operation. Specifically, under normal conditions the facility will have impacts within the limits posted by applicable DOE guidelines, and in accident conditions the facility will similarly meet or exceed the requirements of all applicable standards. 16 figs., 6 tabs.

NONE

1990-09-19T23:59:59.000Z

346

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

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

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

347

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

SciTech Connect (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

348

Technical Review Report for the Model 9978-96 Package Safety Analysis Report for Packaging (S-SARP-G-00002, Revision 1, March 2009)  

SciTech Connect (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

349

Assessment Documents  

Energy Savers [EERE]

independent-oversight-review-lawrence-livermore-national-laboratory-september-2013" typeof"sioc:Item foaf:Document">

October 2,...

350

Enforcement Documents  

Office of Environmental Management (EM)

Documents en Consent Order, Battelle Memorial Institute - October 24, 2014 http:energy.goveadownloadsconsent-order-battelle-memorial-institute-october-24-2014

351

Safety Analysis and Certification of Open Distributed Systems P. M. Conmy; Department of Computer Science, University of York, York, YO10 5DD U.K.  

E-Print Network [OSTI]

Safety Analysis and Certification of Open Distributed Systems P. M. Conmy; Department of Computer to the safety analysis and certification of avionics computer systems. At present aircraft computing systems are to the way avionics computer systems are analysed and certified. At present analysis techniques are based

Nicholson, Mark

352

Plutonium Finishing Plant safety evaluation report  

SciTech Connect (OSTI)

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

353

2007 Wholesale Power Rate Case Final Proposal : Risk Analysis Study Documentation.  

SciTech Connect (OSTI)

The RiskMod Model is comprised of a set of risk simulation models, collectively referred to as RiskSim; a set of computer programs that manages data referred to as Data Management Procedures; and RevSim, a model that calculates net revenues. RiskMod interacts with the AURORA Model, the RAM2007, and the ToolKit Model during the process of performing the Risk Analysis Study. AURORA is the computer model being used to perform the Market Price Forecast Study (see Market Price Forecast Study, WP-07-FS-BPA-03); the RAM2007 is the computer model being used to calculate rates (see Wholesale Power Rate Development Study, WP-07-FS-BPA-05); and the ToolKit is the computer model being used to develop the risk mitigation package that achieves BPA's 92.6 percent TPP standard (see Section 3 in the Risk Analysis Study, WP-07-FS-BPA-04). Variations in monthly loads, resources, natural gas prices, forward market electricity prices, transmission expenses, and aluminum smelter benefit payments are simulated in RiskSim. Monthly spot market electricity prices for the simulated loads, resources, and natural gas prices are estimated by the AURORA Model. Data Management Procedures facilitate the format and movement of data that flow to and/or from RiskSim, AURORA, and RevSim. RevSim estimates net revenues using risk data from RiskSim, spot market electricity prices from AURORA, loads and resources data from the Load Resource Study, WP-07-FS-BPA-01, various revenues from the Revenue Forecast component of the Wholesale Power Rate Development Study, WP-07-FSBPA-05, and rates and expenses from the RAM2007. Annual average surplus energy revenues, purchased power expenses, and section 4(h)(10)(C) credits calculated by RevSim are used in the Revenue Forecast and the RAM2007. Heavy Load Hour (HLH) and Light Load Hour (LLH) surplus and deficit energy values from RevSim are used in the Transmission Expense Risk Model. Net revenues estimated for each simulation by RevSim are input into the ToolKit Model to develop the risk mitigation package that achieves BPA's 92.6 percent TPP standard. The processes and interaction between each of the models and studies are depicted in Graph 1.

United States. Bonneville Power Administration.

2006-07-01T23:59:59.000Z

354

2007 Wholesale Power Rate Case Initial Proposal : Risk Analysis Study Documentation.  

SciTech Connect (OSTI)

The RiskMod Model is comprised of a set of risk simulation models, collectively referred to as RiskSim; a set of computer programs that manages data referred to as Data Management Procedures; and RevSim, a model that calculates net revenues. RiskMod interacts with the AURORA Model, the RAM2007, and the ToolKit Model during the process of performing the Risk Analysis Study. AURORA is the computer model being used to perform the Market Price Forecast Study (see Market Price Forecast Study, WP-07-E-BPA-03); the RAM2007 is the computer model being used to calculate rates (see Wholesale Power Rate Development Study, WP-07-E-BPA-05); and the ToolKit is the computer model being used to develop the risk mitigation package that achieves BPA's 92.6 percent TPP standard (see Section 3 in the Risk Analysis Study, WP-07-E-BPA-04). Variations in monthly loads, resources, natural gas prices, forward market electricity prices, transmission expenses, and aluminum smelter benefit payments are simulated in RiskSim. Monthly spot market electricity prices for the simulated loads, resources, and natural gas prices are estimated by the AURORA Model. Data Management Procedures facilitate the format and movement of data that flow to and/or from RiskSim, AURORA, and RevSim. RevSim estimates net revenues using risk data from RiskSim, spot market electricity prices from AURORA, loads and resources data from the Load Resource Study, WP-07-E-BPA-01, various revenues from the Revenue Forecast component of the Wholesale Power Rate Development Study, WP-07-E-BPA-05, and rates and expenses from the RAM2007. Annual average surplus energy revenues, purchased power expenses, and section 4(h)(10)(C) credits calculated by RevSim are used in the Revenue Forecast and the RAM2007. Heavy Load Hour (HLH) and Light Load Hour (LLH) surplus and deficit energy values from RevSim are used in the Transmission Expense Risk Model. Net revenues estimated for each simulation by RevSim are input into the ToolKit Model to develop the risk mitigation package that achieves BPA's 92.6 percent TPP standard. The processes and interaction between each of the models and studies are depicted in Graph 1.

United States. Bonneville Power Administration.

2005-11-01T23:59:59.000Z

355

Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility  

SciTech Connect (OSTI)

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

356

Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety  

SciTech Connect (OSTI)

Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron multiplication factor (k(sub)eff) for the a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models.

DeHart, M.D.

1999-08-01T23:59:59.000Z

357

FAQS Job Task Analyses - DOE AVIATION SAFETY OFFICER (ASO)  

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

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.

358

Untitled Document  

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

What is the MSDS Management System? MSDS stands for Material Safety Data Sheet. This is a computerized data base to help you retrieve the information from the MSDS's more rapidly...

359

Letter from Nuclear Energy Institute regarding Integrated Safety Analysis: Why it is Appropropriate for Fuel Recycling Facilities  

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

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.

