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Note: This page contains sample records for the topic "facilities safety board" 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

Interface with the Defense Nuclear Facilities Safety Board  

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

The manual defines the process DOE will use to interface with the Defense Nuclear Facilities Safety Board and its staff. Canceled by DOE M 140.1-1A. Does not cancel other directives.

1996-12-30T23:59:59.000Z

2

Interface with the Defense Nuclear Facilities Safety Board  

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

This Manual presents the process the Department of Energy will use to interface with the Defense Nuclear Facilities Safety Board (DNFSB) and its staff. Cancels DOE M 140.1-1A.

2001-03-30T23:59:59.000Z

3

Interface with the Defense Nuclear Facilities Safety Board  

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

This Manual presents the process the Department of Energy will use to interface with the Defense Nuclear Facilities Safety Board (DNFSB) and its staff. Cancels DOE M 140.1-1.

1999-01-26T23:59:59.000Z

4

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

5

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

6

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

7

Independent Activity Report, Defense Nuclear Facilities Safety...  

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

Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October...

8

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 1998  

SciTech Connect (OSTI)

This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department`s defense nuclear facilities. The locations of the major Department facilities are provided. During 1998, Departmental activities resulted in the proposed closure of one Board recommendation. In addition, the Department has completed all implementation plan milestones associated with four other Board recommendations. Two new Board recommendations were received and accepted by the Department in 1998, and two new implementation plans are being developed to address these recommendations. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, a renewed effort to increase the technical capabilities of the federal workforce, and a revised plan for stabilizing excess nuclear materials to achieve significant risk reduction.

NONE

1999-02-01T23:59:59.000Z

9

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999  

SciTech Connect (OSTI)

This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted in the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

None

2000-02-01T23:59:59.000Z

10

Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000  

SciTech Connect (OSTI)

This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

None

2001-03-01T23:59:59.000Z

11

Facility Safety  

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

This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

2005-12-22T23:59:59.000Z

12

Facility Safety  

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

The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

2005-12-22T23:59:59.000Z

13

Facility Safety  

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

The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

2012-12-04T23:59:59.000Z

14

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. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

1995-10-13T23:59:59.000Z

15

Facility Safety  

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

To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

2002-05-20T23:59:59.000Z

16

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

17

FACILITY SAFETY (FS)  

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

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...

18

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.

19

Office of Nuclear Facility Safety Programs  

Broader source: Energy.gov [DOE]

The Office of Nuclear Facility Safety Programs establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities.

20

Defense Nuclear Facility Safety Board  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed Newcatalyst phasesData Files Data Files 1B&W Y-12studies in ionand Minor8, 2014

Note: This page contains sample records for the topic "facilities safety board" 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

Facility Safety - DOE Directives, Delegations, and Requirements  

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

Change, Safety, The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety,...

22

Safety of Accelerator Facilities - DOE Directives, Delegations...  

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

Health, Environmental Protection, Facility Authorization, Safety The order defines accelerators and establishes accelerator specific safety requirements and approval authorities...

23

FACILITY SAFETY (FS)  

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

and effectively implemented, with line management responsibility for control of safety. (Old Core Requirement 11) Criteria 1. Operations and support personnel fully...

24

FACILITY SAFETY (FS)  

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

- (Core Requirements 4 and 6) Sufficient numbers of qualified personnel are available to conduct and support operations. Adequate facilities and equipment are available to ensure...

25

Safety of Accelerator Facilities  

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

To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2A. Certified 5-13-08. Canceled by DOE O 420.2C.

2004-07-23T23:59:59.000Z

26

Safety of Accelerator Facilities  

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

To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2. Canceled by DOE O 420.2B.

2001-01-08T23:59:59.000Z

27

Safety of Accelerator Facilities  

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

The order defines accelerators and establishes accelerator specific safety requirements and approval authorities which, when supplemented by other applicable safety and health requirements, promote safe operations to ensure protection of workers, the public, and the environment. Cancels DOE O 420.2B.

2011-07-21T23:59:59.000Z

28

CRAD, Facility Safety- Unreviewed Safety Question Requirements  

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 Unreviewed Safety Question (USQ) process.

29

CRAD, Facility Safety- Technical Safety Requirements  

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 Technical Safety Requirments (TSA).

30

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

31

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

32

Safety of magnetic fusion facilities: Requirements  

SciTech Connect (OSTI)

This Standard identifies safety requirements for magnetic fusion facilities. Safety functions are used to define outcomes that must be achieved to ensure that exposures to radiation, hazardous materials, or other hazards are maintained within acceptable limits. Requirements applicable to magnetic fusion facilities have been derived from Federal law, policy, and other documents. In addition to specific safety requirements, broad direction is given in the form of safety principles that are to be implemented and within which safety can be achieved.

NONE

1996-05-01T23:59:59.000Z

33

Facility Safety Plan CMS Complexes CMS410  

SciTech Connect (OSTI)

Laboratory management requires that the controls specified in this Facility Safety Plan (FSP) be applied to efficiently and safely perform operations within these facilities. Any operation conducted in these facilities that involves activities not commonly performed by the public, requires an Integrated Work Sheet to determine the appropriate level of safety documentation.

Cooper, G

2007-06-14T23:59:59.000Z

34

Facility Safety (9-23-10)--Withdrawn  

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

Withdrawn, 5-19-2014--This approval includes revision of the three implementing Guides: DOE G 420.1-1, Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety; DOE G 420.1-2, Guide for the Mitigation of Natural Phenomena Hazards for DOE Nuclear Facilities and NonNuclear Facilities; and DOE G 420.1-3, Implementation Guide for DOE Fire Protection and Emergency Services Programs for Use with DOE O 420.1B, Facility Safety

2010-09-23T23:59:59.000Z

35

Charter for the ARM Climate Research Facility Science Board  

SciTech Connect (OSTI)

The objective of the ARM Science Board is to promote the Nation’s scientific enterprise by ensuring that the best quality science is conducted at the DOE’s User Facility known as the ARM Climate Research Facility. The goal of the User Facility is to serve scientific researchers by providing unique data and tools to facilitate scientific applications for improving understanding and prediction of climate science.

Ferrell, W

2013-03-08T23:59:59.000Z

36

Hot Cell Facility (HCF) Safety Analysis Report  

SciTech Connect (OSTI)

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

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

2000-11-01T23:59:59.000Z

37

Idaho Waste Treatment Facility Improves Worker Safety and Efficiency...  

Office of Environmental Management (EM)

Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer...

38

Nano Research Facility Lab Safety Manual Nano Research Facility  

E-Print Network [OSTI]

1 Nano Research Facility Lab Safety Manual Nano Research Facility: Weining Wang Office: Brauer rules and procedures (a) Accidents and spills for chemicals Not containing Nano-Materials Spills of non for chemicals Containing Nano-Materials In a fume hood small spills of nano-materials in a liquid may

Subramanian, Venkat

39

Occupational Safety Review of High Technology Facilities  

SciTech Connect (OSTI)

This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.

Lee Cadwallader

2005-01-31T23:59:59.000Z

40

Safety of magnetic fusion facilities: Guidance  

SciTech Connect (OSTI)

This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities.

NONE

1996-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "facilities safety board" 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

Office of Nuclear Safety Basis and Facility Design  

Broader source: Energy.gov [DOE]

The Office of Nuclear Safety Basis & Facility Design establishes safety basis and facility design requirements and expectations related to analysis and design of nuclear facilities to ensure protection of workers and the public from the hazards associated with nuclear operations.

42

Safety of Decommissioning of Nuclear Facilities  

SciTech Connect (OSTI)

Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

Batandjieva, B.; Warnecke, E.; Coates, R. [International Atomic Energy Agency, Vienna (Austria)

2008-01-15T23:59:59.000Z

43

Mechanistic facility safety and source term analysis  

SciTech Connect (OSTI)

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

PLYS, M.G.

1999-06-09T23:59:59.000Z

44

Facility Safety | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomentheATLANTA, GA5 &of EnergyOrganizationtotalFacility Representative AwardIn

45

National Ignition Facility Project Site Safety Program  

SciTech Connect (OSTI)

This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES&H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES&H requirements are consistent with the ''LLNL ES&H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B.

Dun, C

2003-09-30T23:59:59.000Z

46

CRAD, Safety Basis - Idaho MF-628 Drum Treatment Facility | Department...  

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

CRAD, Occupational Safety & Health - Idaho MF-628 Drum Treatment Facility CRAD, Conduct of Operations - Idaho MF-628 Drum Treatment Facility CRAD, Management - Idaho...

47

Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety  

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

This Guide provides guidance on the application of requirements for nonreactor nuclear facilities and explosives facilities of Department of Energy (DOE) O 420.1, Facility Safety, Section 4.1, Nuclear and Explosives Safety Design Criteria. No cancellation.

2000-03-28T23:59:59.000Z

48

CRAD, Nuclear Facility Safety System- September 25, 2009  

Broader source: Energy.gov [DOE]

Nuclear Facility Safety System Functionality Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-17, Rev 0 )

49

CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect (OSTI)

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the CHF is included in the Q-List (BSC 2005 [DIRS 171190], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

C.E. Sanders

2005-04-07T23:59:59.000Z

50

Compressed Gas Safety for Experimental Fusion Facilities  

SciTech Connect (OSTI)

Experimental fusion facilities present a variety of hazards to the operators and staff. There are unique or specialized hazards, including magnetic fields, cryogens, radio frequency emissions, and vacuum reservoirs. There are also more general industrial hazards, such as a wide variety of electrical power, pressurized air and cooling water systems in use, there are crane and hoist loads, working at height, and handling compressed gas cylinders. This paper outlines the projectile hazard associated with compressed gas cylinders and methods of treatment to provide for compressed gas safety. This information should be of interest to personnel at both magnetic and inertial fusion experiments.

Cadwallader, L.C. [Idaho National Engineering and Environmental Laboratory (United States)

2005-05-15T23:59:59.000Z

51

Compressed Gas Safety for Experimental Fusion Facilities  

SciTech Connect (OSTI)

Experimental fusion facilities present a variety of hazards to the operators and staff. There are unique or specialized hazards, including magnetic fields, cryogens, radio frequency emissions, and vacuum reservoirs. There are also more general industrial hazards, such as a wide variety of electrical power, pressurized air, and cooling water systems in use, there are crane and hoist loads, working at height, and handling compressed gas cylinders. This paper outlines the projectile hazard assoicated with compressed gas cylinders and mthods of treatment to provide for compressed gas safety. This information should be of interest to personnel at both magnetic and inertial fusion experiments.

Lee C. Cadwallader

2004-09-01T23:59:59.000Z

52

Safety Plan for County and District Personnel and Facilities  

E-Print Network [OSTI]

Safety Plan for County and District Personnel and Facilities Table of Contents Purpose and Scope of the Plan 2 Governance and Safety Committees Defined 2 Part I: Accident Reporting and Investigation 4 Processes 5 · Additional Training Resources 6 Part III: Safety Requirements for WSU Extension Facilities 7

Collins, Gary S.

53

NEW - DOE O 420.1 Chg 1, Facility Safety  

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

The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. This Page Change is limited in scope to changes necessary to invoke DOE-STD-1104, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Document, and revised DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis as required methods. DOE O 420.1C Chg 1, dated 2-27-15, cancels DOE O 420.1C, dated 12-4-12.

54

Accelerator Facility Safety Implementation Guide for DOE O 420.2B, Safety of Accelerator Facilities  

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

This document is an aid to understanding and meeting the requirements of DOE O 420.2B, Safety of Accelerator Facilities, dated 7/23/04. It does not impose requirements beyond those stated in that Order or any other DOE Order. No cancellation.

2005-07-01T23:59:59.000Z

55

Safety Culture And Best Practices At Japan's Fusion Research Facilities  

SciTech Connect (OSTI)

The Safety Monitor Joint Working Group (JWG) is one of the magnetic fusion research collaborations between the US Department of Energy and the government of Japan. Visits by occupational safety personnel are made to participating institutions on a biennial basis. In the 2013 JWG visit of US representatives to Japan, the JWG members noted a number of good safety practices in the safety walkthroughs. These good practices and safety culture topics are discussed in this paper. The JWG hopes that these practices for worker safety can be adopted at other facilities. It is a well-known, but unquantified, safety principle that well run, safe facilities are more productive and efficient than other facilities (Rule, 2009). Worker safety, worker productivity, and high quality in facility operation all complement each other (Mottel, 1995).

Rule, K. [Princeton Plasma Physics Lab., Princeton, NJ (United States); King, M. [General Atomics, San Diego, CA (United States); Takase, Y. [Univ. of Tokyo (Japan); Oshima, Y. [Univ. of Tokyo (Japan); Nishimura, K. [National Institute for Fusion Science, Toki (Japan); Sukegawa, A. [Japan Atomic Energy Agency, Naka (Japan)

2014-04-01T23:59:59.000Z

56

Safety Culture and Best Practices at Japan's Fusion Research Facilities  

SciTech Connect (OSTI)

The Safety Monitor Joint Working Group (JWG) is one of the magnetic fusion research collaborations between the US Department of Energy and the government of Japan. Visits by occupational safety personnel are made to participating institutions on a biennial basis. In the 2013 JWG visit of US representatives to Japan, the JWG members noted a number of good safety practices in the safety walkthroughs. These good practices and safety culture topics are discussed in this paper. The JWG hopes that these practices for worker safety can be adopted at other facilities. It is a well-known, but unquantified, safety principle that well run, safe facilities are more productive and efficient than other facilities (Rule, 2009). Worker safety, worker productivity, and high quality in facility operation all complement each other (Mottel, 1995).

Rule, Keith [PPPL

2014-05-01T23:59:59.000Z

57

Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review...  

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

Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions Name: Organization: Directions: This is an open-book evaluation. Complete the...

58

Safety analysis report for the Waste Storage Facility. Revision 2  

SciTech Connect (OSTI)

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

Bengston, S.J.

1994-05-01T23:59:59.000Z

59

Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)  

SciTech Connect (OSTI)

In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the software. The discussion provided herein illustrates benefits of applying the Safety Software Guide to work activities dependent on software applications and directed toward the design of new nuclear facilities. In particular, the Guide-based systematic approach with software enables design processes to effectively proceed and reduce the likelihood of rework activities. Several application examples are provided for the new facility.

VINCENT, Andrew

2005-07-14T23:59:59.000Z

60

Criticality Safety Evaluation of Hanford Tank Farms Facility  

SciTech Connect (OSTI)

Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

WEISS, E.V.

2000-12-15T23:59:59.000Z

Note: This page contains sample records for the topic "facilities safety board" 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

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

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

Technical Safety Requirements - December 2, 2014 (EA CRAD 31-07, Rev. 0) More Documents & Publications CRAD, Nuclear Reactor Facility Operations - December 4, 2014 (EA CRAD 31-08...

62

CRAD, Occupational Safety & Health- Idaho MF-628 Drum Treatment Facility  

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) used for a February 2006 Commencement of Operations assessment of the Occupational Safety and Industrial Hygiene programs at the MF-628 Drum Treatment Facility at the Idaho National Laboratory Advanced Mixed Waste Treatment Project.

63

Safety of magnetic fusion facilities: Volume 2, Guidance  

SciTech Connect (OSTI)

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

NONE

1995-07-01T23:59:59.000Z

64

Facility Safety - DOE Directives, Delegations, and Requirements  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series toESnet4:Epitaxial ThinFOR IMMEDIATE5Facilities SomeFacilitiesFacility0.1C

65

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

66

Integration of Environment, Safety, and Health into Facility Disposition Activities  

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

Volume One of this Standard has been revised to provide a Department of Energy (DOE) approved methodology for preparing a Documented Safety Analysis (DSA) for decommissioning of nuclear facilities, as well as environmental restoration activities that involve work not done within a permanent structure. Methodologies provided in this Standard are intended to be compliant with Title 10 of the Code of Federal Regulations (CFR) Part 830, Nuclear Safety Management, Subpart B, Safety Basis Requirements. Volume Two contains the appendices that provide additional environment, safety and health (ES&H) information to complement Volume 1 of this Standard. Volume 2 of the Standard is much broader in scope than Volume 1 and satisfies several purposes. Integrated safety management expectations are provided in accordance with facility disposition requirements contained in DOE O 430.1B, Real Property Asset Management.

1998-05-01T23:59:59.000Z

67

Facility Safety (For Informational Purposes Only)  

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

This draft has been scheduled for final review before the Directives Review Board on 12/18/14. All major comments and concerns should be provided to your DRB representative, following your organization process. If you do not know who your representative is, please see the list of DRB members. If your office is represented by Ingrid Kolb, Director, Office of Management, please submit your major concerns and comments to the DRB Liaison, Camille Beben (Camille.Beben@hq.doe.gov; 202-586-1014). All major comments and concerns should be submitted by COB 12/16/2014.

2014-12-04T23:59:59.000Z

68

Nonreactor Nuclear Safety Design Guide for use with DOE O 420.1C, Facility Safety  

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

This Guide provides an acceptable approach for safety design of DOE hazard category 1, 2 and 3 nuclear facilities for satisfying the requirements of DOE O 420.1C. Cancels DOE G 420.1-1.

2012-12-04T23:59:59.000Z

69

Defense Nuclear Facilities Safety Board (DNFSB) Letters and Recommendations  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecember 2005Department ofDOE AccidentWasteZone Modeling | DepartmentDeep Vadose|

70

Departmental Representative to the Defense Nuclear Facilities Safety Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecember 2005Department ofDOE AccidentWasteZone

71

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartment ofThe full text of what isAnalysisMeeting - October

72

Defense Nuclear Facilities Safety Board (DNFSB) Update - Dale Govan,  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office of Audit Services Audit Report Department ofDecoupling and UtilityDeepwater

73

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

74

Facility Safety - DOE Directives, Delegations, and Requirements  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicy andExsolutionFES6FY 2011Facility Engineering

75

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010  

Broader source: Energy.gov [DOE]

On August 12, 2009, the Defense Nuclear Facilities Safety Board(DNFSB) issued Recommendation 2009?1, Risk Assessment Methodologies at Defense Nuclear Facilities. Thisrecommendation focused on the...

76

Facility Siting and Layout Optimization Based on Process Safety  

E-Print Network [OSTI]

) that identifies potential layouts by minimizing overall costs. This approach gives the coordinates of each facility in a continuous plane, and estimates for the total length of pipes, the land area, and the selection of safety devices. Finally, the 3D...

Jung, Seungho

2012-02-14T23:59:59.000Z

77

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect (OSTI)

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6. This Introduction to the WASTE STORAGE FACILITIES TSRs is not part of the TSR limits or conditions and contains no requirements related to WASTE STORAGE FACILITIES operations or to the safety analyses of the DSA.

Larson, H L

2007-09-07T23:59:59.000Z

78

Documented Safety Analysis for the Waste Storage Facilities  

SciTech Connect (OSTI)

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

Laycak, D

2008-06-16T23:59:59.000Z

79

Documented Safety Analysis for the Waste Storage Facilities March 2010  

SciTech Connect (OSTI)

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

Laycak, D T

2010-03-05T23:59:59.000Z

80

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect (OSTI)

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6.

Laycak, D T

2008-06-16T23:59:59.000Z

Note: This page contains sample records for the topic "facilities safety board" 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

Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6  

SciTech Connect (OSTI)

In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (``the Panel``) handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel`s caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel`s judges and licensing boards.

NONE

1995-08-01T23:59:59.000Z

82

Construction safety program for the National Ignition Facility Appendix A: Safety Requirements  

SciTech Connect (OSTI)

These rules apply to all LLNL employees, non-LLNL employees (including contract labor, supplemental labor, vendors, personnel matrixed/assigned from other National Laboratories, participating guests, visitors and students) and construction contractors/subcontractors. The General Safety and Health rules shall be used by management to promote accident prevention through indoctrination, safety and health training and on-the-job application. As a condition for contracts award, all contractors and subcontractors and their employees must certify on Form S & H A-1 that they have read and understand, or have been briefed and understand, the National Ignition Facility OCIP Project General Safety Rules.

Cerruti, S.J.

1997-01-14T23:59:59.000Z

83

TRANSPORTATION CASK RECEIPT/RETURN FACILITY CRITICALITY SAFETY EVALUATIONS  

SciTech Connect (OSTI)

The purpose of this design calculation is to demonstrate that the handling operations of transportation casks performed in the Transportation Cask Receipt and Return Facility (TCRRF) and Buffer Area meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC [Bechtel SAIC Company] 2004 [DIRS 171599], Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''Transportation Cask Receipt/Return Facility Description Document'' (BSC 2004 [DIRS 170217], Section 3.2.3). Specific scope of work contained in this activity consists of the following items: (1) Evaluate criticality effects for both dry and fully flooded conditions pertaining to TCRRF and Buffer Area operations for defense in depth. (2) Evaluate Category 1 and 2 event sequences for the TCRRF as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). This evaluation includes credible fuel reconfiguration conditions. In addition to the scope of work listed above, an evaluation was also performed of modeling assumptions for commercial spent nuclear fuel (CSNF) regarding inclusion of plenum and end regions of the active fuel. This calculation is limited to CSNF and US Department of Energy (DOE) SNF. it should be mentioned that the latter waste form is evaluated more in depth in the ''Canister Handling Facility Criticality Safety Calculations (BSC 2004 [DIRS 167614]). Further, the design and safety analyses of the naval SNF canisters are the responsibility of the US Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the TCRRF and Buffer Area and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the TCRRF is included in the Q-List (BSC 2004 [DIRS 168361], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

C.E. Sanders

2005-04-26T23:59:59.000Z

84

Impacts of criticality safety on hot fuel examination facility operations  

SciTech Connect (OSTI)

The Hot Fuel Examination Facility (HFEF) complex comprises four large hot cells. These cells are used to support the nation's nuclear energy program, especially the liquid-metal fast breeder reactor, by providing nondestructive and destructive testing of irradiated reactor fuels and furnishing the hot cell services required for operation of Experimental Breeder Reactor II (EBR-II). Because it is a research rather than a production facility, HFEF assignments are varied and change from time to time to meet the requirements of our experimenters. Such a variety of operations presents many challenges, especially for nuclear criticality safety. The following operations are reviewed to assure that accidental criticality is not possible, and that all rules and regulations are met: transportation, temporary storage, examinations, and disposition.

Garcia, A.S.; Courtney, J.C.; Bacca, J.P.

1985-11-01T23:59:59.000Z

85

The Fast Flux Test Facility built on safety  

SciTech Connect (OSTI)

No other high-tech industry has grown as fast as the nuclear industry. The information available to the general public has not kept pace with the rapid growth of nuclear data---its growth has outpaced its media image and the safety of nuclear facilities has become a highly debated issue. This book is an attempt to bridge the gap between the high-tech information of the nuclear industry and its understanding by the general public. It explains the three levels of defense at the Fast Flux Test Facility (FFTF) and why these levels provide an acceptable margin to protect the general public and on-site personnel, while achieving FFTF's mission to provide research and development for the US Department of Energy (DOE).

Not Available

1989-01-01T23:59:59.000Z

86

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

87

Advanced Test Reactor (ATR) Facility 10CFR830 Safety Basis Related to Facility Experiments  

SciTech Connect (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Test Reactor (ATR), a DOE Category A reactor, was designed to provide an irradiation test environment for conducting a variety of experiments. The ATR Safety Analysis Report, determined by DOE to meet the requirements of 10 CFR 830, Subpart B, provides versatility in types of experiments that may be conducted. This paper addresses two general types of experiments in the ATR facility and how safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore this type of experiment is addressed with more detail in the safety basis. This allows individual safety analyses for these experiments to be more routine and repetitive. The second type of experiment is less defined and is permitted under more general controls. Therefore, individual safety analyses for the second type of experiment tend to be more unique from experiment to experiment. Experiments are also discussed relative to "major modifications" and DOE-STD-1027-92. Application of the USQ process to ATR experiments is also discussed.

Tomberlin, Terry Alan

2002-06-01T23:59:59.000Z

88

Advanced Test Reactor (ATR) Facility 10CFR830 Safety Basis Related to Facility Experiments  

SciTech Connect (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Test Reactor (ATR), a DOE Category A reactor, was designed to provide an irradiation test environment for conducting a variety of experiments. The ATR Safety Analysis Report, determined by DOE to meet the requirements of 10 CFR 830, Subpart B, provides versatility in types of experiments that may be conducted. This paper addresses two general types of experiments in the ATR facility and how safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore this type of experiment is addressed with more detail in the safety basis. This allows individual safety analyses for these experiments to be more routine and repetitive. The second type of experiment is less defined and is permitted under more general controls. Therefore, individual safety analyses for the second type of experiment tend to be more unique from experiment to experiment. Experiments are also discussed relative to ''major modifications'' and DOE-STD-1027-92. Application of the USQ process to ATR experiments is also discussed.

Tomberlin, T.A.

2002-06-19T23:59:59.000Z

89

Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities  

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

This standard provides a framework for generating Criticality Safety Evaluations (CSE) supporting fissionable material operations at Department of Energy (DOE) nonreactor nuclear facilities. This standard imposes no new criticality safety analysis requirements.

2007-02-07T23:59:59.000Z

90

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

91

National ignition facility environment, safety, and health management plan  

SciTech Connect (OSTI)

The ES&H Management Plan describes all of the environmental, safety, and health evaluations and reviews that must be carried out in support of the implementation of the National Ignition Facility (NIF) Project. It describes the policy, organizational responsibilities and interfaces, activities, and ES&H documents that will be prepared by the Laboratory Project Office for the DOE. The only activity not described is the preparation of the NIF Project Specific Assessment (PSA), which is to be incorporated into the Programmatic Environmental Impact Statement for Stockpile Stewardship and Management (PEIS). This PSA is being prepared by Argonne National Laboratory (ANL) with input from the Laboratory participants. As the independent NEPA document preparers ANL is directly contracted by the DOE, and its deliverables and schedule are agreed to separately with DOE/OAK.

NONE

1995-11-01T23:59:59.000Z

92

Nuclear space power safety and facility guidelines study  

SciTech Connect (OSTI)

This report addresses safety guidelines for space nuclear reactor power missions and was prepared by The Johns Hopkins University Applied Physics Laboratory (JHU/APL) under a Department of Energy grant, DE-FG01-94NE32180 dated 27 September 1994. This grant was based on a proposal submitted by the JHU/APL in response to an {open_quotes}Invitation for Proposals Designed to Support Federal Agencies and Commercial Interests in Meeting Special Power and Propulsion Needs for Future Space Missions{close_quotes}. The United States has not launched a nuclear reactor since SNAP 10A in April 1965 although many Radioisotope Thermoelectric Generators (RTGs) have been launched. An RTG powered system is planned for launch as part of the Cassini mission to Saturn in 1997. Recently the Ballistic Missile Defense Office (BMDO) sponsored the Nuclear Electric Propulsion Space Test Program (NEPSTP) which was to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source in space. As of late 1993 the flight portion of this program was canceled but work to investigate the attributes of the reactor were continued but at a reduced level. While the future of space nuclear power systems is uncertain there are potential space missions which would require space nuclear power systems. The differences between space nuclear power systems and RTG devices are sufficient that safety and facility requirements warrant a review in the context of the unique features of a space nuclear reactor power system.

Mehlman, W.F.

1995-09-11T23:59:59.000Z

93

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

SciTech Connect (OSTI)

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

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

1995-03-01T23:59:59.000Z

94

Improving the regulation of safety at DOE nuclear facilities. Final report  

SciTech Connect (OSTI)

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by DOE itself. The three major recommendations are: under any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

NONE

1995-12-01T23:59:59.000Z

95

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices  

SciTech Connect (OSTI)

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

NONE

1995-12-01T23:59:59.000Z

96

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

97

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities  

SciTech Connect (OSTI)

This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24.

Not Available

1993-11-01T23:59:59.000Z

98

FACILITY SAFETY PLAN Department of Chemical and Biological Engineering  

E-Print Network [OSTI]

Glover Building SAFETY OFFICE: ADMINISTRATIVE OFFICE ROOM 100 GLOVER PHONE 491-5252 Emergency Numbers

99

Policy Name: Bicycle, Rollerblade, Scooter ad Skate Board Policy Originating/Responsible Department: Department of University Safety  

E-Print Network [OSTI]

Policy Name: Bicycle, Rollerblade, Scooter ad Skate Board Policy Originating/Responsible Department of University Safety Policy: The University encourages the use of bicycles, rollerblades, scooters for the use of bicycles, roller blades, scooters and skateboards on campus. Purpose: The purpose

100

Policy Name: Bicycle, Rollerblade, Scooter ad Skate Board Policy Originating/Responsible Department: Department of University Safety  

E-Print Network [OSTI]

Policy Name: Bicycle, Rollerblade, Scooter ad Skate Board Policy Originating/Responsible Department Safety Policy: The University encourages the use of bicycles, rollerblades, scooters and skateboards for the use of bicycles, roller blades, scooters and skateboards on campus. Purpose: The purpose

Carleton University

Note: This page contains sample records for the topic "facilities safety board" 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

Design and Development of an ADC/DAC Evaluation Board for NIJ Public Safety Radio  

E-Print Network [OSTI]

present all the input/output ports of the ADC/DAC board. 2 #12;A PROGRAM OF THE NATIONAL INSTITUTE to implement on a 4-layer PCB ADC ~ $21 (1k), DAC ~ $10 (1k) Figure 2: Image of ADC/DAC board. ADC/DAC Board Rx/Tx Board Overview IB DAC Output ADC Input ADI Interface to FPGA Board EXT_CLK_DAC CLK_ADC IA QB QA IA IB QB

Ellingson, Steven W.

102

340 Waste handling Facility Hazard Categorization and Safety Analysis  

SciTech Connect (OSTI)

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

T. J. Rodovsky

2010-10-25T23:59:59.000Z

103

Chemical Waste Guide for Facilities Services UW Environmental Health and Safety  

E-Print Network [OSTI]

CChemmical Fa Was aciliti Au te G ies S ugust uide Servic t 24, 2 for ces 2011 #12;Chemical Waste Guide for Facilities Services UW Environmental Health and Safety Page 2 Chemical Waste Guide ........................................................................................................... 3 Chemical Hazards

Wilcock, William

104

Safety Analysis Report: X17B2 beamline Synchrotron Medical Research Facility  

SciTech Connect (OSTI)

This report contains a safety analysis for the X17B2 beamline synchrotron medical research facility. Health hazards, risk assessment and building systems are discussed. Reference is made to transvenous coronary angiography. (LSP)

Gmuer, N.F.; Thomlinson, W.

1990-02-01T23:59:59.000Z

105

Construction safety program for the National Ignition Facility, Appendix A  

SciTech Connect (OSTI)

Topics covered in this appendix include: General Rules-Code of Safe Practices; 2. Personal Protective Equipment; Hazardous Material Control; Traffic Control; Fire Prevention; Sanitation and First Aid; Confined Space Safety Requirements; Ladders and Stairways; Scaffolding and Lift Safety; Machinery, Vehicles, and Heavy Equipment; Welding and Cutting-General; Arc Welding; Oxygen/Acetylene Welding and Cutting; Excavation, Trenching, and Shoring; Fall Protection; Steel Erection; Working With Asbestos; Radiation Safety; Hand Tools; Electrical Safety; Nonelectrical Work Performed Near Exposed High-Voltage Power-Distribution Equipment; Lockout/Tagout Requirements; Rigging; A-Cranes; Housekeeping; Material Handling and Storage; Lead; Concrete and Masonry Construction.

Cerruti, S.J.

1997-06-26T23:59:59.000Z

106

Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities  

SciTech Connect (OSTI)

This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

Garvin, L.J.

1995-11-01T23:59:59.000Z

107

CRAD, Criticality Safety- Y-12 Enriched Uranium Operations Oxide Conversion Facility  

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) used for a January 2005 assessment of the Criticality Safety program at the Y-12 - Enriched Uranium Facility.