360

The Front Lines of Patient Safety  

E-Print Network [OSTI]

patient safety · Incident Reporting · Root Cause Analysis · FMEA · Culture of Patient Safety Survey

Soloveichik, David

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

ELM Documents  

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

362

CRITICALITY SAFETY (CS)  

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

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

363

Fuel-Coolant-Interaction modeling and analysis work for the High Flux Isotope Reactor Safety Analysis Report  

SciTech Connect (OSTI)

A brief historical background and a description of short- and long-term task plan development for effective closure of this important safety issue for the HFIR are given. Short-term aspects deal with Fuel-Coolant-Interaction (FCI) issues experimentation, modeling, and analysis for the flow-blockage-induced steam explosion events in direct support of the SAR. Long-term aspects deal with addressing FCI issues resulting from other accidents in conjunction with issues dealing with aluminum ignition, which can result in an order of magnitude increase in overall energetics. Problem formulation, modeling, and computer code simulation for the various phases of steam explosions are described. The evaluation of core melt initiation propagation, and melt superheat are described. Core melt initiation and propagation have been studied using simple conservative models as well as from modeling and analysis using RELAP5. Core debris coolability, heatup, and melting/freezing aspects have been studied by use of the two-dimensional melting/freezing analysis code 2DKO, which was also benchmarked with MELCOR code predictions. Descriptions are provided for the HM, BH, FCIMOD, and CTH computer codes that have been implemented for studying steam explosion energetics from the standpoint of evaluating bounding loads by thermodynamic models or best-estimate loads from one- and two-dimensional simulations of steam explosion energetics. Vessel failure modeling and analysis was conducted using the principles of probabilistic fracture mechanics in conjunction with ADINA code calculations. Top head bolts failure modeling has also been conducted where the failure criterion was based upon stresses in the bolts exceeding the material yield stress for a given time duration. Missile transport modeling and analysis was conducted by setting up a one-dimensional mathematical model that accounts for viscous dissipation, virtual mass effects, and material inertia.

Taleyarkhan, R.P.; Georgevich, V.; Nestor, C.W.; Chang, S.J.; Freels, J.; Gat, U.; Lepard, B.L.; Gwaltney, R.C.; Luttrell, C.; Kirkpatrick, J.

1993-07-01T23:59:59.000Z

364

Safety Basis Report  

SciTech Connect (OSTI)

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

365

Safety for Users  

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

366

Enforcement Guidance Supplement 99-03: Limitation of 10 CFR Part 830 to Equipment Referenced in the Safety Analysis Report  

Broader source: Energy.gov [DOE]

Recently this Office received a reply to a Preliminary Notice of Violation (PNOV), although not denying any facts or conclusions in the PNOV and agreeing to pay the full imposed Civil Penalty, included arguments that some of the equipment cited in the PNOV was not, in their view, subject to the requirements of Part 830. The contractor argued that only equipment referenced in the Safety Analysis Report (SAR), Technical Safety Requirements (TSR) or Technical Specifications should come under the requirements of Part 830. The attached is DOEs response to denying that argument.

367

Electric Vehicle Safety Training for Emergency Responders | Department...  

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

Peer Evaluation Meeting arravt036tiklock2012o.pdf More Documents & Publications Electric Vehicle Safety Training for Emergency Responders U.S. First Responder Safety Training...

368

Electric Vehicle Safety Training for Emergency Responders | Department...  

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

and Peer Evaluation arravt036tiklock2011p.pdf More Documents & Publications Electric Vehicle Safety Training for Emergency Responders U.S. First Responder Safety Training...

369

Worker Safety and Health Rules, Directives, and Technical Standards...  

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

Worker Safety and Health Rules, Directives, and Technical Standards Worker Safety and Health Rules, Directives, and Technical Standards Document Number Title Date 10 CFR 707...

370

Office of Environment, Safety and Health Assessments Protocol...  

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

Office of Environment, Safety and Health Assessments Protocol, Development and Maintenance of Criteria Review and Approach Documents, June 2014 Office of Environment, Safety and...

371

USW Health Safety and Environment Conference - HSS Workshop ...  

Office of Environmental Management (EM)

USW Health Safety and Environment Conference - HSS Workshop USW Health Safety and Environment Conference - HSS Workshop Workshop Date: March 7, 2012 Documents Available for...

372

Revised 9/11/12 ________________________ _____Environment, Health, & Safety _____ ______________________  

E-Print Network [OSTI]

that assist the completion and documentation of a walkaround. · Practice conducting and effective safety Minute For Safety - http://www.lbl.gov/ehs/index.shtml #12;

Eisen, Michael

373

Regulatory guidance document  

SciTech Connect (OSTI)

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

374

Facility Safety  

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

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1996-10-24T23:59:59.000Z

375

Facility Safety  

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

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1995-11-16T23:59:59.000Z

376

PETSc: Documentation  

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

377

FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter  

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

378

Oversight Documents  

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

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

379

Enforcement Documents  

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

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

380

Nuclear Engineer (Criticality Safety)  

Broader source: Energy.gov [DOE]

This position is located in the Nuclear Safety Division (NSD) which has specific responsibility for managing the development, analysis, review, and approval of non-reactor nuclear facility safety...

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

Electrical Safety  

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

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

382

Uncertainty analysis of criticality safety for the plate type fuel assembly storage rack  

Science Journals Connector (OSTI)

To evaluate the criticality safety of the fresh and the spent fuel storage racks in an open pool type research reactor designed by KAERI, the upper subcriticality limit (USL) analysis was carried out. First, the bias and its uncertainty of MCNP code system with ENDF/B-VII library were evaluated using the calculation results of the 183 benchmark experiments. The criticality calculations for the fuel storage rack are carried out under a normal state, an increased water temperature, a fuel assembly drop, and an eccentric insertion which can affect the criticality. Considering biases and uncertainties for the MCNP code system, abnormal conditions, and the manufacturing tolerance of the cell tube thickness, the USL value that can guarantee sufficient subcriticality is determined. It was found that the criticality of the fresh and the spent fuel storage racks currently designed satisfy the USL condition. Additionally, it was concluded that the pitch size of a fresh fuel storage rack can be reduced for efficient space availability, and even under a worst case in which the fresh storage rack is surrounded by a lower water density and the smallest pitch size satisfies the USL conditions.

Tae Young Han; Chang Je Park; Byung Chul Lee; Jae Man Noh

2013-01-01T23:59:59.000Z

383

Submersion Criticality Safety Analysis of Tungsten-Based Fuel for Nuclear Power and Propulsion Applications  

SciTech Connect (OSTI)

The Center for Space Nuclear Research (CSNR) is developing tungsten-encapsulated fuels for space nuclear applications. Aims to develop NTP fuels that are; Affordable Low impact on production and testing environment Producible on a large scale over suitable time period Higher-performance compared to previous graphite NTP fuel elements Space nuclear reactors remain subcritical before and during launch, and do not go critical until required by its mission. A properly designed reactor will remain subcritical in any launch abort scenario, where the reactor falls back to Earth and becomes submerged in terrestrial material. Submersion increases neutron reflection and thermalizes the neutrons, which typically increases the reactivity of the core. This effect is usually very significant for fast-spectrum reactors. This research provided a submersion criticality safety analysis for a representative tungsten/uranium oxide fueled reactor. Determine the submersion behavior of a reactor fueled by tungsten-based fuel. Considered fuel compositions with varying: Rhenium content (wt% rhenium in tungsten) Fuel loading fractions (UO2 vol%)

A.E. Craft; R. C. O'Brien; S. D. Howe; J. C. King

2014-07-01T23:59:59.000Z

384

Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 2, Rev. 14  

SciTech Connect (OSTI)

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

385

Advanced organic analysis and analytical methods development: FY 1995 progress report. Waste Tank Organic Safety Program  

SciTech Connect (OSTI)

This report describes the work performed during FY 1995 by Pacific Northwest Laboratory in developing and optimizing analysis techniques for identifying organics present in Hanford waste tanks. The main focus was to provide a means for rapidly obtaining the most useful information concerning the organics present in tank waste, with minimal sample handling and with minimal waste generation. One major focus has been to optimize analytical methods for organic speciation. Select methods, such as atmospheric pressure chemical ionization mass spectrometry and matrix-assisted laser desorption/ionization mass spectrometry, were developed to increase the speciation capabilities, while minimizing sample handling. A capillary electrophoresis method was developed to improve separation capabilities while minimizing additional waste generation. In addition, considerable emphasis has been placed on developing a rapid screening tool, based on Raman and infrared spectroscopy, for determining organic functional group content when complete organic speciation is not required. This capability would allow for a cost-effective means to screen the waste tanks to identify tanks that require more specialized and complete organic speciation to determine tank safety.