108

CRAD, Occupational Safety & Health- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility  

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) used for an assessment of the Occupational and Industrial Safety and Hygiene Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

109

CRAD, Occupational Safety & Health- Y-12 Enriched Uranium Operations Oxide Conversion Facility  

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) used for a January 2005 assessment of Industrial Safety and Industrial Health programs at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility.

110

CRAD, Safety Basis- Y-12 Enriched Uranium Operations Oxide Conversion Facility  

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) used for a January 2005 assessment of the Safety Basis at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility.

111

Superconducting Magnet Safety Nuclear Magnetic Resonance (NMR) facilities present unique hazards not found in most  

E-Print Network [OSTI]

Superconducting Magnet Safety Nuclear Magnetic Resonance (NMR) facilities present unique hazards not found in most laboratory environments. The NMR facilities maintain superconducting magnets which have for asphyxiation. Once energized the field of the superconducting magnet of the spectrometer is always present

Maroncelli, Mark

112

CRAD, Criticality Safety- Los Alamos National Laboratory TA 55 SST Facility  

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) used for an assessment of the Criticality Safety program at the Los Alamos National Laboratory, TA 55 SST Facility.

113

Construction safety program for the National Ignition Facility, Appendix B  

SciTech Connect (OSTI)

This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety.

Cerruti, S.J.

1997-06-26T23:59:59.000Z

114

Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade  

SciTech Connect (OSTI)

The regulatory requirement to develop an upgraded safety basis for a DOE nuclear facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830).1 Subpart B of 10 CFR 830, “Safety Basis Requirements,” requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements.1 10 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants”2 as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology that was developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830.

Gregg L. Sharp; R. T. McCracken

2003-06-01T23:59:59.000Z

115

Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade  

SciTech Connect (OSTI)

The regulatory requirement to develop an upgraded safety basis for a DOE Nuclear Facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830). Subpart B of 10 CFR 830, ''Safety Basis Requirements,'' requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements. 10 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, ''Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants'' as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology that was developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830.

Sharp, G.L.; McCracken, R.T.

2003-05-13T23:59:59.000Z

116

Type A Accident Investigation Board report on the January 17, 1996, electrical accident with injury in Technical Area 21 Tritium Science and Fabrication Facility Los Alamos National Laboratory. Final report  

SciTech Connect (OSTI)

An electrical accident was investigated in which a crafts person received serious injuries as a result of coming into contact with a 13.2 kilovolt (kV) electrical cable in the basement of Building 209 in Technical Area 21 (TA-21-209) in the Tritium Science and Fabrication Facility (TSFF) at Los Alamos National Laboratory (LANL). In conducting its investigation, the Accident Investigation Board used various analytical techniques, including events and causal factor analysis, barrier analysis, change analysis, fault tree analysis, materials analysis, and root cause analysis. The board inspected the accident site, reviewed events surrounding the accident, conducted extensive interviews and document reviews, and performed causation analyses to determine the factors that contributed to the accident, including any management system deficiencies. Relevant management systems and factors that could have contributed to the accident were evaluated in accordance with the guiding principles of safety management identified by the Secretary of Energy in an October 1994 letter to the Defense Nuclear Facilities Safety Board and subsequently to Congress.

NONE

1996-04-01T23:59:59.000Z

117

Accelerator Facility Safety Implementation Guide for DOE Order (0) 420.2C, Safety of Accelerator Facilities  

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

The revision will address implementation of roles and responsibilities, improve operational efficiency using operating experience, and clarify the use of program requirements such as the Unreviewed Safety Issue and Accelerator Readiness Review.

2013-07-17T23:59:59.000Z

118

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

119

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

120

Facility Safety Policy, Guidance & Reports | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecember 2005DepartmentDecember U.S. Department-5 METRIC SUMMARYFacility Safety

Note: This page contains sample records for the topic "facilities safety board" 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

Spent nuclear fuel project cold vacuum drying facility safety equipment list  

SciTech Connect (OSTI)

This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved.

IRWIN, J.J.

1999-02-24T23:59:59.000Z

122

Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

Timothy Solack; Carol Mason

2012-03-01T23:59:59.000Z

123

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard  

SciTech Connect (OSTI)

This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

NONE

1998-05-01T23:59:59.000Z

124

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-02-01T23:59:59.000Z

125

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-05-01T23:59:59.000Z

126

Management of radioactive material safety programs at medical facilities. Final report  

SciTech Connect (OSTI)

A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

Camper, L.W.; Schlueter, J.; Woods, S. [and others

1997-05-01T23:59:59.000Z

127

Revision of the RFIC Board for NIJ Public Safety S.M. Shajedul Hasan  

E-Print Network [OSTI]

12 C Layout 19 Bradley Dept. of Electrical & Computer Engineering, 432 Durham Hall, Virginia to build a another prototype MMR, which will be more compact and will have less cable connections. Hence just two boards for the present study using the quickest manufacturing time, the PCB fabrication

Ellingson, Steven W.

128

The dual axis radiographic hydrodynamic test (DARHT) facility personnel safety system (PSS) control system  

SciTech Connect (OSTI)

The mission of the Dual Axis Radiograph Hydrodynamic Test (DARHT) Facility is to conduct experiments on dynamic events of extremely dense materials. The PSS control system is designed specifically to prevent personnel from becoming exposed to radiation and explosive hazards during machine operations and/or the firing site operation. This paper will outline the Radiation Safety System (RSS) and the High Explosive Safety System (HESS) which are computer-controlled sets of positive interlocks, warning devices, and other exclusion mechanisms that together form the PSS.

Jacquez, Edward B [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

129

DOE Order Self Study Modules - DOE O 420.1B Facility Safety  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Deliciouscritical_materials_workshop_presentations.pdf MoreProgram |DOEInfrastructure Working420.1B FACILITY SAFETY

130

NNSA and Defense Nuclear Facilities Safety Board certifications free up $47  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | National Nuclear Security Administration Weaponsmillion in

131

Peer review of the National Transportation Safety Board structural analysis of the I-35W bridge collapse.  

SciTech Connect (OSTI)

The Engineering Sciences Center at Sandia National Laboratories provided an independent peer review of the structural analysis supporting the National Transportation Safety Board investigation of the August 1, 2007 collapse of the I-35W Bridge in Minneapolis. The purpose of the review was to provide an impartial critique of the analysis approach, assumptions, solution techniques, and conclusions. Subsequent to reviewing numerous supporting documents, a SNL team of staff and management visited NTSB to participate in analysis briefings, discussions with investigators, and examination of critical elements of the bridge wreckage. This report summarizes the opinion of the review team that the NTSB analysis effort was appropriate and provides compelling supporting evidence for the NTSB probable cause conclusion.

Gwinn, Kenneth West; Redmond, James Michael; Wellman, Gerald William

2008-10-01T23:59:59.000Z

132

Documented Safety Analysis Addendum for the Neutron Radiography Reactor Facility Core Conversion  

SciTech Connect (OSTI)

The Neutron Radiography Reactor Facility (NRAD) is a Training, Research, Isotope Production, General Atomics (TRIGA) reactor which was installed in the Idaho National Laboratory (INL) Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) in the mid 1970s. The facility provides researchers the capability to examine both irradiated and non-irradiated materials in support of reactor fuel and components programs through non-destructive neutron radiography examination. The facility has been used in the past as one facet of a suite of reactor fuels and component examination facilities available to researchers at the INL and throughout the DOE complex. The facility has also served various commercial research activities in addition to the DOE research and development support. The reactor was initially constructed using Fuel Lifetime Improvement Program (FLIP)- type highly enriched uranium (HEU) fuel obtained from the dismantled Puerto Rico Nuclear Center (PRNC) reactor. In accordance with international non-proliferation agreements, the NRAD core will be converted to a low enriched uranium (LEU) fuel and will continue to utilize the PRNC control rods, control rod drives, startup source, and instrument console as was previously used with the HEU core. The existing NRAD Safety Analysis Report (SAR) was created and maintained in the preferred format of the day, combining sections of both DOE-STD-3009 and Nuclear Regulatory Commission Regulatory Guide 1.70. An addendum was developed to cover the refueling and reactor operation with the LEU core. This addendum follows the existing SAR format combining required formats from both the DOE and NRC. This paper discusses the project to successfully write a compliant and approved addendum to the existing safety basis documents.

Boyd D. Christensen

2009-05-01T23:59:59.000Z

133

Facility Safety  

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

Changes include invoking DOE-STD-3009 and DOE-STD-1104 as requirements documents. NOTE: The two standards are not final documents but can be found in Technical Standards RevCom at https://www.standards.doe.gov/login.jsp. Login as an SME using your email address.

2014-06-25T23:59:59.000Z

134

Hanford Advisory Board Draft Advice Topic: Tank Farm Vapors...  

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

Health Safety and Environmental Protection (HSEP) Version 1 : Color: pinkyellowgreensalmonpurpleXblue Background The Hanford Advisory Board (Board) has always...

135

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

136

"Defense-in-Depth" Laser Safety and the National Ignition Facility  

SciTech Connect (OSTI)

The National Ignition Facility (NIF) is the largest and most energetic laser in the world contained in a complex the size of a football stadium. From the initial laser pulse, provided by telecommunication style infrared nanoJoule pulsed lasers, to the final 192 laser beams (1.8 Mega Joules total energy in the ultraviolet) converging on a target the size of a pencil eraser, laser safety is of paramount concern. In addition to this, there are numerous high-powered (Class 3B and 4) diagnostic lasers in use that can potentially send their laser radiation travelling throughout the facility. With individual beam paths of up to 1500 meters and a workforce of more than one thousand, the potential for exposure is significant. Simple laser safety practices utilized in typical laser labs just don't apply. To mitigate these hazards, NIF incorporates a multi layered approach to laser safety or 'Defense in Depth.' Most typical high-powered laser operations are contained and controlled within a single room using relatively simplistic controls to protect both the worker and the public. Laser workers are trained, use a standard operating procedure, and are required to wear Personal Protective Equipment (PPE) such as Laser Protective Eyewear (LPE) if the system is not fully enclosed. Non-workers are protected by means of posting the room with a warning sign and a flashing light. In the best of cases, a Safety Interlock System (SIS) will be employed which will 'safe' the laser in the case of unauthorized access. This type of laser operation is relatively easy to employ and manage. As the operation becomes more complex, higher levels of control are required to ensure personnel safety. Examples requiring enhanced controls are outdoor and multi-room laser operations. At the NIF there are 192 beam lines and numerous other Class 4 diagnostic lasers that can potentially deliver their hazardous energy to locations far from the laser source. This presents a serious and complex potential hazard to personnel. Because of this, a multilayered approach to safety is taken. This paper presents the philosophy and approach taken at the NIF in the multi-layered 'defense-in-depth' approach to laser safety.

King, J J

2010-12-02T23:59:59.000Z

137

Safety and licensing issues that are being addressed by the Power Burst Facility test programs. [PWR; BWR  

SciTech Connect (OSTI)

This paper presents an overview of the results of the experimental program being conducted in the Power Burst Facility and the relationship of these results to certain safety and licensing issues. The safety issues that were addressed by the Power-Cooling-Mismatch, Reactivity Initiated Accident, and Loss of Coolant Accident tests, which comprised the original test program in the Power Burst Facility, are discussed. The resolution of these safety issues based on the results of the thirty-six tests performed to date, is presented. The future resolution of safety issues identified in the new Power Burst Facility test program which consists of tests which simulate BWR and PWR operational transients, anticipated transients without scram, and severe fuel damage accidents, is described.

McCardell, R.K.; MacDonald, P.E.

1980-01-01T23:59:59.000Z

138

Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities  

SciTech Connect (OSTI)

This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

2011-03-13T23:59:59.000Z

139

FAST FLUX TEST FACILITY (FFTF) A HISTORY OF SAFETY & OPERATIONAL EXCELLENCE  

SciTech Connect (OSTI)

The Fast Flux Test Facility (FFTF) is a 400-megawatt (thermal) sodium-cooled, high temperature, fast neutron flux, loop-type test reactor. The facility was constructed to support development and testing of fuels, materials and equipment for the Liquid Metal Fast Breeder Reactor program. FFTF began operation in 1980 and over the next 10 years demonstrated its versatility to perform experiments and missions far beyond the original intent of its designers. The reactor had several distinctive features including its size, flux, core design, extensive instrumentation, and test features that enabled it to simultaneously carry out a significant array of missions while demonstrating its features that contributed to a high level of plant safety and availability. FFTF is currently being deactivated for final closure.

NIELSEN, D L

2004-02-26T23:59:59.000Z

140

Use of Administrative Controls for Specific Safety Functions, 10/21/03.  

Broader source: Energy.gov [DOE]

On December 11,2002, the Defense Nuclear Facilities Safety Board issued Recommendation 2002-3. Recommendation 2002-3 noted concerns about the lack of rigor and quality assurance accorded some...

Note: This page contains sample records for the topic "facilities safety board" 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

Office of Health, Safety and Security Report to the Secretary of Energy- February 2011  

Broader source: Energy.gov [DOE]

Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1

142

Safety Basis Requirements for Nonnuclear Facilities at Lawrence Livermore National Laboratory Site-Specific Work Smart Standards Revision 1  

SciTech Connect (OSTI)

This standard establishes requirements that, when coupled with Lawrence Livermore National Laboratory's (LLNL's) Integrated Safety Management System (ISMS) methods and other Work Smart Standards for assuring worker safety, assure that the impacts of nonnuclear operations authorized in LLNL facilities are well understood and controlled in a manner that protects the health of workers, the public, and the environment. All LLNL facilities shall be classified based on potential for adverse impact of operations to the health of co-located (i.e., nearby) workers and the public in accordance with this standard, Title 10 Code of Federal Regulations (10 CFR) 830, Subpart B, and Department of Energy Order (DOE O) 420.2A. This standard provides information on: Objectives; Applicability; Safety analysis requirements; Control selection and maintenance; Documentation requirements; Safety basis review, approval, and renewal; and Safety basis implementation.

Beach, R; Brereton, S; Failor, R; Hildum, S; Spagnolo, S; Van Warmerdam, C

2003-02-24T23:59:59.000Z

143

Environmental Management Waste Management Facility (EMWMF) Site-Specific Health and Safety Plan, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Bechtel Jacobs Company LLC (BJC) policy is to provide a safe and healthy workplace for all employees and subcontractors. The implementation of this policy requires that operations of the Environmental Management Waste Management Facility (EMWMF), located one-half mile west of the U.S. Department of Energy (DOE) Y-12 National Security Complex, be guided by an overall plan and consistent proactive approach to environment, safety and health (ES&H) issues. The BJC governing document for worker safety and health, BJC/OR-1745, 'Worker Safety and Health Program', describes the key elements of the BJC Safety and Industrial Hygiene (IH) programs, which includes the requirement for development and implementation of a site-specific Health and Safety Plan (HASP) where required by regulation (refer also to BJC-EH-1012, 'Development and Approval of Safety and Health Plans'). BJC/OR-1745, 'Worker Safety and Health Program', implements the requirements for worker protection contained in Title 10 Code of Federal Regulations (CFR) Part 851. The EMWMF site-specific HASP requirements identifies safe operating procedures, work controls, personal protective equipment, roles and responsibilities, potential site hazards and control measures, site access requirements, frequency and types of monitoring, site work areas, decontamination procedures, and outlines emergency response actions. This HASP will be available on site for use by all workers, management and supervisors, oversight personnel and visitors. All EMWMF assigned personnel will be briefed on the contents of this HASP and will be required to follow the procedures and protocols as specified. The policies and procedures referenced in this HASP apply to all EMWMF operations activities. In addition the HASP establishes ES&H criteria for the day-to-day activities to prevent or minimize any adverse effect on the environment and personnel safety and health and to meet standards that define acceptable waste management practices. The HASP is written to make use of past experience and best management practices to eliminate or minimize hazards to workers or the environment from events such as fires, falls, mechanical hazards, or any unplanned release to the environment.

Flynn, N.C. Bechtel Jacobs

2008-04-21T23:59:59.000Z

144

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

145

Type A Accident Investigation Board Report on the January 17, 1996, Electrical Accident With Injury in Building 209, Technical Area 21, Tritium Science and Fabrication Facility, Los Alamos National Laboratory  

Broader source: Energy.gov [DOE]

This report is an independent product of the Type A Accident Investigation Board appointed by Tara O’Toole, M.D., M.P.H., Assistant Secretary for Environment, Safety and Health (EH-1).

146

Safety Assessment for the Kozloduy National Disposal Facility in Bulgaria - 13507  

SciTech Connect (OSTI)

Due to the early decommissioning of four Water-Water Energy Reactors (WWER) 440-V230 reactors at the Nuclear Power Plant (NPP) near the city of Kozloduy in Bulgaria, large amounts of low and intermediate radioactive waste will arise much earlier than initially scheduled. In or-der to manage the radioactive waste from the early decommissioning, Bulgaria has intensified its efforts to provide a near surface disposal facility at Radiana with the required capacity. To this end, a project was launched and assigned in international competition to a German-Spanish consortium to provide the complete technical planning including the preparation of the Intermediate Safety Assessment Report. Preliminary results of operational and long-term safety show compliance with the Bulgarian regulatory requirements. The long-term calculations carried out for the Radiana site are also a good example of how analysis of safety assessment results can be used for iterative improvements of the assessment by pointing out uncertainties and areas of future investigations to reduce such uncertainties in regard to the potential radiological impact. The computer model used to estimate the long-term evolution of the future repository at Radiana predicted a maximum total annual dose for members of the critical group, which is carried to approximately 80 % by C-14 for a specific ingestion pathway. Based on this result and the outcome of the sensitivity analysis, existing uncertainties were evaluated and areas for reasonable future investigations to reduce these uncertainties were identified. (authors)

Biurrun, E.; Haverkamp, B. [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany)] [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany); Lazaro, A.; Miralles, A. [Westinghouse Electric Spain SAR, Padilla 17, E-28006 Madrid (Spain)] [Westinghouse Electric Spain SAR, Padilla 17, E-28006 Madrid (Spain); Stefanova, I. [SERAW, 52 A Dimitrov Blvd, 6 Fl., 1797 Sofia (Bulgaria)] [SERAW, 52 A Dimitrov Blvd, 6 Fl., 1797 Sofia (Bulgaria)

2013-07-01T23:59:59.000Z

147

Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor  

SciTech Connect (OSTI)

This report describes the EG&G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options.

Ryskamp, J.M. [ed.; Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

1992-07-01T23:59:59.000Z

148

Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor  

SciTech Connect (OSTI)

This report describes the EG G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options.

Ryskamp, J.M. (ed.); Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

1992-07-01T23:59:59.000Z

149

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites  

SciTech Connect (OSTI)

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.

Zull, Lawrence M.; Yeniscavich, William [Defense Nuclear Facilities Safety Board, 625 Indiana Ave., NW, Suite 700, Washington, DC 20004-2901 (United States)

2008-01-15T23:59:59.000Z

150

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

151

SHSD Manager Safety Engineering Group Manager  

E-Print Network [OSTI]

Safety, Machine Shop Safety, Tier I Program, Traffic Safety S. Moss: Nuclear Criticality Safety G. Shepherd: Explosives Safety, Facility Authorization Basis, Nuclear Safety R. Travis: Readiness Evaluations

152

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

SciTech Connect (OSTI)

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

Not Available

1993-01-01T23:59:59.000Z

153

An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility  

SciTech Connect (OSTI)

The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

P. Calderoni; P. Sharpe; M. Shimada

2009-09-01T23:59:59.000Z

154

Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities  

SciTech Connect (OSTI)

To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

Donovan, G.L.; Goldstein, S.A.

1986-12-01T23:59:59.000Z

155

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

156

U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)  

Broader source: Energy.gov [DOE]

"This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak...

157

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...

158

Nuclear Safety Regulatory Framework  

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

overall Nuclear Safety Policy & ESH Goals Safety Basis Review and Approval In the DOE governance model, contractors responsible for the facility develop the safety basis and...

159

Technical safety requirements (TSR) for waste receiving and processing (WRAP) facility  

SciTech Connect (OSTI)

The scope of this TSR document is based on the WRAP Final Safety Analysis Report (HNF-SD-W026-SAR-002) and supporting documents. The administrative controls set forth in this TSR document are derived from the WRAP Final Safety Analysis Report.

Weidert, J.R.

1997-11-18T23:59:59.000Z

160

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

Note: This page contains sample records for the topic "facilities safety board" 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

CRAD, Occupational Safety & Health- Los Alamos National Laboratory TA 55 SST Facility  

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) used for an assessment of the Industrial Hygiene program at the Los Alamos National Laboratory TA 55 SST Facility.

162

Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII  

SciTech Connect (OSTI)

Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

Not Available

1980-01-01T23:59:59.000Z

163

Criticality Safety Evaluation Report for the Cold Vacuum Drying (CVD) Facilities Process Water Handling System  

SciTech Connect (OSTI)

This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified.

KESSLER, S.F.

2000-08-10T23:59:59.000Z

164

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

165

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents  

SciTech Connect (OSTI)

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

166

Waste Receiving and Processing (WRAP) Facility Final Safety Analysis Report (FSAR)  

SciTech Connect (OSTI)

The Waste Receiving and Processing Facility (WRAP), 2336W Building, on the Hanford Site is designed to receive, confirm, repackage, certify, treat, store, and ship contact-handled transuranic and low-level radioactive waste from past and present U.S. Department of Energy activities. The WRAP facility is comprised of three buildings: 2336W, the main processing facility (also referred to generically as WRAP); 2740W, an administrative support building; and 2620W, a maintenance support building. The support buildings are subject to the normal hazards associated with industrial buildings (no radiological materials are handled) and are not part of this analysis except as they are impacted by operations in the processing building, 2336W. WRAP is designed to provide safer, more efficient methods of handling the waste than currently exist on the Hanford Site and contributes to the achievement of as low as reasonably achievable goals for Hanford Site waste management.

TOMASZEWSKI, T.A.

2000-04-25T23:59:59.000Z

167

Observation challenges in a glovebox environment : behavior based safety at a plutonium facility.  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) is one of the Nation's leading scientific and defense laboratories, owned by the Department of Energy and managed by the University of California. LANL is one of the original weapons complex labs dating back to the days of the Manhattan Project during World War II. Since then, radioactive materials research has continued at LANLs Plutonium Facility, and remains a primary responsibility of the Laboratory. The Nuclear Materials Technology Division (NMT) is a multidisciplinary organization responsible for daily operations of the Plutonium Facility and the Chemistry Research Metallurgy Facility. NMT Division is responsible for the saence, engineering and technology of plutonium and other actinides in support of the Nation's nuclear weapons stockpile, nuclear materials disposition, and nuclear energy programs. A wide amy of activities are performed within NMT Division, such as analytical chemistry, metallurgical operations, actinide processes, waste operations, radioactive materials research and related administrative tasks.

Montalvo, M. L. (Maryrose L.)

2002-01-01T23:59:59.000Z

168

Safety Software Quality Assurance Functions, Responsibilities, and Authorities for Nuclear Facilities and Activities  

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

To assign roles and responsibilities for improving the quality of safety software. DOE N 411.2 (archived) extends this Notice until 01/31/2005. DOE N 411.3 extends this Notice until 1/31/06. Canceled by DOE O 414.1C. does not cancel other directives.

2003-08-27T23:59:59.000Z

169

Report on the American Nuclear Society International Topical Meeting: {open_quotes}The safety, status, and future of non-commercial reactors and irradiation Facilities{close_quotes}  

SciTech Connect (OSTI)

The American Nuclear Society`s International Topical Meeting, The Safety, Status, and Future of Non-Commercial Reactors and Irradiation Facilities, also known as SAFOR 90, was held in Boise, Idaho, September 30 to October 4, 1990. In 19 half-day sessions, 102 papers were presented which covered operating research reactors, production reactors, the use of reactors for training and research, probabilistic risk assessments applied to research reactors, plans for new facilities, and new fuels and reactor types. A special session on space reactor safety was also presented. 11 refs., 1 tab.

Silver, E.G. [Oak Ridge National Laboratory, TN (United States)

1991-01-01T23:59:59.000Z

170

Safety aspects related to the operation of the Cabril L/ILW disposal facility  

SciTech Connect (OSTI)

In October 1992 the Spanish Ministry of Industry granted the operating permit to the Centro de Almacenamiento de El Cabril (C.A. El Cabril). The Annex 1 to this permit contains the limits and conditions related to safety and to radiological health protection, set by nuclear regulatory authority, the Consejo de Seguridad Nuclear (CSN). The main aspects of the operation regulated in the permit as well as their technical basis and practical meaning are discussed in this paper.

Ruiz, M.C. [Consejo de Seguridad Nuclear, Madrid (Spain); Alonso, J.A. [ENRESA, Madrid (Spain). Safety and Licensing Dept.

1993-12-31T23:59:59.000Z

171

Cost-effective facility disposition planning with safety and health lessons learned and good practices from the Oak Ridge Decontamination and Decommissioning Program  

SciTech Connect (OSTI)

An emphasis on transition and safe disposition of DOE excess facilities has brought about significant challenges to managing worker, public, and environmental risks. The transition and disposition activities involve a diverse range of hazardous facilities that are old, poorly maintained, and contain radioactive and hazardous substances, the extent of which may be unknown. In addition, many excess facilities do not have historical facility documents such as operating records, plant and instrumentation diagrams, and incident records. The purpose of this report is to present an overview of the Oak Ridge Decontamination and Decommissioning (D and D) Program, its safety performance, and associated safety and health lessons learned and good practices. Illustrative examples of these lessons learned and good practices are also provided. The primary focus of this report is on the safety and health activities and implications associated with the planning phase of Oak Ridge facility disposition projects. Section 1.0 of this report provides the background and purpose of the report. Section 2.0 presents an overview of the facility disposition activities from which the lessons learned and good practices discussed in Section 3.0 were derived.

NONE

1998-05-01T23:59:59.000Z

172

Toolbox Safety Talk Articulating Boom Work Platforms  

E-Print Network [OSTI]

Toolbox Safety Talk Articulating Boom Work Platforms Environmental Health & Safety Facilities sign-in sheet to Environmental Health & Safety for recordkeeping. Articulating boom work platforms Articulating Boom Work Platforms Environmental Health & Safety Facilities Safety & Health Section 395 Pine Tree

Pawlowski, Wojtek

173

Evaluation of the US Department of Energy's occupational safety and health program for its government-owned contractor-operated facilities  

SciTech Connect (OSTI)

The purpose of this report is to present to Secretary of Energy James Watkins the findings and recommendations of the Occupational Safety and Health Administration's (OSHA) evaluation of the Department of Energy's (DOE) programs for worker safety and health at DOE's government-owned contractor-operated (GOCO) nuclear facilities. The OSHA evaluation is based on an intensive and comprehensive review and analysis of DOE's worker safety and health programs including: written programs; safety and health inspection programs; and the adequacy of resource, training, and management controls. The evaluation began on April 10, 1990 and involved over three staff years before its conclusion. The evaluation was initiated by former Secretary of Labor Elizabeth Dole in response to Secretary of Energy James Watkins' request that OSHA assist him in determining the actions needed to assure that DOE has an exemplary safety and health program in place at its GOCOs. 6 figs.

Not Available

1990-12-01T23:59:59.000Z

174

ORNL results for Test Case 1 of the International Atomic Energy Agency`s research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities  

SciTech Connect (OSTI)

The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled ```The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.`` The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test Case 1: a simple earth trench and an engineered vault.

Thorne, D.J.; McDowell-Boyer, L.M.; Kocher, D.C.; Little, C.A. [Oak Ridge National Lab., Grand Junction, CO (United States); Roemer, E.K. [Oak Ridge Inst. for Science and Education, TN (United States)

1993-07-01T23:59:59.000Z

175

Toolbox Safety Talk Hot Work Safety Procedures  

E-Print Network [OSTI]

Toolbox Safety Talk Hot Work Safety Procedures Environmental Health & Safety Facilities Safety-in sheet to Environmental Health & Safety for recordkeeping. "Hot Work" is defined as any temporary WORK Obtain a hot work permit from your supervisor or safety rep. Ensure fire/smoke detection

Pawlowski, Wojtek

176

Toolbox Safety Talk Machine Shop Safety  

E-Print Network [OSTI]

Toolbox Safety Talk Machine Shop Safety Environmental Health & Safety Facilities Safety & Health to Environmental Health & Safety for recordkeeping. Machine shops are an integral part of the Cornell University be taken seriously. Many of the most frequently cited OSHA safety standards pertain to machine safeguarding

Pawlowski, Wojtek

177

E-Print Network 3.0 - advisory board gustav Sample Search Results  

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

Ride Safety Advisory Board Could not Contact 1 Animal Health and Diagnostic Commission... Armstrong County Board of Assistance 1 Asian ... Source: Sibille, Etienne - Center for the...

178

E-Print Network 3.0 - advisory board savannah Sample Search Results  

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

Ride Safety Advisory Board Could not Contact 1 Animal Health and Diagnostic Commission... Armstrong County Board of Assistance 1 Asian ... Source: Sibille, Etienne - Center for the...

179

E-Print Network 3.0 - advisory board paducah Sample Search Results  

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

Ride Safety Advisory Board Could not Contact 1 Animal Health and Diagnostic Commission... Armstrong County Board of Assistance 1 Asian ... Source: Sibille, Etienne - Center for the...

180

E-Print Network 3.0 - advisory board public Sample Search Results  

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

Ride Safety Advisory Board Could not Contact 1 Animal Health and Diagnostic Commission... Armstrong County Board of Assistance 1 Asian ... Source: Sibille, Etienne - Center for the...

Note: This page contains sample records for the topic "facilities safety board" 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

E-Print Network 3.0 - advisory board osteoporosis Sample Search...  

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

Ride Safety Advisory Board Could not Contact 1 Animal Health and Diagnostic Commission... Armstrong County Board of Assistance 1 Asian ... Source: Sibille, Etienne - Center for the...

182

E-Print Network 3.0 - advisory board portsmouth Sample Search...  

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

Ride Safety Advisory Board Could not Contact 1 Animal Health and Diagnostic Commission... Armstrong County Board of Assistance 1 Asian ... Source: Sibille, Etienne - Center for the...

183

E-Print Network 3.0 - advisory board shun-ichi Sample Search...  

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

Ride Safety Advisory Board Could not Contact 1 Animal Health and Diagnostic Commission... Armstrong County Board of Assistance 1 Asian ... Source: Sibille, Etienne - Center for the...

184

Pipeline Safety (Pennsylvania)  

Broader source: Energy.gov [DOE]

The Pennsylvania legislature has empowered the Public Utility Commission to direct and enforce safety standards for pipeline facilities and to regulate safety practices of certificated utilities...

185

Post-test analysis of dryout test 7B' of the W-1 Sodium Loop Safety Facility Experiment with the SABRE-2P code. [LMFBR  

SciTech Connect (OSTI)

An understanding of conditions that may cause sodium boiling and boiling propagation that may lead to dryout and fuel failure is crucial in liquid-metal fast-breeder reactor safety. In this study, the SABRE-2P subchannel analysis code has been used to analyze the ultimate transient of the in-core W-1 Sodium Loop Safety Facility experiment. This code has a 3-D simple nondynamic boiling model which is able to predict the flow instability which caused dryout. In other analyses dryout has been predicted for out-of-core test bundles and so this study provides additional confirmation of the model.

Rose, S.D.; Dearing, J.F.

1981-01-01T23:59:59.000Z

186

APS Experiment Safety Review Board  

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

work. The Committee will solicit other representatives to participate in standing or ad hoc subcommittees as deemed necessary. Committee members can solicit nominations of...

187

Safety Basis Requirements for Nonnuclear Facilities at Lawrence Livermore National Laboratory Site-Specific Work Smart Standard Revision 3 December 2006  

SciTech Connect (OSTI)

This standard establishes requirements that, when coupled with Lawrence Livermore National Laboratory's (LLNL's) Integrated Safety Management System (ISMS) methods and other Work Smart Standards for assuring worker safety, assure that the impacts of nonnuclear operations authorized in LLNL facilities are well understood and controlled in a manner that protects the health of workers, the public, and the environment. All LLNL facilities shall be classified based on potential for adverse impact of operations to the health of co-located (i.e., nearby) workers and the public in accordance with this standard, Title 10 Code of Federal Regulations (10 CFR) 830, Subpart B, and Department of Energy Order (DOE O) 420.2A.