Wahl, K.L.; Campbell, J.A.; Clauss, S.A. [and others

1995-09-01T23:59:59.000Z

386

Yucca Mountain Project Document Suspension, OAS-M-08-07 | Department of  

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

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

387

Yucca Mountain Project Document Suspension, OAS-M-08-07 | Department of  

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

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

388

CY 2012 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

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

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

389

CY 2011 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

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

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

390

The safety climate of a Department of Energy nuclear facility: A sociotechnical analysis  

SciTech Connect (OSTI)

Government- and public-sponsored groups are increasingly demanding greater accountability by the Department of Energy`s weapons complex. Many of these demands have focused on the development of a positive safety climate, one that not only protects workers onsite, but also the surrounding populace and environment as well. These demands are, in part, a response to findings which demonstrate a close linkage between actual organizational safety performance and the organization`s safety climate, i.e., the collective attitudes employees hold concerning the level of safety in their organization. This paper describes the approach taken in the systematic assessment of the safety climate at EG&G Rocky Flats Plant (RFP).

Johnson, A.E.; Harbour, J.L.

1993-06-01T23:59:59.000Z

391

Quantifying information leakage in document redaction  

Science Journals Connector (OSTI)

In this paper, we examine ways in which sensitive information might leak through the process of redaction. Such attacks apply known methods from document image analysis and natural language processing to recover text thought to have been obliterated ... Keywords: character shape coding, classified documents, document analysis, document redaction

Daniel Lopresti; A. Lawrence Spitz

2004-11-01T23:59:59.000Z

392

Overview of New Tools to Perform Safety Analysis: BWR Station Black Out Test Case  

SciTech Connect (OSTI)

Dynamic Probabilistic Risk Assessment (DPRA) methodologies couple system simulator codes (e.g., RELAP, MELCOR) with simulation controller codes (e.g., RAVEN, ADAPT). While system simulator codes accurately model system dynamics deterministically, simulation controller codes introduce both deterministic (e.g., system control logic, operating procedures) and stochastic (e.g., component failures, parameter uncertainties) elements into the simulation. Typically, a DPRA is performed by: 1) sampling values of a set of parameters from the uncertainty space of interest (using the simulation controller codes), and 2) simulating the system behavior for that specific set of parameter values (using the system simulator codes). For complex systems, one of the major challenges in using DPRA methodologies is to analyze the large amount of information (i.e., large number of scenarios ) generated, where clustering techniques are typically employed to allow users to better organize and interpret the data. In this paper, we focus on the analysis of a nuclear simulation dataset that is part of the Risk Informed Safety Margin Characterization (RISMC) Boiling Water Reactor (BWR) station blackout (SBO) case study. We apply a software tool that provides the domain experts with an interactive analysis and visualization environment for understanding the structures of such high-dimensional nuclear simulation datasets. Our tool encodes traditional and topology-based clustering techniques, where the latter partitions the data points into clusters based on their uniform gradient flow behavior. We demonstrate through our case study that both types of clustering techniques complement each other in bringing enhanced structural understanding of the data.

D. Mandelli; C. Smith; T. Riley; J. Nielsen; J. Schroeder; C. Rabiti; A. Alfonsi; Cogliati; R. Kinoshita; V. Pasucci; B. Wang; D. Maljovec

2014-06-01T23:59:59.000Z

393

FACILITY SAFETY (FS)  

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

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

394

ARM - Conference Documents  

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

govPublicationsConference Documents Publications Journal Articles Conference Documents Program Documents Technical Reports Publications Database Public Information Materials Image...

395

Safety Assurance for ATR Irradiations  

SciTech Connect (OSTI)

The Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL) is the worlds premiere test reactor for performing high fluence, large volume, irradiation test programs. The ATR has many capabilities and a wide variety of tests are performed in this truly one of a kind reactor, including isotope production, simple self-contained static capsule experiments, instrumented/controlled experiments, and loop testing under pressurized water conditions. Along with the five pressurized water loops, ATR may also have gas (temperature controlled) lead experiments, fuel boosted fast flux experiments, and static sealed capsules all in the core at the same time. In addition, any or all of these tests may contain fuel or moderating materials that can affect reactivity levels in the ATR core. Therefore the safety analyses required to ensure safe operation of each experiment as well as the reactor itself are complex. Each test has to be evaluated against stringent reactor control safety criteria, as well as the effects it could have on adjacent tests and the reactor as well as the consequences of those effects. The safety analyses of each experiment are summarized in a document entitled the Experiment Safety Assurance Package (ESAP). The ESAP references and employs the results of the reactor physics, thermal, hydraulic, stress, seismic, vibration, and all other analyses necessary to ensure the experiment can be irradiated safely in the ATR. The requirements for reactivity worth, chemistry compatibilities, pressure limitations, material issues, etc. are all specified in the Technical Safety Requirements and the Upgraded Final Safety Analysis Report (UFSAR) for the ATR. This paper discusses the ESAP process, types of analyses, types of safety requirements and the approvals necessary to ensure an experiment can be safely irradiated in the ATR.

S. Blaine Grover

2006-10-01T23:59:59.000Z

396

Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

1992-06-01T23:59:59.000Z

397

Safety First Safety Last Safety Always Safety Shoes  

E-Print Network [OSTI]

Safety First Safety Last Safety Always Safety Shoes and Boots Safety Tip #21 Don't let your day guards) can be used in conjunction with standard safety shoes. Safety boots Safety boots come in many varieties, and which you will use will depend on the specific hazards you face. Boots offer more protection

Minnesota, University of

398

RESEARCH SAFETY RADIATION SAFETY  

E-Print Network [OSTI]

and Communications Manager (951) 827-6303 janette.ducut@ucr.edu Beiwei Tu, MS, CIH, CSP Safety and Industrial Hygiene, CSP Laboratory Safety Compliance Specialist (951) 827-2528 sarah.meyer@ucr.edu (vacant) Integrated

399

Untitled Document  

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

400

CHRG Documents  

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

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

NEPA Documentation  

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

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

402

Accelerated safety analyses - structural analyses Phase I - structural sensitivity evaluation of single- and double-shell waste storage tanks  

SciTech Connect (OSTI)

Accelerated Safety Analyses - Phase I (ASA-Phase I) have been conducted to assess the appropriateness of existing tank farm operational controls and/or limits as now stipulated in the Operational Safety Requirements (OSRs) and Operating Specification Documents, and to establish a technical basis for the waste tank operating safety envelope. Structural sensitivity analyses were performed to assess the response of the different waste tank configurations to variations in loading conditions, uncertainties in loading parameters, and uncertainties in material characteristics. Extensive documentation of the sensitivity analyses conducted and results obtained are provided in the detailed ASA-Phase I report, Structural Sensitivity Evaluation of Single- and Double-Shell Waste Tanks for Accelerated Safety Analysis - Phase I. This document provides a summary of the accelerated safety analyses sensitivity evaluations and the resulting findings.

Becker, D.L.

1994-11-01T23:59:59.000Z

403

Nuclear Safety Enforcement Documents | Department of Energy  

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

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,

404

Nuclear Safety Enforcement Documents | Department of Energy  

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

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

405

Preparation of Nonreactor Nuclear Facility Documented Safety...  