Beach, D; Brereton, S; Failor, R; Hildum, J; Ingram, C; Spagnolo, S; van Warmerdam, C

2007-06-07T23:59:59.000Z

188

Toolbox Safety Talk Welding & Metal Work Safety  

E-Print Network [OSTI]

Toolbox Safety Talk Welding & Metal Work Safety Environmental Health & Safety Facilities Safety or harmful emission giving metals. Welding Safety When welding outside of a designated welding booth, ensure injury. Avoid welding on materials such as galvanized or stainless steel in order to minimize toxic fume

Pawlowski, Wojtek

189

FACILITY SAFETY (FS)  

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

actions, demonstrate a highpriority commitment to comply with these requirements. (Old Core Requirements 14 and 8) Criteria 1. A QA program has been approved by DOE and...

190

FACILITY SAFETY (FS)  

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

Criteria 1. A radiological protection program has been established and implemented. (10 CFR 830.204(b)(5); 10 CFR 835; DOE O 5400.5; DOE N 441.3) 2. The radiological protection...

191

FACILITY SAFETY (FS)  

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

and in place for supervisors, operators, support staff, and maintenance personnel. (10 CFR 830.204(b)(5); 10 CFR 830, Subpart A, Criterion 2) 2. Training and qualification...

192

Review of Nevada Site Office Criticality Safety Assessments at the Criticality Experiments Facility and Training Assembly for Criticality Safety and Appraisal of the Criticality Experiments Facility Startup Plan, October 2011  

Broader source: Energy.gov [DOE]

This report provides the results of an independent oversight review of criticality safety assessment activities conducted by the Department of Energy's (DOE) Nevada Site Office

193

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 1, Waste streams and treatment technologies  

SciTech Connect (OSTI)

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

194

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

Neupauer, R.M.; Thurmond, S.M.

1992-09-01T23:59:59.000Z

195

Nuclear Explosive Safety Manual - DOE Directives, Delegations...  

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

1A Admin Chg 1, Nuclear Explosive Safety Manual by Carl Sykes Functional areas: Administrative Change, Defense Nuclear Facility Safety and Health Requirement, Nuclear Safety,...

196

Waste minimization at a plutonium processing facility  

SciTech Connect (OSTI)

As part of Los Alamos National Laboratory`s (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management.

Pillay, K.K.S. [Los Alamos National Laboratory, NM (United States)

1995-12-31T23:59:59.000Z

197

Safety analysis report for the National Low-Temperature Neutron Irradiation Facility (NLTNIF) at the ORNL Bulk Shielding Reactor (BSR)  

SciTech Connect (OSTI)

This report provides information concerning: the experiment facility; experiment assembly; instrumentation and controls; materials; radioactivity; shielding; thermodynamics; estimated or measured reactivity effects; procedures; hazards; and quality assurance. (JDB)

Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.; Richardson, S.A.

1986-06-01T23:59:59.000Z

198

Conservator Animal Facility  

E-Print Network [OSTI]

. Research Compliance A.Rubenstein Radiation Safety Committee S. Sechrist Review Board G. Maihafer Applied & Licensing K.Abul-Hassan Licensing Associate R.Alsberry Coastal Phys. Ocean. J. Klinck Soc. Sci. Res. Center

199

Hazardous Waste Facility Siting Program (Maryland)  

Broader source: Energy.gov [DOE]

The Hazardous Waste Facilities Siting Board is responsible for overseeing the siting of hazardous waste facilities in Maryland, and will treat hazardous waste facilities separately from low-level...

200

Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11  

Broader source: Energy.gov [DOE]

During the 580th meeting of the Advisory Committee on Reactor Safeguards (ACRS), February10-12, 2011, we reviewed the staff’s white paper, “A Comparison of Integrated Safety Analysisand...

Note: This page contains sample records for the topic "facilities safety board" 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

Appendix A Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

39 Appendices Appendices #12;Appendix A Nuclear Waste Technical Review Board Members: Curricula to the Nuclear Waste Technical Review Board. President Clinton appointed Dr. Cohon chairman on January 17, 1997, and Asia and on energy facility siting, including nuclear waste ship- ping and storage. In addition to his

202

Appendix A Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

59 Appendices Appendices #12;Appendix A Nuclear Waste Technical Review Board Members: Curricula Cohon to serve on the Nuclear Waste Technical Review Board. President Clinton appointed Dr. Cohon, and Asia and on energy-facility siting, including nuclear waste shipping and storage. In addition to his

203

Pre-title I safety evaluation for the retrieval operations of transuranic waste drums in the Solid Waste Disposal Facility. Revision 2  

SciTech Connect (OSTI)

Phase I of the Transuranic (TRU) Waste Facility Line Item Project includes the retrieval and safe storage of the pad drums that are stored on TRU pads 2-6 in the Solid Waste Disposal Facility (SWDF). Drums containing TRU waste were placed on these pads as early as 1974. The pads, once filled, were mounded with soil. The retrieval activities will include the excavation of the soil, retrieval of the pad drums, placing the drums in overpacks (if necessary) and venting and purging the retrieved drums. Once the drums have been vented and purged, they will be transported to other pads within the SWDF or in a designated area until they are eventually treated as necessary for ultimate shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This safety evaluation provides a bounding assessment of the radiological risk involved with the drum retrieval activities to the maximally exposed offsite individual and the co-located worker. The results of the analysis indicate that the risk to the maximally exposed offsite individual and the co-located worker using maximum frequencies and maximum consequences are within the acceptance criteria defined in WSRC Procedural Manual 9Q. The purpose of this evaluation is to demonstrate the incremental risk from the SWDF due to the retrieval activities for use as design input only. As design information becomes available, this evaluation can be revised to satisfy the safety analysis requirements of DOE Orders 4700 and 5480.23.

Rabin, M.S.

1992-08-01T23:59:59.000Z

204

Toolbox Safety Talk Lock/Tag/Verify  

E-Print Network [OSTI]

Energy Environmental Health & Safety Facilities Safety & Health Section 395 Pine Tree Rd. Suite 210 Energy Environmental Health & Safety Facilities Safety & Health Section 395 Pine Tree Rd. Suite 210Toolbox Safety Talk Lock/Tag/Verify The Control of Hazardous Energy Environmental Health & Safety

Pawlowski, Wojtek

205

Workplace Responsibilities System Approved by Board of Governors on December 17, 2004 Workplace Safety and Environmental Protection Page 1 of 10  

E-Print Network [OSTI]

Responsibilities System is the University of Saskatchewan-specific "line management" model. The key to superior by an inspector. A "line management" system focuses on prevention rather than after-the-fact analysis and environment (HSE) law as the minimum benchmark to be met in regards to worker health and safety. 3. Workers

Saskatchewan, University of

206

Type B Investigation Board Report on the April 2, 2002, Worker Fall from Shoring/Scaffolding Structure at the Savannah River Site Tritium Extraction Facility Construction Site  

Broader source: Energy.gov [DOE]

On April 2, 2002, a carpenter helping to erect shoring/scaffolding fell about 52” and struck his head. He sustained head injuries requiring hospitalization that exceeded the threshold for a Type B investigation in accordance with Department of Energy (DOE) Order 225.1A, Accident Investigation. The accident occurred at the DOE’s Savannah River Site (SRS) at the Tritium Extraction Facility (TEF) construction site.

207

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...

208

2015 DOE Safety and Security Enforcement Workshop - Badging and...  

Office of Environmental Management (EM)

2015 DOE Safety and Security Enforcement Workshop - Badging and Facility Information 2015 DOE Safety and Security Enforcement Workshop - Badging and Facility Information January...

209

Nuclear Safety Basis Program Review Overview and Management Oversight...  

Office of Environmental Management (EM)

Nuclear Safety Basis Program Review During Facility Operations and Transitions Volume 4 - Nuclear Safety Basis Program Review During Facility Decommissioning and Environmental...

210

Rates for Alternate Energy Production Facilities (Iowa)  

Broader source: Energy.gov [DOE]

The Utilities Board may require public utilities furnishing gas, electricity, communications, or water to public consumers, to own alternate energy production facilities, enter into long-term...

211

CRAD, Radiological Controls - Idaho MF-628 Drum Treatment Facility...  

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

Safety & Health - Idaho MF-628 Drum Treatment Facility CRAD, Engineering - Idaho MF-628 Drum Treatment Facility CRAD, Conduct of Operations - Idaho MF-628 Drum Treatment Facility...

212

CRAD, Management - Idaho MF-628 Drum Treatment Facility | Department...  

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

- Idaho MF-628 Drum Treatment Facility CRAD, Occupational Safety & Health - Idaho MF-628 Drum Treatment Facility CRAD, Conduct of Operations - Idaho MF-628 Drum Treatment Facility...

213

SEAS Safety Program SEAS SAFETY PROGRAM 2013-2014  

E-Print Network [OSTI]

SEAS Safety Program SEAS SAFETY PROGRAM 2013-2014 Program Structure and Responsibilities Dr. Anas Chalah #12;SEAS Safety Program SEAS Safety Program Structure We have developed a great model of collaboration among · EHSEM · SEAS Safety Program · SEAS Facilities which accounts for the regulatory component

214

SEAS Safety Program SEAS SAFETY PROGRAM 2012-2103  

E-Print Network [OSTI]

SEAS Safety Program SEAS SAFETY PROGRAM 2012-2103 Program Structure and Responsibilities Dr. Anas Chalah #12;SEAS Safety Program SEAS Safety Program Structure We have developed a great model of collaboration among · EHSEM · SEAS Safety Program · SEAS Facilities which accounts for the regulatory component

215

Independent Oversight Assessment, Salt Waste Processing Facility...  

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

Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department...

216

Independent Oversight Inspection, Thomas Jefferson National Accelerator Facility- August 2008  

Broader source: Energy.gov [DOE]

Inspection of Environment, Safety and Health Programs at the Thomas Jefferson National Accelerator Facility

217

School Land Board (Texas)  

Broader source: Energy.gov [DOE]

The School Land Board oversees the use of land owned by the state or held in trust for use and benefit by the state or one of its departments, boards, or agencies. The Board is responsible for...

218

Nuclear Explosive Safety Evaluation Processes - DOE Directives...  

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

2 Admin Chg 1, Nuclear Explosive Safety Evaluation Processes by Carl Sykes Functional areas: Administrative Change, Defense Nuclear Facility Safety and Health Requirement, Defense...

219

RESEARCH SAFETY RADIATION SAFETY  

E-Print Network [OSTI]

RESEARCH SAFETY RADIATION SAFETY ENVIRONMENTAL PROGRAMS HAZARDOUS MATERIALS CONTROLLED SUBSTANCES INTEGRATED WASTE MANAGEMENT LABORATORY SAFETY AUDITS & COMPLIANCE BIOSAFETY and ENVIRONMENTAL HEALTH EMERGENCY MANAGEMENT and MISSION CONTINUITY FIRE PREVENTION and LIFE SAFETY GENERAL SAFETY TRAINING

220

BRIEFING NOTE SUMMARY OF MATTERS CONSIDERED BY THE MANAGEMENT BOARD  

E-Print Network [OSTI]

the System - would be crucial if the necessary improvements to the health and safety culture across Imperial for election to the Fellowship of the College and two for election to its Associateship. HEALTH AND SAFETY UPDATE 3. The Board noted that Professor John Wood would succeed Professor Smith as the College Safety

Note: This page contains sample records for the topic "facilities safety board" 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

FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS  

SciTech Connect (OSTI)

This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

GARVIN, L J; JENSEN, M A

2004-04-13T23:59:59.000Z

222

Microsoft PowerPoint - Janaskie, 4-27-10 SSAB Excess Facilities...  

Office of Environmental Management (EM)

Specific Advisory Board (SSAB): Advisory Board (SSAB): Transfer of Excess Facilities, Materials and Wastes Transfer of Excess Facilities, Materials and Wastes i t th Offi f E i t l...

223

DOE handbook electrical safety  

SciTech Connect (OSTI)

Electrical Safety Handbook presents the Department of Energy (DOE) safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety guidance and information for DOE installations to effect a reduction or elimination of risks associated with the use of electrical energy. The objectives of this handbook are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

NONE

1998-01-01T23:59:59.000Z

224

Electrical safety guidelines  

SciTech Connect (OSTI)

The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

Not Available

1993-09-01T23:59:59.000Z

225

UNBC Board of Governors Public Minutes March 24, 2012 Page 1 of 7 BOARD OF GOVERNORS -PUBLIC SESSION MINUTES  

E-Print Network [OSTI]

'". CARRIED 4. Business Arising a. Report on Utilization of Heat from Bio-energy Plant in First Year was requested at the last Board meeting. The University target to displace 85% of the natural gas used on campus and Safety Report This annual report was presented to the Board. 6. Finance and Audit Committee - Louise

Northern British Columbia, University of

226

Toolbox Safety Talk Woodworking Machines  

E-Print Network [OSTI]

Toolbox Safety Talk Woodworking Machines Environmental Health & Safety Facilities Safety & Health to Environmental Health & Safety for recordkeeping. Machine shops are an integral part of the Cornell University for many student courses and elective activities. Woodworking machines can pose a myriad of hazards

Pawlowski, Wojtek

227

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

, aging, and disposal (TAD) canister concept; and the repository safety case. Also included is a short of parameter correlations can enhance the technical credibility of TSPA. TAD Canister Concept The Board met in May to discuss DOE's proposed TAD canister concept. In a follow-up letter dated June 14, 2006

228

*****I* ****f?* Fusion Programme Evaluation Board  

E-Print Network [OSTI]

of the Community's programme in the field of Controlled Thermonuclear Fusion; to appraise the environmental, safety*****I* ****f?* Report of the Fusion Programme Evaluation Board prepared for the Commission . . . . . . . . . . . . 11 CHAPTER ONE: NUCLEAR FUSION AND ITS POTENTIAL CONTRIBUTION TO THE WORLD'S ENERGY NEEDS 1

229

Type B Accident Investigation Board Report of the Savannah River...  

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

Site Hand Injury at the Salt Waste Processing Facility on October 6, 2009 Type B Accident Investigation Board Report of the Savannah River Site Hand Injury at the Salt Waste...

230

Type B Accident Investigation Board Report Employee Puncture...  

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

F-TRU Waste Remediation Facility at the Savannah River Site on June 14, 2010 Type B Accident Investigation Board Report Employee Puncture Wound at the F-TRU Waste Remediation...

231

Appendix A U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

7 Appendices Appendices #12;Appendix A U.S. Nuclear Waste Technical Review Board Members: Curricula to the Nuclear Waste Technical Review Board. President Clinton appointed Dr. Cohon chairman on January 17, 1997, and Asia and on energy facility siting, including nuclear waste shipping and storage. In addition to his

232

Facility Safety | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecember 2005DepartmentDecember U.S. Department-5 METRIC SUMMARYFacility

233

Facility Disposition Safety Strategy RM  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power SystemsResourcesFLASH2011-11-OPAMFY 2007 Total System12 EERE CongressionalDepartment

234

Seismic Safety Guide  

SciTech Connect (OSTI)

This guide provides managers with practical guidelines for administering a comprehensive earthquake safety program. The Guide is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, evaluation and rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, special considerations related to shielding blocks, non-structural elements, lifelines, fire protection and emergency facilities. Management of risk and liabilities is also covered. Nuclear facilities per se are not dealt with specifically. The principles covered also apply generally to nuclear facilities but the design and construction of such structures are subject to special regulations and legal controls.

Eagling, D.G. (ed.)

1983-09-01T23:59:59.000Z

235

Student Disability Services Student Advisory Board  

E-Print Network [OSTI]

reported that the Storm Hall construction crew sometimes opens the staging area gate to wide and it blocks access to the wheelchair ramp by AL 204. Facilities Services needs to talk to the construction company:30 to 5pm. Patty went to the meeting as the Board's representative, but no one was there. Teresa called

Gallo, Linda C.

236

ORSSAB monthly board meeting  

Broader source: Energy.gov [DOE]

The ORSSAB monthly board meeting is open to the public. The board will receive an update on the Community Reuse Organization of East Tennessee efforts at the East Tennessee Technology Park.

237

ORSSAB monthly board meeting  

Broader source: Energy.gov [DOE]

The ORSSAB monthly board meeting is open to the public. The board will hear a presentation and discuss the development of a comprehensive mercury strategy for the Oak Ridge Reservation.

238

San Diego County- Design Standards for County Facilities  

Broader source: Energy.gov [DOE]

The San Diego County Board of Supervisors established design standards for county facilities and property. Among other requirements, the policy requires that all new county buildings or major...

239

Readiness Assessment for MF-628 Drum Treatment Facility - Advanced...  

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

NS.1 Facility safety documentation that describes the "safety envelope" for the AR Project II activities is in place and has been implemented to meet the following criteria:...

240

Self-imposed self-assessment program at a DOE Nuclear Facility  

SciTech Connect (OSTI)

The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL`s internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES&H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES&H, conduct of operations, and other functional area requirements.

Geoffrion, R.R.; Loud, J.J.; Walter, E.C. [Los Alamos National Laboratory, NM (United States)

1996-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "facilities safety board" 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

Evaluation of the US Department of Energy's occupational safety and health program for its government-owned contractor-operated facilities  

SciTech Connect (OSTI)

An evaluation of the Department of Energy's (DOE) occupational safety and health programs for its government-owned contractor-operated (GOCO) activities was completed by the Department of Labor's Occupational Safety and Health Administration (OSHA) in response to DOE's request for assistance. The purpose of the evaluation was to provide DOE with a blueprint for strengthening these programs. Under the leadership of Secretary of Energy James Watkins, DOE has launched a number of significant initiatives designed to instill a new culture of safety and health accountability within the Department. The Secretary of Energy's personal concern for safety and health was not being reflected in the priorities, resource allocation decisions and planning of DOE and GOCO managers. The report recommends that DOE consider major organizational changes, changes in priorities, and the development of operationally meaningful safety and health goals and objectives together with the accountability systems necessary to measure progress.

Not Available

1990-12-01T23:59:59.000Z

242

Integrated Safety Management Policy  

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

The policy establishes DOE's expectation for safety, including integrated safety management that will enable the Department’s mission goals to be accomplished efficiently while ensuring safe operations at all departmental facilities and activities. Cancels DOE P 411.1, DOE P 441.1, DOE P 450.2A, DOE P 450.4, and DOE P 450.7

2011-04-25T23:59:59.000Z

243

Nuclear Reactor Safety Design Criteria  

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

The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Certified 11-18-10.

1993-01-19T23:59:59.000Z

244

CRAD, Criteria and Guidelines For the Assessment of Safety System...  

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

CRAD, Criteria and Guidelines For the Assessment of Safety System Software and Firmware at Defense Nuclear Facilities CRAD, Criteria and Guidelines For the Assessment of Safety...

245

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

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

Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 21711 Comparison of Integrated Safety Analysis (ISA) and...

246

ACTION: Technical Position on the Use of National Consensus and Building Codes to Meet DOE Order 420.18, Facility Safety, Albright, 9/13/07  

Broader source: Energy.gov [DOE]

The attached technical position was developed in response to line organization requests for clarification and it will be posted on the Office ofNuclear Safety and Environmental Policy web page for...

247

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

E-Print Network [OSTI]

Based on recent decisions made by Los Alamos National Laboratory concerning the development of site-wide National Environmental Policy Act documents, an effort was undertaken to develop a Pilot Safety Information Document (PSID) for the replacement...

Selvage, Ronald Derek

1995-01-01T23:59:59.000Z

248

Health and Safety Training Reciprocity  

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

Establishes a policy for reciprocity of employee health and safety training among DOE entities responsible for employee health and safety at DOE sites and facilities to increase efficiency and effectiveness of Departmental operations while meeting established health and safety requirements. Does not cancel other directives.

2014-04-14T23:59:59.000Z

249

ORSSAB Monthly Board Meeting  

Broader source: Energy.gov [DOE]

The ORSSAB Monthly Board meeting is open to the public. This month, participants will be briefed on the East Tennessee Technology Park Zone 1 Soils Proposed Plan.

250

ORSSAB monthly board meeting  

Broader source: Energy.gov [DOE]

The ORSSAB monthly board meeting is open to the public. This month, participants will receive an update on the U-233 Project.

251

EWEB – Existing Facilities Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

Eugene Water and Electric Board (EWEB) offers an extensive list of energy efficiency rebates for existing facilities that apply to both specific equipment, as well as customized rebates for more...

252

Quality Assurance Corporate Board | Department of Energy  

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

Assurance Corporate Board Quality Assurance Corporate Board The Office of Environmental Management (EM) Quality Assurance Corporate Board is an executive board that includes both...

253

Nonreactor Nuclear Safety Design Guide for use with DOE O 420...  

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

CURRENT DOE G 420.1-1A, Nonreactor Nuclear Safety Design Guide for use with DOE O 420.1C, Facility Safety by Pranab Guha Functional areas: Facility Safety, Nonreactor Nuclear...

254

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

255

Office of Environment, Safety and Health Evaluations Appraisal...  

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

transportation, radioactive waste management, quality assurance, procurement, conduct of operations, design and system facility engineering, safety system maintenance,...

256

Supervisory General Engineer (Facility Engineering Division Director)  

Broader source: Energy.gov [DOE]

A successful candidate in this position will lead the Facility Engineering Division by providing internal and independent safety system oversight of Waste Isolation Pilot Plant (WIPP) operations in...

257

General Engineer / Physical Scientist (Facility Representative)  

Broader source: Energy.gov [DOE]

Facility Representatives (FRs) are line management's on-site technical representative with responsibility for identifying and evaluating environmental, safety and health issues and concerns,...

258

Cold vacuum drying facility design requirements  

SciTech Connect (OSTI)

This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

IRWIN, J.J.

1999-07-01T23:59:59.000Z

259

CHRPR Neutron Board Replacement Manual  

SciTech Connect (OSTI)

This document will walk through the steps to exchange the neutron channel boards with gamma channel boards in the CHRPR box.

Erikson, Rebecca L.; Myjak, Mitchell J.

2013-03-31T23:59:59.000Z

260

Radiation Safety Guide For Ancillary Personnel  

E-Print Network [OSTI]

, facilities, and public safety staff) who occasionally work in areas posted with the radiation symbol rules, you can ensure your safety while working in areas posted with the radiation symbol. 1. Follow allRadiation Safety Guide For Ancillary Personnel University of Washington Radiation Safety Office 203

Wilcock, William

Note: This page contains sample records for the topic "facilities safety board" 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

Total safety: A new safety culture to integrate nuclear safety and operational safety  

SciTech Connect (OSTI)

The creation of a complete and thorough safety culture is proposed for the purpose of providing additional assurance about nuclear safety and improving the performance of nuclear power plants. The safety philosophy developed a combination of the former hardware-oriented nuclear safety approach and recent operational safety concepts. The improvement of the latter, after TMI-2 and Chernobyl, has been proven very effective in reducing the total risk associated with nuclear power plants. The first part of this article introduces a {open_quotes}total safety{close_quotes} concept. This extends the concept of {open_quotes}nuclear safety{close_quotes} and makes it closer to the public perception of safety. This concept is defined by means of a taxonomy of total safety. The second part of the article shows that total safety can be achieved by integrating it into a modern quality assurance (QA) system since it is tailored to make implementation into a framework of QA easier. The author believes that the outstanding success experienced by various industries as a result of introducing the modern QA system should lead to its application for ensuring the safety and performance of nuclear facilities. 15 refs., 3 figs.

Saji, G. [Japan Atomic Energy Research Institute, Ibaraki-ken (Japan); Murphy, G.A. [ed.

1991-07-01T23:59:59.000Z

262

Associate Vice President Facilities Management  

E-Print Network [OSTI]

Operations & Energy Services Jack Baker Executive Director Building & Landscape Maintenance Harry Teabout III Safety HVAC Systems HVAC Systems Administration/ Signs & Graphics Administration/ Signs & Graphics Piped-Campus Facilities Director Department of Engineering & Energy VACANT Energy Management Energy Management Engineering

Milchberg, Howard

263

NASA Benchmarks Safety Functions Assessment plan - Developed...  

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

safety meetings how those goals can be met. (DOEEH- 0135) References: DOE 5480.19, "Conduct of Operations Requirements for DOE Facilities." NV M 111.XC, "Functions,...

264

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

265

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

266

ORSSAB monthly board meeting  

Broader source: Energy.gov [DOE]

Board members and participants will hear a presentation and updates about the "Y-12 Mercury Cleanup Strategy and Plan for a Y-12 Water Treatment Plant." The meeting is open to the public.

267

324 Building safety basis criteria document  

SciTech Connect (OSTI)

The Safety Basis Criteria document describes the proposed format, content, and schedule for the preparation of an updated Safety Analysis Report (SAR) and Operational Safety Requirements document (OSR) for the 324 Building. These updated safety authorization basis documents are intended to cover stabilization and deactivation activities that will prepare the facility for turnover to the Environmental Restoration Contractor for final decommissioning. The purpose of this document is to establish the specific set of criteria needed for technical upgrades to the 324 Facility Safety Authorization Basis, as required by Project Hanford Procedure HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval.

STEFFEN, J.M.

1999-06-02T23:59:59.000Z

268

Facility effluent monitoring plan for the tank farm facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements.

Crummel, G.M.

1998-05-18T23:59:59.000Z

269

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

270

K Basin safety analysis  

SciTech Connect (OSTI)

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

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

1994-12-16T23:59:59.000Z

271

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

272

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

273

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

274

Kansas City Board of Public Utilities- Commercial Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

The Kansas City Board of Public Utilities provides incentives for commercial customers to install, or upgrade to, energy efficiency equipment in new and existing facilities.Rebates are available...

275

University of New Mexico Board of Regents Committees 2014-2015 Operations Committee  

E-Print Network [OSTI]

University of New Mexico Board of Regents Committees 2014-2015 Operations Committee Regent and Facilities Committee James H. Koch, Chair Conrad D. James, Ph.D. , Vice Chair J.E. Gene Gallegos Audit N. Overton Lobo Energy Board (meets quarterly) J.E. Gene Gallegos, Vice Chair Conrad D. James, Ph

Maccabe, Barney

276

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

277

ANNUAL SECURITY & FIRE SAFETY REPORT  

E-Print Network [OSTI]

ANNUAL SECURITY & FIRE SAFETY REPORT 2014 A guide to policies, procedures, practices, and programs implemented to keep students, faculty, and staff safe and facilities secure. www.montana.edu/reports/security.pdf #12;Inside this Report 2014 Annual Security and Fire Safety Report for Reporting Year 2013

Maxwell, Bruce D.

278

Nuclear Waste Technical Review Board Strategic Plan FY 20082013  

E-Print Network [OSTI]

on compliance activities, in conduct- ing its evaluation, the Board will encourage DOE through its science its review of DOE activities into three technical areas: preclosure operations, including surface-facility design and operations and the transport of spent nuclear fuel and high-level radioactive waste from

279

U.S. Nuclear Waste Technical Review Board Members  

E-Print Network [OSTI]

Appendix A Appendix A U.S. Nuclear Waste Technical Review Board Members Jared L. Cohon, Ph.D.; Chairman On June 29, 1995, President Bill Clinton appointed Jared Cohon to the Nuclear Waste Technical, and Asia and on energy facil ity siting, including nuclear waste shipping and storage. In addition to his

280

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

Note: This page contains sample records for the topic "facilities safety board" 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

Arduino Board Design Nicholas Skadberg  

E-Print Network [OSTI]

Arduino Board Design Nicholas Skadberg 4/30/09 EE290 Dr. Pushkin Kachroo #12;Abstract In an effort an Arduino Atmega 168 controller chip and an Arduino Duemilanove circuit board. The device is controlled

Kachroo, Pushkin

282

Secretary of Energy Advisory Board  

Office of Environmental Management (EM)

Secretary of Energy Advisory Board Follow Up Response from the Task Force on High Performance Computing November 30, 2014 On August 18, 2014, the Secretary of Energy Advisory Board...

283

Advisory Board Chris Donnelly,  

E-Print Network [OSTI]

Michael DeBonis, Maine Forest Service J.B. Cullen, New Hampshire Division of Forests and Lands Steven Forest Service's Northeastern Area State and Private Forestry, the seven states of New England and New, and cooperators at various levels of public and private service. The Center has a fourteen member Advisory Board

Schweik, Charles M.

284

ACADEMIC BOARD Information for members  

E-Print Network [OSTI]

Principles and Quality Management Framework........................... 7 Self......................................................... 31 Attachment 2 -- Academic Board Quality Management Framework............. 32 http

University of Technology, Sydney

285

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

286

Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale facility implementation -- excavation -- storage technology -- safety analysis and review statement. Final report  

SciTech Connect (OSTI)

The purpose of this study is to assess the state-of-the-art of excavation technology as related to environmental remediation applications. A further purpose is to determine which of the excavation technologies reviewed could be used by the US Corp of Engineers in remediating contaminated soil to be excavated in the near future for construction of a new Lock and Dam at Winfield, WV. The study is designed to identify excavation methodologies and equipment which can be used at any environmental remediation site but more specifically at the Winfield site on the Kanawha River in Putnam County, West Virginia. A technical approach was determined whereby a functional analysis was prepared to determine the functions to be conducted during the excavation phase of the remediation operations. A number of excavation technologies were identified from the literature. A set of screening criteria was developed that would examine the utility and ranking of the technologies with respect to the operations that needed to be conducted at the Winfield site. These criteria were performance, reliability, implementability, environmental safety, public health, and legal and regulatory compliance. The Loose Bulk excavation technology was ranked as the best technology applicable to the Winfield site. The literature was also examined to determine the success of various methods of controlling fugitive dust. Depending upon any changes in the results of chemical analyses, or prior remediation of the VOCs from the vadose zone, consideration should be given to testing a new ``Pneumatic Excavator`` which removes the VOCs liberated during the excavation process as they outgas from the soil. This equipment however would not be needed on locations with low levels of VOC emissions.

Johnson, H.R.; Overbey, W.K. Jr.; Koperna, G.J. Jr.

1994-02-01T23:59:59.000Z

287

Technology Innovation Program Advisory Board  

E-Print Network [OSTI]

Technology Innovation Program Advisory Board 2009 Annual Report of the Technology Innovation Program Advisory Board 2010 Annual Report of the #12;2010 Annual Report of the Technology Innovation Program Advisory Board U.S. Department of Commerce National Institute of Standards and Technology

288

CRITICALITY SAFETY TRAINING AT FLUOR HANFORD (FH)  

SciTech Connect (OSTI)

The Fluor Hanford Criticality Safety engineers are extensively trained. The objectives and requirements for training are derived from Department of Energy (DOE) and American National Standards Institute/American Nuclear Society Standards (ANSI/ANS), and are captured in the Hanford Criticality Safety Program manual, HNF-7098. Qualification cards have been established for the general Criticality Safety Engineer (CSE) analyst, CSEs who support specific facilities, and for the facility Criticality Safety Representatives (CSRs). Refresher training and continuous education in the discipline are emphasized. Weekly Brown Bag Sessions keep the criticality safety engineers informed of the latest developments and historic perspectives.

TOFFER, H.

2005-05-02T23:59:59.000Z

289

Chemical Safety Vulnerability Working Group Report  

SciTech Connect (OSTI)

This report marks the culmination of a 4-month review conducted to identify chemical safety vulnerabilities existing at DOE facilities. This review is an integral part of DOE's efforts to raise its commitment to chemical safety to the same level as that for nuclear safety.