Energy Savers [EERE]

of such hazards might include the generation of flammableexplosive hydrogen gas by electrolysis of uranium in water or a spill of sodium hydroxide used in radioactive waste...

406

Nuclear Safety Enforcement Documents | Department of Energy  

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

July 25, 2000 Consent Order, CH2M Hill Hanford Group, Inc. - EA-2000-09 Issued to CH2M Hill Hanford Group, Inc., related to Quality Problems at the Hanford Site Tank Farms,...

407

Nuclear Safety Enforcement Documents | Department of Energy  

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

related to Concrete Work Issues at the Waste Treatment and Immobilization Plant at the Hanford Site February 5, 2004 Preliminary of Violation, Kaiser-Hill Company, LLC, -...

408

Nuclear Safety Enforcement Documents | Department of Energy  

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

Issued to CH2M Hill Mound, Inc. related to a Radioactive Contamination Event during Remediation Activities at the Miamisburg Closure Project November 18, 2004 Preliminary Notice...

409

Nuclear Safety Enforcement Documents | Department of Energy  

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

Letter, NEL-2013-01 - January 7, 2013 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant October 4, 2012 Preliminary Notice of...

410

Nuclear Safety Enforcement Documents | Department of Energy  

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

Paducah Gaseous Diffusion Plants March 26, 2010 Enforcement Letter, Geiger Brothers Mechanical Contractors, INC - March 26, 2010 Issued to Geiger Brothers Mechanical Contractors,...

411

Nuclear Safety Enforcement Documents | Department of Energy  

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

to Kaiser-Hill Company, LLC related to Recurring Weaknesses in Implementing Quality Assurance Rule Requirements at the Rocky Flats Environmental Technology Site June 4, 1998...

412

Nuclear Safety Enforcement Documents | Department of Energy  

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

- July 7, 1997 Issued to the University of California related to Potential Quality Assurance Rule Violations associated with an Explosion and Fire at the Los Alamos National...

413

A Comparison of Two Approaches to Safety Analysis Based on Use Cases  

Science Journals Connector (OSTI)

Engineering has a long tradition in analyzing the safety of mechanical, electrical and electronic systems. Important methods like HazOp and FMEA have also been adopted by the software ... by the software communit...

Tor Stlhane; Guttorm Sindre

2007-01-01T23:59:59.000Z

414

Nuclear Energy Institute (NEI) Attachment, Integrated Safety...  

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

Energy Institute (NEI) Attachment, Integrated Safety Analysis Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis This paper addresses why the use of an...

415

Waste Tank Organic Safety Program: Analytical methods development. Progress report, FY 1994  

SciTech Connect (OSTI)

The objectives of this task are to develop and document extraction and analysis methods for organics in waste tanks, and to extend these methods to the analysis of actual core samples to support the Waste Tank organic Safety Program. This report documents progress at Pacific Northwest Laboratory (a) during FY 1994 on methods development, the analysis of waste from Tank 241-C-103 (Tank C-103) and T-111, and the transfer of documented, developed analytical methods to personnel in the Analytical Chemistry Laboratory (ACL) and 222-S laboratory. This report is intended as an annual report, not a completed work.

Campbell, J.A.; Clauss, S.A.; Grant, K.E. [and others

1994-09-01T23:59:59.000Z

416

Technical safety requirements for the Auxiliary Hot Cell Facility (AHCF).  

SciTech Connect (OSTI)

These Technical Safety Requirements (TSRs) identify the operational conditions, boundaries, and administrative controls for the safe operation of the Auxiliary Hot Cell Facility (AHCF) at Sandia National Laboratories, in compliance with 10 CFR 830, 'Nuclear Safety Management.' The bases for the TSRs are established in the AHCF Documented Safety Analysis (DSA), which was issued in compliance with 10 CFR 830, Subpart B, 'Safety Basis Requirements.' The AHCF Limiting Conditions of Operation (LCOs) apply only to the ventilation system, the high efficiency particulate air (HEPA) filters, and the inventory. Surveillance Requirements (SRs) apply to the ventilation system, HEPA filters, and associated monitoring equipment; to certain passive design features; and to the inventory. No Safety Limits are necessary, because the AHCF is a Hazard Category 3 nuclear facility.

Seylar, Roland F.

2004-02-01T23:59:59.000Z

417

Nuclear Safety Regulatory Framework  

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

Department of Energy Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946 Atomic Energy Act 1954 Energy Reorganization Act 1974 DOE Act 1977 Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural Rules ISMS-QA; Operating Experience; Metrics and Analysis Cross Cutting DOE Directives & Manuals DOE Standards Central Technical Authorities (CTA) Office of Health, Safety, and Security (HSS) Line Management SSO/ FAC Reps 48 CFR 970 48 CFR 952 Federal Acquisition Regulations External Oversight *Defense Nuclear Facility

418

Safety and Security Enforcement Program  

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

419

CRAD, Facility Safety- Nuclear Facility Safety Basis  

Broader source: Energy.gov [DOE]

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.

420

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10  

Broader source: Energy.gov [DOE]

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...

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

Ehron Documents  

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

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

422

Safety First Safety Last Safety Always General site safety  

E-Print Network [OSTI]

Safety First Safety Last Safety Always General site safety During the course of construction barrier at least 5 feet (1.5m) high having a fire-resistance rating of at least one half hour. Site Safety and Clean-up Safety Tip #20 Safety has no quitting time. All contractors should clean up their debris, trash

Minnesota, University of

423

Safety First Safety Last Safety Always Safety Tip #22  

E-Print Network [OSTI]

Safety First Safety Last Safety Always Safety Tip #22 Mowing Operations Mowing unsafely just doesn for out-of-control vehicles. Wear hearing protection and a safety vest. Wear a hard hat and safety goggles of this safety tip sheet. Please refrain from reading the information verbatim--paraphrase it instead

Minnesota, University of

424

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE  

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

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1 This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE's operation of nuclear facilities. In developing the revised Policy and performing this analysis, DOE reviewed the current Nuclear Safety Policy (Secretary of Energy Notice [SEN] 35-91, Nuclear Safety Policy) and safety policies established by other safety

425

Integrated Safety Management Workshop Registration, PIA, Idaho...  

Office of Environmental Management (EM)

Safety Management Workshop Registration, PIA, Idaho National Laboratory More Documents & Publications TRAIN-PIA.pdf Occupational Medicine - Assistant PIA, Idaho National Laboratory...

426

An analysis of firefighter personal safety alarm effectiveness on the fire ground  

Science Journals Connector (OSTI)

For firefighters in the line of duty the last line of defense and chance for rescue oftentimes relies on the effectiveness of their Personal Alert Safety System (PASS) devices. When activated a PASS device emits an alarm signal to notify others that a firefighter is in distress. However there have been notable instances where PASS devices have confused rescue personnel or created a more hazardous situation for instance when noise interference originating from other objects is involved. This research compiles data from various sources for example firefighter near miss reports and National Institute for Occupational Safety and Health (NIOSH) fatality reports regarding PASS device effectiveness. The research will investigate the causes of confusion and danger as well as take a look at the situations where the device achieved its goal and was able to save a life. The implications of discovering how interfering noises can render PASS devices ineffective could save several lives in the future and ultimately lead to increased firefighter safety.