Not Available

1994-09-01T23:59:59.000Z

290

Toolbox Safety Talk Waste Anesthetic Gas (WAG)  

E-Print Network [OSTI]

Toolbox Safety Talk Waste Anesthetic Gas (WAG) Environmental Health & Safety Facilities Safety into the surrounding room during medical or research procedures are considered waste anesthetic gas (WAG). These gases. Please refer to the EHS Waste Anesthetic Gas Standard Operating Procedure for complete information

Pawlowski, Wojtek

291

Facility Microgrids  

SciTech Connect (OSTI)

Microgrids are receiving a considerable interest from the power industry, partly because their business and technical structure shows promise as a means of taking full advantage of distributed generation. This report investigates three issues associated with facility microgrids: (1) Multiple-distributed generation facility microgrids' unintentional islanding protection, (2) Facility microgrids' response to bulk grid disturbances, and (3) Facility microgrids' intentional islanding.

Ye, Z.; Walling, R.; Miller, N.; Du, P.; Nelson, K.

2005-05-01T23:59:59.000Z

292

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

293

Environmental Management Advisory Board Subcommittees | Department...  

Office of Environmental Management (EM)

EMAB Environmental Management Advisory Board Subcommittees Environmental Management Advisory Board Subcommittees ACQUISITION AND PROJECT MANAGEMENT SUBCOMMITTEE SUBCOMMITTEE...

294

National Spherical Torus Experiment-Upgrade SAFETY ASSESSMENT DOCUMENT  

E-Print Network [OSTI]

-00 Revision 6 DECEMBER 2014 Prepared by: _______________________ Jerry Levine Head, PPPL ESH&S Reviewed by Chair, PPPL ES&H Executive Board #12;#12;NSTX-U SAFETY ASSESSMENT DOCUMENT (SAD) Table of Contents 1

Princeton Plasma Physics Laboratory

295

Type A Accident Investigation Board Report of the July 28, 1998, Fatality and Multiple Injuries Resulting from Release of Carbon Dioxide at Building 648, Test Reactor Area, Idaho National Engineering and Environmental Laboratory  

Broader source: Energy.gov [DOE]

This report is an independent product of the Type A Accident Investigation Board appointed by Peter N. Brush, Acting Assistant Secretary for Environment, Safety and Health (EH-1).

296

Hazard Baseline Downgrade Effluent Treatment Facility  

SciTech Connect (OSTI)

This Hazard Baseline Downgrade reviews the Effluent Treatment Facility, in accordance with Department of Energy Order 5480.23, WSRC11Q Facility Safety Document Manual, DOE-STD-1027-92, and DOE-EM-STD-5502-94. It provides a baseline grouping based on the chemical and radiological hazards associated with the facility. The Determination of the baseline grouping for ETF will aid in establishing the appropriate set of standards for the facility.

Blanchard, A.

1998-10-21T23:59:59.000Z

297

OFFICE OF FACILITIES ENGINEERING AND OPERATIONS Strategic and  

E-Print Network [OSTI]

Engineering Museum Support Services Bruce Kendall Director Sheryl Kolasinski DD/CoS Facilities Master Planning Management Engineering &Design Management Technical Services Fire Protection Occupational Safety OccupationalOFFICE OF FACILITIES ENGINEERING AND OPERATIONS Strategic and Administrative Management Julie

Mathis, Wayne N.

298

Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years.

Greager, E.M.

1997-12-11T23:59:59.000Z

299

Facility effluent monitoring plan for the plutonium uranium extraction facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Wiegand, D.L.

1994-09-01T23:59:59.000Z

300

Sandia National Laboratories: Excellence Award in the 2012 Facilities...  

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

Testing Excellence Award in the 2012 Facilities Environmental, Safety and Health Go Green Initiative On December 19, 2012, in Concentrating Solar Power, Energy, Events,...

Note: This page contains sample records for the topic "facilities safety board" 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

Waste receiving and processing facility module 1 auditable safetyanalysis  

SciTech Connect (OSTI)

The Waste Receiving and Processing Facility Module 1 Auditable Safety Analysis analyzes postulated accidents and determines controls to prevent the accidents or mitigate the consequences.

Bottenus, R.J.

1997-02-01T23:59:59.000Z

302

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

303

Process safety management (OSHA) and process risk management (CAA) application. Application to a coke plant  

SciTech Connect (OSTI)

Risk Management Programs for Chemical Accidental Release Prevention is the name of the proposed rule for the RMP Risk Management Program. The RMP was written in response to several catastrophic releases of hazardous substances. The rule is applicable to facilities that store, process or use greater than threshold quantities of 62 listed flammable chemicals and another 100 listed toxic substances. Additionally, a Risk Management Plan is registered with the EPA, Chemical Safety and Hazardous Investigation Board, state governments and the local emergency planning commission. The Clean Air Act Amendments of 1990 (specifically Section 112r) required the EPA to develop a three phase Risk Management Plan for industry: prevention program; hazard assessment; and emergency response program. The Prevention Program closely follows the OSHA`s Process Safety Management Standard. The Hazard Assessment section requires facilities to develop plans for a worst case scenario. The Emergency Response section defines the steps the facility and each employee will take if a release occurs. This section also needs to be coordinated with the Local Emergency Planning Commission. These regulations are described using Clairton Works as an example of compliance.

Graeser, W.C.; Mentzer, W.P.

1995-12-01T23:59:59.000Z

304

Report of the Task Group on operation Department of Energy tritium facilities  

SciTech Connect (OSTI)

This report discusses the following topics on the operation of DOE Tritium facilities: Environment, Safety, and Health Aspects of Tritium; Management of Operations and Maintenance Functions; Safe Shutdown of Tritium Facilities; Management of the Facility Safety Envelope; Maintenance of Qualified Tritium Handling Personnel; DOE Tritium Management Strategy; Radiological Control Philosophy; Implementation of DOE Requirements; Management of Tritium Residues; Inconsistent Application of Requirements for Measurement of Tritium Effluents; Interdependence of Tritium Facilities; Technical Communication among Facilities; Incorporation of Confinement Technologies into New Facilities; Operation/Management Requirements for New Tritium Facilities; and Safety Management Issues at Department of Energy Tritium Facilities.

Not Available

1991-10-01T23:59:59.000Z

305

Nuclear safety information sharing agreement between NRC and...  

Office of Environmental Management (EM)

for DOE and NRC to exchange information related to safety issues associated with non-reactor nuclear facilities. The NRC-DOE Inter-Agency nuclear safety information sharing...

306

Local Scouts Train with Hanford Safety Experts - 52 Boy Scouts...  

Office of Environmental Management (EM)

Local Scouts Train with Hanford Safety Experts - 52 Boy Scouts Earn Merit Badges at the HAMMER Training Facility Local Scouts Train with Hanford Safety Experts - 52 Boy Scouts Earn...

307

www.nasa.gov WSTF SAFETY AND HEALTH CAPABILITIES  

E-Print Network [OSTI]

a positive safety culture where employees and management work together to identify hazards and eliminate jobwww.nasa.gov WSTF SAFETY AND HEALTH CAPABILITIES SUMMARY The White Sands Test Facility (WSTF) Safety & Mission Assurance (S&MA) offices support all WSTF test activities and general industrial safety

308

Hanford Advisory Board HAB  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuided Self-Assembly ofSeptember 4-5, 2014 Advisory Board HAB

309

Board of Directors - SRSCRO  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation InInformationCenterResearch HighlightsToolsBESEnergy DepartmentLectures 9 Apr1ofBoard of

310

On-board Diagnostics  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratorySpeeding access1 TechnicalOil inventories inOmbudsOmniOn-board

311

International Facility Management Association Strategic Facility  

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

Facility Management Association Strategic Facility Planning: A WhIte PAPer Strategic Facility Planning: A White Paper on Strategic Facility Planning 2009 | International...

312

Safety evaluation for packaging (onsite) product removal can containers  

SciTech Connect (OSTI)

This safety evaluation for packaging allows the transport of nine Product Removal (PR) Cans with their Containers from the PUREX Facility to the Plutonium Finishing Plant.

Boettger, J.S.

1997-04-29T23:59:59.000Z

313

Safety System Oversight Assessment of the Los Alamos National...  

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

Safety System Oversight Assessment of the Los Alamos National Laboratory Weapons Engineering Tritium Facility Tritium Gas Handling System INTRODUCTION AND OVERVIEW This report...

314

Sandia National Laboratories: Safety and Health Go Green Initiative  

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

Initiative Excellence Award in the 2012 Facilities Environmental, Safety and Health Go Green Initiative On December 19, 2012, in Concentrating Solar Power, Energy, Events,...

315

DOE Standard Integration Of Environment,Safety, and Health Into...  

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

of Energy (DOE) approved methodology for preparing a Documented Safety Analysis (DSA) for decommissioning of nuclear facilities, as well as environmental restoration activities...

316

Department of Energy Office of Nuclear Safety and Environmental...  

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

Safety, must comply with national consensus industry standards and the model building codes applicable for the state or region in which the facility is located. Certain...

317

Secretary of Energy Advisory Board  

Broader source: Energy.gov [DOE]

The Board will provide advice and recommendations to the Secretary of Energy on the Department's basic and applied research and development activities, economic and national security policy,...

318

Secretary of Energy Advisory Board  

Office of Environmental Management (EM)

a committee charged with identifying future technology needs for offshore oil and gas development. Dr. Hunter serves on many advisory boards for universities and government...

319

POST-CONSTRUCTION WILDLIFE MONITORING AT THE ATLANTIC CITY UTILITIES AUTHORITY-JERSEY ATLANTIC WIND POWER FACILITY  

E-Print Network [OSTI]

WIND POWER FACILITY PROJECT STATUS REPORT IV Submitted to: New Jersey Board of Public Utilities New Authority (ACUA) wind power facility. The period covered by this report is 1 January to 31 August 2009

Firestone, Jeremy

320

CRAD, Facility Safety - Documented Safety Analysis | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:June 2015 <Ones |Laboratory, JuneDid y ouRev. 0)

Note: This page contains sample records for the topic "facilities safety board" 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

CRAD, New Nuclear Facility Documented Safety Analysis and Technical Safety  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:June 2015 <Ones |Laboratory, JuneDid yRequirements - December

322

Tag: Safety  

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

8all en Best Practices Workshop for Safety Culture http:www.y12.doe.goveshbest-practices-workshop-safety-culture

323

Safety Information for Families  

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

Safety Information for Families Checking your home for hazards 22 safety items no home should be without Home Safety Checklists Helpful links Home Safety Council Hunter Safety:...

324

Radiological safety training for uranium facilities  

SciTech Connect (OSTI)

This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

NONE

1998-02-01T23:59:59.000Z

325

Toolbox Safety Talk Facility Flood Response  

E-Print Network [OSTI]

water, drain waste vent wastes ("sewage"), steam condensate, high ambient humidity, process chilled water, and rain, ground, and surface run-off water. The uncontrolled presence of water can create or Building Coordinator should ascertain the level of damage to building surfaces and materials, and determine

Pawlowski, Wojtek

326

Radiological Safety Training for Accelerator Facilities  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More Documents &DOE.F 1325.8 (08-93)DepartmentTS NOT

327

Radiological Safety Training for Plutonium Facilities  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More Documents &DOE.F 1325.8 (08-93)DepartmentTS

328

Radiological Safety Training for Plutonium Facilities  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More Documents &DOE.F 1325.8 (08-93)DepartmentTSNOT

329

Radiological Safety Training for Uranium Facilities  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More Documents &DOE.F 1325.8CHANGE NOTICE NO. 1DOE

330

Biological Safety  

Broader source: Energy.gov [DOE]

The DOE's Biological Safety Program provides a forum for the exchange of best practices, lessons learned, and guidance in the area of biological safety. This content is supported by the Biosurety Executive Team. The Biosurety Executive Team is a DOE-chartered group. The DOE Office of Worker Safety and Health Policy provides administrative support for this group. The group identifies biological safety-related issues of concern to the DOE and pursues solutions to issues identified.

331

HANFORD SAFETY ANALYSIS & 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 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S&M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard.

EVANS, C B

2004-12-21T23:59:59.000Z

332

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

333

Industrial Engineering Industrial Advisory Board  

E-Print Network [OSTI]

Industrial Engineering Industrial Advisory Board (IAB) #12;PURPOSE: The Texas Tech University - Industrial Engineering Industrial Ad- visory Board (IAB) is an association of professionals with a com- mon goal - promoting and developing the Texas Tech Department of Industrial Engineering and its students

Gelfond, Michael

334

Technology Innovation Program Advisory Board  

E-Print Network [OSTI]

Technology Innovation Program Advisory Board 2009 Annual Report of the #12;2009 Annual Report of the Technology Innovation Program Advisory Board U.S. Department of Commerce National Institute of Standards and Technology Technology Innovation Program February 2010 #12;For Information regarding the Technology

Magee, Joseph W.

335

STUDENT HEARING BOARD 20132014 APPLICATION  

E-Print Network [OSTI]

UMBC STUDENT HEARING BOARD 2013­2014 APPLICATION INTEGRITY,CIVILITY,&CONDUCT:FOSTERINGASAFECAMPUSCOMMUNITY #12;UMBC STUDENT HEARING BOARD I 2013­2014 APPLICATION To serve the UMBC community and the individual student by specifying behavioral standards, and by establishing a fair and efficient process

Maryland, Baltimore County, University of

336

STUDENT HEARING BOARD 20122013 APPLICATION  

E-Print Network [OSTI]

UMBC STUDENT HEARING BOARD 2012­2013 APPLICATION INTEGRITY,CIVILITY,&CONDUCT:FOSTERINGASAFECAMPUSCOMMUNITY #12;UMBC STUDENT HEARING BOARD I 2012­2013 APPLICATION To serve the UMBC community and the individual student by specifying behavioral standards, and by establishing a fair and efficient process

Maryland, Baltimore County, University of

337

ULTRANS BOARD OF ADVISORS Biographies  

E-Print Network [OSTI]

ULTRANS BOARD OF ADVISORS Biographies GREGG ALBRIGHT California Business, Transportation moved to Sacramento. #12;ULTRANS Board of Advisors Biographies ULTRANS BOA Meeting Page 2 September 23, and Papers in Regional Science. DALE BONNER Cal-Infra Advisors, INC. Dale Bonner is founder of Cal

California at Davis, University of

338

Aalto University Foundation Board Report  

E-Print Network [OSTI]

Aalto University Foundation Board Report and Financial Statements #12;Board Report 2010 4­21 Introduction 4 Purpose of the Foundation 5 Governance 6 Research, Education, and Artistic Activities 7 Sheet 24­25 Group Cash Flow Statement 26­27 Foundation Profit and Loss Account 28­29 Foundation Balance

Kaski, Samuel

339

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Kenneth L. Casavant, Chair Roger Mann, Vice-Chair Joel R of Independent Economic Analysis Board's Activities and Contributions to NPPC Fish and Wildlife Planning document of achieving the same sound biological objective exist, the alternative with the minimum economic cost

340

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Daniel D. Huppert, Chair Lon L. Peters, Vice-Chair Joel R. Hamilton Kenneth L. Casavant Jack A. Richards Roger Mann Paul C. Sorensen Hans Radtke Economic Review of Instream Water Supply Components of the Salmon Creek Project Independent Economic Analysis Board Northwest

Note: This page contains sample records for the topic "facilities safety board" 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

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Roger Mann, Chair Noelwah R. Netusil, Vice-Chair Kenneth L. Casavant Daniel D. Huppert Joel R. Hamilton Lon L. Peters Susan S. Hanna Hans Radtke A I - 1 Economic Effects From Columbia River Basin Anadromous Salmonid Fish Production Independent Economic Analysis Board

342

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Hans Radtke, Chair Roger Mann, Vice-Chair Daniel D. Huppert Joel R. Hamilton Susan S. Hanna John Duffield Noelwah R. Netusil Independent Economic Analysis Board Task Number 139 Integrated Hatchery Operations: Fish and Wildlife Program Costs and Other Economic

343

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Daniel D. Huppert, Chair Lon L. Peters, Vice-Chair Joel R and Guidance for Economic Analysis in Subbasin Planning Independent Economic Analysis Board January 2003, document IEAB 2003-2 Summary Subbasin planning may need to consider two types of economic issues; 1

344

Weapons engineering tritium facility overview  

SciTech Connect (OSTI)

Materials provide an overview of the Weapons Engineering Tritium Facility (WETF) as introductory material for January 2011 visit to SRS. Purpose of the visit is to discuss Safety Basis, Conduct of Engineering, and Conduct of Operations. WETF general description and general GTS program capabilities are presented in an unclassified format.