Kyle Ford; Mudeer Habeeb; Joelle Suits; Mustafa Abbasi; Ofodike Ezekoye

2013-01-01T23:59:59.000Z

427

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

428

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 _

429

Enron Documents  

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

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

430

Enron Documents  

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

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:

431

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory. TRU curium shipping container  

SciTech Connect (OSTI)

An analytical evaluation of the Oak Ridge National Laboratory Transuranium (TRU) Curium Shipping Container was made to demonstrate its compliance with the regulations governing offsite shipment of packages containing radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the container complies with the applicable regulations.

Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Aramayo, G.A.

1980-06-01T23:59:59.000Z

432

Component Failure Behaviour: Patterns and Reuse in Automated System Safety Analysis  

E-Print Network [OSTI]

using a pool of shared information and energy resources. In practice, one of the major challenges together a number of currently standalone functions in a common platform where functions are implemented towards implementation of distributed active safety in vehicles is automatic control of the steering

Boyer, Edmond

433

INL Procurement Document and Forms  

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

Excavation Checklist Word 432.58 Job Safety Analysis PRD-1007 Word 432.65 Construction LockoutTagout Checklist Word 432.A31 Competent Person Roster Word 432.A42 Manpower and...

434

Enforcement Guidance Supplement 99-03, Limitation of 10 CFR 830 to Equipment Referenced in the Safety Analysis Report  

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

for Enforcement Department of Energy Washington DC 20585 October 20, 1999 MEMORANDUM FOR: DOE and Contractor PAAA Coordinators FROM: R. Keith Christopher Director Office of Enforcement and Investigation SUBJECT: Enforcement Guidance Supplement 99-03: Limitation of 10 CFR Part 830 to Equipment Referenced in the Safety Analysis Report Recently this Office received a reply to a Preliminary Notice of Violation (PNOV), although not denying any facts or conclusions in the PNOV and agreeing to pay the full imposed Civil Penalty, included arguments that some of the equipment cited in the

435

Safety Alerts | Department of Energy  

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

Alerts Safety Alerts Documents downloaded from the password-protected areas of this web site may be made available to the DOE Federal and contractor community and to the...

436

INDUSTRIAL SAFETY & HEALTH (ISH)  

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

BASIS (SB) BASIS (SB) OBJECTIVE SB.1 Facility safety documentation 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 (systems, procedures, administrative controls, etc.) that protect workers and the public form those hazards/risks. Safety structures, systems and components (SSCs) are defined and a system to maintain control over their designs and modification is established. (Core Requirement 7) Criteria 1. The TA-55 SST Facility safety basis and related documentation address the full spectrum of hazards/risks associated with operations. 2. Controls designed to mitigate the consequence of analyzed TA-55 SST Facility

437

Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container  

SciTech Connect (OSTI)

An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable regulations.

Box, W.D.; Shappert, L.B.; Seagren, R.D.; Klima, B.B.; Jurgensen, M.C.; Hammond, C.R.; Watson, C.D.

1980-01-01T23:59:59.000Z

438

UNBC SAFETY CHECKLIST SAFETY CHECKLIST  

E-Print Network [OSTI]

1 UNBC SAFETY CHECKLIST SAFETY CHECKLIST INSTRUCTIONS PAGE Please use the following table below needs, contact the Risk & Safety Department at 250-960- (5530) for further instructions. This safety. The safety checklist also helps you to establish due diligence under Federal and Provincial safety laws

Northern British Columbia, University of

439

Toolbox Safety Talk Ladder Safety  

E-Print Network [OSTI]

Toolbox Safety Talk Ladder Safety Environmental Health & Safety Facilities Safety & Health Section Health & Safety for recordkeeping. Slips, trips, and falls constitute the majority of general industry elevated work tasks. Like any tool, ladders must be used properly to ensure employee safety. GENERAL

Pawlowski, Wojtek

440

ARM - ARM Safety Policy  

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

Safety Policy Safety Policy About Become a User Recovery Act Mission FAQ Outreach Displays History Organization Participants Facility Statistics Forms Contacts Facility Documents ARM Management Plan (PDF, 335KB) Field Campaign Guidelines (PDF, 1.1MB) ARM Climate Research Facility Expansion Workshop (PDF, 1.46MB) Facility Activities ARM and the Recovery Act Contributions to International Polar Year Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send ARM Safety Policy The ARM Climate Research Facility safety policy states that all activities for which the ARM Climate Research Facility has primary responsibility will be conducted in such a manner that all reasonable precautions are taken to protect the health and safety of employees and the general public. All

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

Argonne CNM: Safety Training  

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

Safety at Work Safety at Work (printable pdf version) In case of emergency or if you need help or assistance dial Argonne's Protective Force: 911 (from Argonne phones) or (630) 252-1911 (from cell phones) As a staff member or user at the Center for Nanoscale Materials (CNM), you need to be aware of safety regulations at Argonne National Laboratory. You are also required to have taken any safety, orientation, and training classes or courses specified by your User Work Authorization(s) and/or work planning and control documents prior to beginning your work. For safety and security reasons, it is necessary to know of all facility users present in the CNM (Buildings 440 and 441). Users are required to sign in and out in the visitors logbook located in Room A119. Some detailed emergency information is provided on the Argonne National Laboratory web site. Brief instructions and general guidelines follow.

442

Ferrocyanide Safety Program rationale for removing six tanks from the safety watch list  

SciTech Connect (OSTI)

This report documents an in-depth study of single-shell tanks containing ferrocyanide wastes. Topics include: safety assessments, tank histories, supportive documentation about interim stabilization and planned remedial activities.

Borsheim, G.L.

1993-09-01T23:59:59.000Z

443

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

444

Order Module--DOE O 231.1B, ENVIRONMENT, SAFETY, AND HEALTH REPORTING |  

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

231.1B, ENVIRONMENT, SAFETY, AND HEALTH 231.1B, ENVIRONMENT, SAFETY, AND HEALTH REPORTING Order Module--DOE O 231.1B, ENVIRONMENT, SAFETY, AND HEALTH REPORTING To ensure the DOE receives timely and accurate information about events that have affected or could adversely affect the health, safety, and security of the public or workers, the environment, the operations of DOE facilities, or the credibility of the Department. This will be accomplished through timely collection, reporting, analysis, and dissemination of data pertaining to environment, safety, and health issues as required by law, or regulations, or in support of United States political commitments to the International Atomic Energy Agency (IAEA). DOE Order Self Study Modules - DOE O 231.1A Environment, Safety, and Health Reporting More Documents & Publications

445

FAQS Qualification Card Occupational Safety  

Broader source: Energy.gov [DOE]

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

446

Safety Management System Policy | Department of Energy  

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

Services » Program Management » Safety » Safety Management Services » Program Management » Safety » Safety Management System Policy Safety Management System Policy Safety Management Systems provide a formal, organized process whereby people plan, perform, assess, and improve the safe conduct of work. The Safety Management System is institutionalized through Department of Energy (DOE) directives and contracts to establish the Department-wide safety management objective, guiding principles, and functions. The DOE safety management system consists of six components: Objective Guiding principles Core functions Mechanisms Responsibilities Implementation Safety Management System Policy More Documents & Publications "DOE O 450.2 INTEGRATED SAFETY MANAGEMENT AND DOE P 450.4A INTEGRATED SAFETY MANAGEMENT POLICY FAMILIAR LEVEL

447

Electrical Equipment Inspection Program Electrical Safety  

E-Print Network [OSTI]

Electrical Equipment Inspection Program Electrical Safety SLAC-I-730-0A11A-001-R003 23 March 2005 Document Title: Electrical Equipment Inspection Program Original Publication Date: 19 January 2005 Revised Publication Date: 23 March 2005 (updated 29 November 2010) Department: Electrical Safety Document Number: SLAC

Wechsler, Risa H.

448

Stair Safety  

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

Stair Safety: Causes and Prevention of Stair Safety: Causes and Prevention of Residential Stair Injuries Cornell Department of Design & Cornell University Cooperative Environmental Analysis Martha Van Rensselaer Hall Extension 607-255-2144 Ithaca, NY 14853 In the United States during 1997 about 27,000 people were killed by unintentional home injuries. 1 Figure 1 illustrates the causes of some of the injuries that resulted in death. As you can see, falls account for the majority of incidents. Also in 1997, 6.8 million people suffered home accidents that resulted in disabling injuries. 1 While data on the number of injuries related to stairs and steps are not available for 1997, data from 1996 show that 984,000 people experienced injuries related to home stairs or steps during

449

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

E-Print Network [OSTI]

of the fixed-bed reactor, among other disadvantages, is that the reaction is very exothermic, which is a concern in terms of safety hazards and also in terms of cost of heat removal. With the slurry reactor, a problem is that in the liquid media... at different lengths.4 After the reaction takes place, the amount of carbon monoxide consumed decreases and carbon dioxide is produced as a side product.9 The FTS reaction is an extremely exothermic process, which represents serious challenges...

Hamad, Natalie

2012-02-14T23:59:59.000Z

450

Environment/Health/Safety (EHS)  

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

S S A B C D E F G H I J K L M N O P Q R S T U V W X Y Z SAAR - Supervisor's Accident Analysis Report SAAR for Division Safety Coordinators Safety Concerns/Comments Safety Engineering (Division) Safety Committee Safety Advisory Committee (LBNL) Safety Coordinator and Liaison Resources Safety Flicks Safety Shoes Safety Walk Around Check List Safety Walk Around Check List for Managers Satellite Accumulation Areas Security call x5472 Security and Emergency Operations Shipping & Transporting Hazardous Materials Shoemobile (schedule) (form) Site Access (parking permits, gate passes, buses) Site Environmental Report Site Map SJHA Spot Award Program Stop Work Policy Stretch Break Software-RSIGuard Subcontractor Job Hazard Analysis

451

Document Control Process  

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

452

Combining Formal Methods and Safety Analysis -The ForMoSA Approach  

E-Print Network [OSTI]

techniques [13, 20] like failure modes and effects analysis (FMEA) or fault tree analysis (FTA). The combina in which a component may fail. The leaves of all fault trees are failure modes. The starting column of FMEA

Reif, Wolfgang

453

Formal Support for Quantitative Analysis of Residual Risks in Safety-Critical Systems  

E-Print Network [OSTI]

and Effects Analysis (FMEA) and Fault-Tree Analy- sis (FTA) [16]. However, many of these techniques become

454

Enron Documents  

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

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

455

Preliminary safety analysis report for the Auxiliary Hot Cell Facility, Sandia National Laboratories, Albuquerque, New Mexico  

SciTech Connect (OSTI)

The Auxiliary Hot Cell Facility (AHCF) at Sandia National Laboratories, New Mexico (SNL/NM) will be a Hazard Category 3 nuclear facility used to characterize, treat, and repackage radioactive and mixed material and waste for reuse, recycling, or ultimate disposal. A significant upgrade to a previous facility, the Temporary Hot Cell, will be implemented to perform this mission. The following major features will be added: a permanent shield wall; eight floor silos; new roof portals in the hot-cell roof; an upgraded ventilation system; and upgraded hot-cell jib crane; and video cameras to record operations and facilitate remote-handled operations. No safety-class systems, structures, and components will be present in the AHCF. There will be five safety-significant SSCs: hot cell structure, permanent shield wall, shield plugs, ventilation system, and HEPA filters. The type and quantity of radionuclides that could be located in the AHCF are defined primarily by SNL/NM's legacy materials, which include radioactive, transuranic, and mixed waste. The risk to the public or the environment presented by the AHCF is minor due to the inventory limitations of the Hazard Category 3 classification. Potential doses at the exclusion boundary are well below the evaluation guidelines of 25 rem. Potential for worker exposure is limited by the passive design features incorporated in the AHCF and by SNL's radiation protection program. There is no potential for exposure of the public to chemical hazards above the Emergency Response Protection Guidelines Level 2.

OSCAR,DEBBY S.; WALKER,SHARON ANN; HUNTER,REGINA LEE; WALKER,CHERYL A.

1999-12-01T23:59:59.000Z

456

Safety First Safety Last Safety Always Requirements for employers  

E-Print Network [OSTI]

Safety First Safety Last Safety Always Requirements for employers · Fallprotectionsandproperuseofrelated-safety equipmentsuchaslifelines,harness · Properuseofdangeroustools,thenecessaryprecautionstotake,andtheuseof theprotectiveandemergencyequipmentrequired. Safety Training and Education Safety Tip #18 Get smart. Use safety from the start. All

Minnesota, University of

457

Portsmouth DUF6 Conversion Final EIS - Volume 2: Comment and Response Document: Chapter 2: Comment Documents  

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

458

Chemical Safety Program  

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

Program Program Home Chemical Safety Topical Committee Library Program Contacts Related Links Site Map Tools 2013 Chemical Safety Workshop Archived Workshops Contact Us Health and Safety HSS Logo Chemical Safety Program logo The Department of Energy's (DOE's) Chemical Safety web pages provide a forum for the exchange of best practices, lessons learned, and guidance in the area of chemical management. This page is supported by the Chemical Safety Topical Committee which was formed to identify chemical safety-related issues of concern to the DOE and pursue solutions to issues identified. Noteworthy products are the Chemical Management Handbooks and the Chemical Lifecycle Cost Analysis Tool, found under the TOOLS menu. Chemical Management Handbook Vol (1) Chemical Management Handbook Vol (2)

459

Safety System Oversight  

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

Safety System Oversight Safety System Oversight Office of Nuclear Safety Home Safety System Oversight Home Annual SSO/FR Workshop DOE Safety Links › ORPS Info › Operating Experience Summary › DOE Lessons Learned › Accident Investigation Program Assessment Tools › SSO CRADS Subject Matter Links General Program Information › Program Mission Statement › SSO Program Description › SSO Annual Award Program › SSO Annual Award › SSO Steering Committee › SSO Program Assessment CRAD SSO Logo Items Site Leads and Steering Committee Archive Facility Representative Contact Us HSS Logo SSO SSO Program News Congratulations to Ronnie L. Alderson of Nevada Field Office, the Winner of the 2012 Safety System Oversight Annual Award! 2012 Safety System Oversight Annual Award Nominees SSO Staffing Analysis

460

Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 1, Plenary sessions, reactor licensing topics, NUREG-1150, risk analysis/PRA applications, innovative concepts for increased safety of advanced power reactors, severe accident modeling and analysis  

SciTech Connect (OSTI)

This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 1, discusses the following: plenary sessions; reactor licensing; NUREG-1150; risk analysis; innovative concepts for increased safety of advanced power reactors; and severe accident modeling and analysis. Thirty-two reports have been cataloged separately.

Weiss, A.J. (comp.)

1988-02-01T23:59:59.000Z

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.


461

Hotspot Gap Analysis Final 20070323  

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

HS-0003 HS-0003 Software Evaluation of Hotspot and DOE Safety Software Toolbox Recommendation U.S. Department of Energy Office of Health, Safety and Security 1000 Independence Avenue, S.W. Washington, DC 20585-2040 March, 2007 ii Foreword This report documents the outcome of an evaluation of the Safety Software Quality Assurance (SSQA) attributes of Hotspot, a health physics application, relative to the safety software requirements identified in DOE O 414.1C, Quality Assurance. This evaluation, a "gap analysis", is performed according to the implementation guide DOE G 414.1-4, and is a requisite for deciding whether Hotspot should be designated as a toolbox code for DOE's safety software Central Registry. Comments regarding this document should be addressed to:

462

Environment/Health/Safety (EHS): JHA FAQ  

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

Job Hazards Analysis FAQ Job Hazards Analysis FAQ Topics JHA Basics Accessing the JHA Benefits of the JHA Work Lead JHA Work Groups Taking Your JHA Correcting Your JHA Training Profile JHA Basics Back to top Q: What is a JHA? A: The Job Hazards Analysis (JHA) process provides a documented mechanism to answer the question "How do I know that I'm doing my job safely?" It is a methodical analysis tool used by highly effective organizations to identify and eliminate workplace hazards before they can cause harm. Job Hazards Analysis is a tool used by LBNL to address the five core functions of Integrated Safety Management namely Plan the Work by identifying the tasks to be performed; Analyze the Hazards of the Work; Determine the Controls necessary to safely perform the Work; Perform the Work utilizing the prescribed Controls; and

463

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

SciTech Connect (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.

Crandall, R.S.; Nelson, B.P. (National Renewable Energy Lab., Golden, CO (United States)); Moskowitz, P.D.; Fthenakis, V.M. (Brookhaven National Lab., Upton, NY (United States))

1992-07-01T23:59:59.000Z

464

UNBC SAFETY CHECKLIST SAFETY CHECKLIST  

E-Print Network [OSTI]

1 UNBC SAFETY CHECKLIST SAFETY CHECKLIST INSTRUCTIONS PAGE Please use the following table below needs, contact the Risk & Safety Department at 250-960- (5530) for further instructions. This safety to remain safe here at UNBC. The safety checklist also helps you to establish due diligence under Federal

Northern British Columbia, University of

465

Integrated Safety Management Safety Culture Resources | Department...  

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

Safety Culture Resources Integrated Safety Management Safety Culture Resources A collection of resources available in implementing ISM safety culture activities Safety from the...

466

PAT-1 safety analysis report addendum author responses to request for additional information.  

SciTech Connect (OSTI)

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 National Nuclear Security Administration (NNSA) submitted SAND Report SAND2009-5822 to NRC that documented the incorporation of plutonium (Pu) metal as a new payload for the PAT-1 package. NRC responded with a Request for Additional Information (RAI), identifying information needed in connection with its review of the application. The purpose of this SAND report is to provide the authors responses to each RAI. SAND Report SAND2010-6106 containing the proposed changes to the Addendum is provided separately.

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

467

SRS - ARRA General Provisions and Related Documents  

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

468

Formal Safety analysis of a radio-based railroad crossing using Deductive Cause-Consequence  

E-Print Network [OSTI]

and effects analysis (FMEA) and fault tree analysis (FTA). We apply the method to a real world case study like FMEA [10], FMECA [4] and FTA [3]. The logical framework of DCCA may be used to rigorously verify of what can by analyzed) than traditional FMEA. We show, that the results of DCCA have the same semantics

Reif, Wolfgang

469

Safety Analysis of an Airbag System Using Probabilistic FMEA and Probabilistic Counterexamples  

Science Journals Connector (OSTI)

Failure mode and effects analysis (FMEA) isa technique to reason about possible system hazards thatresult from system or system component failures. Traditionally, FMEA does not take the probabilities with which these failures may occur into account. ... Keywords: Probabilistic FMEA, Stochastic Modelling, Stochastic Model Checking, Counter Examples in Stochastic Model Checking, Dependability Analysis

Husain Aljazzar; Manuel Fischer; Lars Grunske; Matthias Kuntz; Florian Leitner-Fischer; Stefan Leue

2009-09-01T23:59:59.000Z

470

Reliability analysis of safety-related digitalinstrumentation and controlin a nuclear power plant.  

E-Print Network [OSTI]

?? There is so far no consensus on how to develop a reliability model of safety-related digitalinstrumentation and control (I&C) in a probabilistic safety assessment (more)

Gustafsson, Johan

2012-01-01T23:59:59.000Z

471

Implementation of Revision 19 of the TRUPACT-II Safety Analysis Report at Rocky Flats Environmental Technology Site  

SciTech Connect (OSTI)

The U.S. Nuclear Regulatory Commission on July 27, 2001 approved Revision 19 of the TRUPACT-II Safety Analysis Report (SAR) and the associated TRUPACT-II Authorized Methods for Payload Control (TRAMPAC). Key initiatives in Revision 19 included matrix depletion, unlimited mixing of shipping categories, a flammability assessment methodology, and an alternative methodology for the determination of flammable gas generation rates. All U.S. Department of Energy (DOE) sites shipping transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) were required to implement Revision 19 methodology into their characterization and waste transportation programs by May 20, 2002. An implementation process was demonstrated by the Rocky Flats Environmental Technology Site (RFETS) in Golden, Colorado. The three-part process used by RFETS included revision of the site-specific TRAMPAC, an evaluation of the contact-handled TRU waste inventory against the regulations in Revision 19, and design and development of software to facilitate future inventory analyses.

D'Amico, E.; O'Leary, J.; Bell, S.; Djordjevic, S.; Givens, C,; Shokes, T.; Thompson, S.; Stahl, S.

2003-02-25T23:59:59.000Z

472

Toolbox Safety Talk Safety Data Sheets (SDS)  

E-Print Network [OSTI]

Toolbox Safety Talk Safety Data Sheets (SDS) Environmental Health & Safety Facilities Safety-in sheet to Environmental Health & Safety for recordkeeping. Chemical manufacturers are required to produce Safety Data Sheets (SDS) for all chemicals produced. "Safety Data Sheets", previously referred

Pawlowski, Wojtek

473

Public Safety Public Safety Center  

E-Print Network [OSTI]

and bring someone with you or visit a grocery store or gas station. Personal Safety Precautions Safety the police, or go di- rectly to the police station or Public Safety. Do not label keys with your name or any

474

Results from One- and Two- Phase Fluid Flow Calculations within the Preliminary Safety Analysis of the Gorleben Site - 13310  

SciTech Connect (OSTI)

Rock salt is one of the possible host rock formations for the disposal of high-level radioactive wastes in Germany. The Preliminary Safety Analysis of the Gorleben Site (Vorlaeufige Sicherheitsanalyse Gorleben, VSG) evaluates the long-term safety of a hypothetical repository in the salt dome of Gorleben, Germany. A mature repository concept and detailed knowledge of the site allowed a detailed process analysis within the project by numerical modeling of single-phase and two-phase flow. The possibility of liquid transport from the shafts to the emplacement drifts is one objective of the present study. Also, the implications of brine inflow on radionuclide transport and gas generation are investigated. Pressure build-up due to rock convergence and gas generation, release of volatile radionuclides from the waste and pressure-driven contaminant transport were considered, too. The study confirms that the compaction behavior of salt grit backfill is one of the most relevant factors for the hydrodynamic evolution of the repository and the transport of contaminants. Due to the interaction between compaction, saturation and pore pressure, complex flow patterns evolve. Emplacement drifts serve as gas sinks or sources at different times. In most calculation cases, the backfill reaches its final porosity after a few hundred years. The repository is then sealed and radionuclides can only be transported by diffusion in the liquid phase. Estimates for the final porosity of compacted backfill range between 0 % and 2 %. The exact properties of the backfill regarding single- and two-phase flow are not well known for this porosity range. The study highlights that this uncertainty has a profound impact on flow and transport processes over long time-scales. Therefore, more research is needed to characterize the properties of crushed salt grit at low porosities or to reduce the adverse effects of possible higher porosities by repository optimization. (authors)

Kock, Ingo; Larue, Juergen; Fischer, Heidi; Frieling, Gerd; Navarro, Martin; Seher, Holger [Department of Final Disposal, GRS mbH, Schwertnergasse 1, 50667 Cologne (Germany)] [Department of Final Disposal, GRS mbH, Schwertnergasse 1, 50667 Cologne (Germany)

2013-07-01T23:59:59.000Z

475

Safety Culture | Department of Energy  

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

Safety Culture Safety Culture Safety Culture "DOE is committed to a strong and sustained safety culture, where all employees - from workers with shovels in the ground to their managers all the way up to the Secretary and everyone in between - are energetically pursuing the safe performance of work, encouraging a questioning work environment, and making sure that executing the mission safely is not just a policy statement but a value shared by all." - Secretary of Energy, Steven Chu Documents Available for Download May 23, 2013 An Independent Evaluation of Safety Culture at the U.S. Department of Energy Office of Health, Safety and Security- Headquarters This report describes the results of an independent evaluation of the existing safety culture at the U.S. Department of Energy Office of Health,

476

An empirical characterisation of electronic document navigation  

Science Journals Connector (OSTI)

To establish an empirical foundation for analysis and redesign of document navigation tools, we implemented a system that logs all user actions within Microsoft Word and Adobe Reader. We then conducted a four month longitudinal study of fourteen users' ... Keywords: document navigation, document use, event logging, scrolling

Jason Alexander; Andy Cockburn

2008-05-01T23:59:59.000Z

477

2013 Annual Workforce Analysis and Staffing Plan Report- Office of Health, Safety and Security  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

478

2012 Annual Workforce Analysis and Staffing Plan Report- Office of Health, Safety and Security  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

479

2011 Annual Workforce Analysis and Staffing Plan Report- Chief of Nuclear Safety  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

480

2011 Annual Workforce Analysis and Staffing Plan Report- Office of Health, Safety and Security  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

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.


481

2012 Annual Workforce Analysis and Staffing Plan Report- Chief of Nuclear Safety  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

482

2010 Annual Workforce Analysis and Staffing Plan Report- Chief of Nuclear Safety  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

483

Preliminary Study on Reliability Analysis of Safety I&C System in NPP  

Science Journals Connector (OSTI)

Digital instrumentation and control (I&C) systems, such as digital Reactor Protection System (RPS), are being employed ... upgraded Nuclear Power Plants (NPPs). The reliability analysis of digital I&C system turn...

Chao Guo; Duo Li; Huasheng Xiong

2012-01-01T23:59:59.000Z

484

2014 Annual Workforce Analysis and Staffing Plan Report- Office of Environment, Health, Safety and Security  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

485

2014 Annual Workforce Analysis and Staffing Plan Report- Chief of Nuclear Safety  

Broader source: Energy.gov [DOE]

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

486

Preservation of FFTF Data Related to Passive Safety Testing  

SciTech Connect (OSTI)

One of the goals of the Fuel Cycle Research and Development Program (FCRD) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMR). A key area deserving special attention for preservation is the data relating to passive safety testing that was conducted in FFTF and EBR-II during the 1980s. Accidents at Unit 4 of the Chernobyl Station and Unit 2 at Three Mile Island changed the safety paradigm of the nuclear power industry. New emphasis was placed on assured safety based on intrinsic plant characteristics that protect not only the public, but the significant investment in the plant as well. Plants designated to perform in this manner are considered to be passively safe since no active sensor/alarm system or human intervention is required to bring the reactor to a safe shutdown condition. The liquid metal reactor (LMR) has several key characteristics needed for a passively safe reactor: reactor coolant with superior heat transfer capability and very high boiling point, low (atmospheric) system pressures, and reliable negative reactivity feedback. The credibility of the design for a passively safe LMR rests on two issues: the validity of analytic methods used to predict passive safety performance and the availability of relevant test data to calibrate design tools. Safety analysis methods used to analyze LMRs under the old safety paradigm were focused on calculating the source term for the Core Disruptive Accident. Passive safety design requires refined analysis methods for transient events because treatment of the detailed reactivity feedbacks is important in predicting the response of the reactor. Similarly, analytic tools should be calibrated against actual test experience in existing LMR facilities. The principal objectives of the combined FFTF natural circulation and Passive Safety Testing program were: 1) to verify natural circulation as a reliable means to safely remove decay heat, 2) to extend passive safety experience to a large-size LMR and obtain data for validating design analysis computer codes, and 3) to develop and test passive safety enhancements that might be used for future LMRs. These tests were designed to provide data sufficient to allow separation of fuel temperature effects from structural temperature effects. The data developed through this testing program were used to verify the predictive capability of passive safety analysis methods as well as provide a data base for calibrating design tools such as the SASSYS/SAS4A codes. These tests were instrumental in improving understanding of reactivity feedback mechanisms in LMRs and demonstrating passive safety margins available in an LMR. Knowledge preservation at the FFTF is focused on the areas of design, construction, startup, and operation of the reactor. This information may be of potential use for international exchanges with other LMR programs around the world. This information provides the basis for creating benchmarks for validating and testing large scale computer programs. All information preserved to date is now being stored and categorized consistent with the IAEA international standardized taxonomy. The test results information exists in several different formats depending upon the final stage of the test evaluation. Over 100 documents relevant to passive safety testing have been identified and are being recovered, scanned, and catalogued. Attempts to recover plant data tapes are also in progress. Documents related to passive safety testing are now being categorized consistent with internationally agreed upon IAEA standards. Documents are being converted to electronic format compatible with a general search engine being developed by INL. The data from the FFTF passive safety tests provides experimental verification of structural reactivity effects that should be very useful to innovative designers seeking to optimize passive safety in the design of new LMRs.

Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.

2010-10-01T23:59:59.000Z

487

Control of External Documents  

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

488

Cryogenic safety  

Science Journals Connector (OSTI)

Cryogenic safety ... Examines the properties of cryogenic fluids and hazards associated with their use and storage. ...

Eric W. Spencer

1964-01-01T23:59:59.000Z

489

ANALYSIS OF SAFETY RELIEF VALVE PROOF TEST DATA TO OPTIMIZE LIFECYCLE MAINTENANCE COSTS  

SciTech Connect (OSTI)

Proof test results were analyzed and compared with a proposed life cycle curve or hazard function and the limit of useful life. Relief valve proof testing procedures, statistical modeling, data collection processes, and time-in-service trends are presented. The resulting analysis of test data allows for the estimation of the PFD. Extended maintenance intervals to the limit of useful life as well as methodologies and practices for improving relief valve performance and reliability are discussed. A generic cost-benefit analysis and an expected life cycle cost reduction concludes that $90 million maintenance dollars might be avoided for a population of 3000 valves over 20 years.

Gross, Robert; Harris, Stephen

2007-08-01T23:59:59.000Z

490

Facility Safety  

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

The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

2000-11-20T23:59:59.000Z

491

FAQS Qualification Card - Occupational Safety | Department of Energy  

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

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