Najera, Larry [Los Alamos National Laboratory

2011-01-20T23:59:59.000Z

345

On the quantification of safety margins  

E-Print Network [OSTI]

The nuclear industry has relied on the concept of Defense in Depth (DID) and traditional safety margins to deal with the uncertainties associated with the design and operation of nuclear facilities. These concepts were ...

Pagani, Lorenzo P

2004-01-01T23:59:59.000Z

346

University Services University Health and Safety  

E-Print Network [OSTI]

Management Storm and Waste Water Compliance Promote Environmental Health Drinking Water Quality Human with environmental, health and safety standards, rules and best practices. Through partnerships with units with Capital Planning and Project Management, Facilities Management and academic departments throughout

Minnesota, University of

347

Safety assured financial evaluation of maintenance  

E-Print Network [OSTI]

Management decisions in complex industrial facilities usually consider both the economic and environmental aspects of the plant's performance. For nuclear power plants (NPPs), safety is also a very substantial issue. The objectives...

Erguina, Vera

2004-09-30T23:59:59.000Z

348

Materials Sciences Division Integrated Safety Management Plan  

E-Print Network [OSTI]

Materials Sciences Division Integrated Safety Management Plan Revised: February 9, 2012 Prepared by: signed Feb. 9, 2012 Rick Kelly, Facility/EH&S Manager Submitted by: signed Feb. 9, 2012 Miquel Salmeron.1 RESPONSIBILITY AND AUTHORITY THROUGH LINE MANAGEMENT............................................................5

349

Facility effluent monitoring plan for the tank farms facilities  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using specific guidelines. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

Bachand, D.D.; Crummel, G.M.

1995-05-01T23:59:59.000Z

350

Advisory Board 2014-15 External Committee  

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

Board Advisory Board 2014-15 External Committee IMS Advisory Panel Gabriel Aeppli (ETH Zurich, Paul Scherer Institute) Peter Littlewood (ANL Director) Diran Apelian (WPI)...

351

Environmental Management Advisory Board Members | Department...  

Energy Savers [EERE]

EMAB Board Member Read Bio Robert J. Thompson EMAB Board Member Read Bio Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition...

352

Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program  

SciTech Connect (OSTI)

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

Not Available

1994-02-01T23:59:59.000Z

353

ENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION  

E-Print Network [OSTI]

: FS Vancouver: Ops CHEMICAL SAFETY 27265 CONTRACTOR SAFETY 23867 EARLY RETURN TO WORK 23011 EMERGENCYENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION SIMON FRASER UNIVERSITY ENVIRONMENTAL HEALTH & SAFETY DEPARTMENT Discovery Park - MTF 8888 University Drive Burnaby, British Columbia Canada V5

354

Facility effluent monitoring plan for 242-A evaporator facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years.

Crummel, G.M.; Gustavson, R.D.

1995-02-01T23:59:59.000Z

355

Fast Reactor Spent Fuel Processing: Experience and Criticality Safety  

SciTech Connect (OSTI)

This paper discusses operational and criticality safety experience associated with the Idaho National Laboratory Fuel Conditioning Facility which uses a pyrometallurgical process to treat spent fast reactor metallic fuel. The process is conducted in an inert atmosphere hot cell. The process starts with chopping metallic fuel elements into a basket. The basket is lowered into molten salt (LiCl-KCl) along with a steel mandrel. Active metal fission products, transuranic metals and sodium metal in the spent fuel undergo chemical oxidation and form chlorides. Voltage is applied between the basket, which serves as an anode, and the mandrel, which serves as a cathode, causing metallic uranium in the spent fuel to undergo electro-chemical oxidation thereby forming uranium chloride. Simultaneously at the cathode, uranium chloride undergoes electro-chemical reduction and deposits uranium metal onto the mandrel. The uranium metal and accompanying entrained salt are placed in a distillation furnace where the uranium melts forming an ingot and the entrained salt boils and subsequently condenses in a separate crucible. The uranium ingots are placed in long term storage. During the ten year operating history, over one hundred criticality safety evaluations were prepared. All criticality safety related limits and controls for the entire process are contained in a single document which required over thirty revisions to accommodate the process changes. Operational implementation of the limits and controls includes use of a near real-time computerized tracking system. The tracking system uses an Oracle database coupled with numerous software applications. The computerized tracking system includes direct fuel handler interaction with every movement of material. Improvements to this system during the ten year history include introduction of web based operator interaction, tracking of moderator materials and the development of a plethora database queries to assist in day to day operations as well as obtaining historical information. Over 12,000 driver fuel elements have been processed resulting in the production of 2500 kg of 20% enriched uranium. Also, over one thousand blanket fuel elements have been processed resulting in the production of 2400 kg of depleted uranium. These operations required over 35,000 fissile material transfers between zones and over 6000 transfers between containers. Throughout all of these movements, no mass limit violations occurred. Numerous lessons were learned over the ten year operating history. From a criticality safety perspective, the most important lesson learned was the involvement of a criticality safety practitioner in daily operations. A criticality safety engineer was assigned directly to facility operations, and was responsible for implementation of limits and controls including upkeep of the associated computerized tracking files. The criticality safety engineer was also responsible for conducting fuel handler training activities including serving on fuel handler qualification oral boards, and continually assessing operations from a criticality control perspective. The criticality safety engineer also attended bimonthly project planning meetings to identify upcoming process changes that would require criticality safety evaluation. Finally, the excellent criticality safety record was due in no small part to the continual support, involvement, trust, and confidence of project and operations mana

Chad Pope

2007-05-01T23:59:59.000Z

356

The Hanford Advisory Board (HAB or Board) welcomes public comment...  

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

and Announcements Steve Hudson Cathy McCague 8:45 a.m. Draft Advice: In-trench Macroencapsulation of waste at ERDF * Overview of revisions - Issue manager (5) * Board discussion...

357

International Oil and Gas Board International Oil and Gas Board...  

Open Energy Info (EERE)

Oil and Gas Board Address Place Zip Website Abu Dhabi Supreme Petroleum Council Abu Dhabi Supreme Petroleum Council Abu Dhabi http www abudhabi ae egovPoolPortal WAR appmanager...

358

Cold Vacuum Drying (CVD) Facility Hazards 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 Final Safety Analysis Report 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 DOE Order 5480.23, ''Nuclear Safety Analysis Reports.''

CROWE, R.D.

2000-08-07T23:59:59.000Z

359

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

360

Ris-R-1104(EN) Nuclear Safety Research  

E-Print Network [OSTI]

.4 Radioanalytical chemistry 36 3.5 Ecophysiology 38 3.6 Radioactive waste 41 4 Nuclear facilities and services 43 4Risř-R-1104(EN) Nuclear Safety Research and Facilities Department Annual Report 1998 Edited by B, Roskilde, Denmark April 1999 #12;Abstract The report presents a summary of the work of the Nuclear Safety

Note: This page contains sample records for the topic "facilities safety board" 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

Ris-R-1162(EN) Nuclear Safety Research  

E-Print Network [OSTI]

.4 Radioanalytical chemistry 26 3.5 Radioactive waste 29 4 Nuclear facilities and services 30 4.1 Research reactor DRRisř-R-1162(EN) Nuclear Safety Research and Facilities Department Annual Report 1999 Edited by B, Denmark April 2000 #12;Abstract The report presents a summary of the work of the Nuclear Safety Research

362

Ris-R-1019(EN) Nuclear Safety Research  

E-Print Network [OSTI]

.2 Severe accidents 7 2.3 Decommissioning of research reactors 9 2.4 Nuclear information 10 3 RadiationRisø-R-1019(EN) Nuclear Safety Research and Facilities Department Annual Report 1997 Edited by B of the work of the Nuclear Safety Research and Facilities Department in 1997. The department´s research

363

Safety of Nuclear Explosive Operations  

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

This directive establishes responsibilities and requirements to ensure the safety of routine and planned nuclear explosive operations and associated activities and facilities. Cancels DOE O 452.2A and DOE G 452.2A-1A. Canceled by DOE O 452.2C.

2001-08-07T23:59:59.000Z

364

Vehicle Management Driver Safety Program  

E-Print Network [OSTI]

Vehicle Management and Driver Safety Program Manual Facilities & Operations / Finance & Administration Version 2 April 2012 #12;© 2012 University of Alberta. #12;The Vehicle Management and Driver of employment. Driver Acknowledgement I have received the University of Alberta, Vehicle Management and Driver

Machel, Hans

365

Safety Values  

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

* Work-related injuries, illnesses and environmental incidents are preventable. * A just culture exists where safety and environmental concerns are brought forward without fear of...

366

Radiation Safety  

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

Weeks of training * 15 of that is OJT * General Code of Operating Rules * Air Brake & Train Handling * System Special Instructions * Safety Instructions * Federal Regulations *...

367

SAFETY PROCEDURES ON BOARD THE SEDCOIBP-471 {JOIDES RESOLUTION)  

E-Print Network [OSTI]

environment, into the daily operation of the drilling vessel. All equipment aboard the ship is installed by Joint Oceanographic Institutions, Inc., under contract with the National Science Foundation. Funding of the University of Tokyo (Japan) National Science Foundation (United States) Natural Environment Research Council

368

Board of Trustees Dorothy Russell  

E-Print Network [OSTI]

Board of Trustees Dorothy Russell VP Financial Affairs (Chief Financial Officer) Corey King Interim & Psychological Services Housing and Residential Life Office of the Associate VP for Student Affairs and Dean

Marques, Oge

369

Extension Program Council's Executive Board.  

E-Print Network [OSTI]

~IB-134'-! II"I~ I~? Extension Program Council's Executive Board Mary G. Marshall and Burl B. Richardson Extension Program Development Specialists The Extension Program Council works with Extension agents to plan, implement, evaluate...

Marshall, Mary G.; Richardson, Burl B.

1986-01-01T23:59:59.000Z

370

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

con202vf UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300, the Nuclear Waste Technical Review Board (Board) submits its second report of 2003 in accordance with provisions of the Nuclear Waste Policy Amendments Act of 1987, Public Law 100-203. The Act requires the Board

371

Chemical Hazards and Safety Issues in Fusion Safety Design  

SciTech Connect (OSTI)

Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard.

Cadwallader, L.C. [Idaho National Engineering and Environmental Laboratory (United States)

2003-09-15T23:59:59.000Z

372

Non-Motorized Facility Inventory CTS Annual Transportation Research Conference  

E-Print Network [OSTI]

Non-Motorized Facility Inventory CTS Annual Transportation Research Conference May 23, 2012 Jesse an inventory and assessment of the non-motorized facilities along Carver County roadways 2. Identify the gaps-8 Safety Issues Identified #12;non-motorized facilities inventory #12;GIS mapping capabilities #12;An

Minnesota, University of

373

200 Area Deactivation Project Facilities Authorization Envelope Document  

SciTech Connect (OSTI)

Project facilities as required by HNF-PRO-2701, Authorization Envelope and Authorization Agreement. The Authorization Agreements (AA's) do not identify the specific set of environmental safety and health requirements that are applicable to the facility. Therefore, the facility Authorization Envelopes are defined here to identify the applicable requirements. This document identifies the authorization envelopes for the 200 Area Deactivation.

DODD, E.N.

2000-03-28T23:59:59.000Z

374

Guidelines for Evaluation of Nuclear Facility Training Programs  

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

The Guidelines for Evaluation of Nuclear Facility Training Programs establish objectives and criteria for evaluating nuclear facility training programs. The guidance in this standard provides a framework for the systematic evaluation of training programs at nuclear facilities and is based, in part, on established criteria for Technical Safety Appraisals, Tiger Team Assessments, commercial nuclear industry evaluations, and the DOE Training Accreditation Program.

1995-11-22T23:59:59.000Z

375

Nuclear Safety  

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

and Management Services Department at INL involves providing advanced risk and reliability analytical capabilities to support complex engineered facilities and processes. The...

376

Design of the Trigger Interface and Distribution Board for CEBAF 12 GeV Upgrade  

SciTech Connect (OSTI)

The design of the Trigger Interface and Distribution (TID) board for the 12 GeV Upgrade at the Continuous Electron Beam Accelerator Facility (CEBAF) at TJNAL is described. The TID board distributes a low jitter system clock, synchronized trigger, and synchronized multi-purpose SYNC signal. The TID also initiates data acquisition for the crate. With the TID boards, a multi-crate system can be setup for experiment test and commissioning. The TID board can be selectively populated as a Trigger Interface (TI) board, or a Trigger Distribution (TD) board for the 12 GeV upgrade experiments. When the TID is populated as a TI, it can be located in the VXS crate and distribute the CLOCK/TRIGGER/SYNC through the VXS P0 connector; it can also be located in the standard VME64 crate, and distribute the CLOCK/TRIGGER/SYNC through the VME P2 connector or front panel. It initiates the data acquisition for the front crate where the TI is positioned in. When the TID is populated as a TD, it fans out the CLOCK/TRIGGER/SYNC from trigger supervisor to the front end crates through optical fibres. The TD monitors the trigger processing on the TIs, and gives feedback to the TS for trigger flow control. Field Programmable Gate Arrays (FPGA) is utilised on TID board to provide programmability. The TID boards were intensively tested on the bench, and various setups.

Gu, Jianhui; Dong, Hai; Cuevas, R; Gyurjyan, Vardan; Heyes, William; Jastrzembski, Edward; Kaneta, Scott; Nganga, Nicholas; Moffit, Bryan; Raydo, Benjamin; Timmer, Carl

2012-10-01T23:59:59.000Z

377

Type A Accident Investigation Board Report on the February 20, 1996, Fall Fatality at the Radioactive Waste Management Complex Transuranic Storage Area- Retrieval Enclosure, Idaho National Engineering Laboratory  

Broader source: Energy.gov [DOE]

This report is an independent product of the Type A Accident Investigation Board appointed by Tara O’Toole, M.D., M.P.H., Assistant Secretary for Environment, Safety and Health (EH-1).

378

Type A Accident Investigation Board Report on the June 20, 1997, Construction Fatality at the Brookhaven National Laboratory, Upton, New York  

Broader source: Energy.gov [DOE]

This report is an independent product of the Type A Accident Investigation Board appointed by Tara O’Toole, M.D., M.P.H., Assistant Secretary for Environment, Safety & Health, U.S. Department of Energy.

379

Harvard-Smithsonian Center for Astrophysics Safety Policy  

E-Print Network [OSTI]

, periodically inspect the facilities and work with the Safety office to identify hazards and unsafe work safety and health hazards. Supervisors are responsible for supervising and training workers in safe work reporting accidents, hazards, near-miss incidents and unsafe work practices to a supervisor, the Safety

380

Ris-R-984(EN) Nuclear Safety Research  

E-Print Network [OSTI]

, Roskilde April 1997 #12;Abstract The report presents a summary of the work of the Nuclear Safety Re- search programmes and the Nordic Nuclear Safety Research Programme. This report describes the work of the departmentRisø-R-984(EN) Nuclear Safety Research and Facilities Department Annual Report 1996 Edited by B

Note: This page contains sample records for the topic "facilities safety board" 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

Cover letter, 10/29/03, re Nuclear Safety Technical Position, Deliverable 4.2.1  

Broader source: Energy.gov [DOE]

The enclosed Nuclear Safety Technical Position is Deliverable 4.2.1. under the Implementation Plan for Defense Nuclear Facilitises Board (DNFSB) Recommendation 2002-3, Requirements for Design...

382

CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I  

SciTech Connect (OSTI)

The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP.

Denney, R.D.

1995-10-01T23:59:59.000Z

383

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

384

Idaho National Laboratory Safety Presentations  

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

* Hand Tool Safety * Protect Your Hearing * Water Safety * Home Firearms Safety * Bicycle Safety * Pedestrian Safety * Others Outdoor Survival Safety (K-Middle School) What to...

385

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

emergencies, Le. , accidents at nuclear facilities, there isas a result of nuclear accidents; these are the Protectiveassociated with a nuclear accident is of greater importance

Nero, A.V.

2010-01-01T23:59:59.000Z

386

Safety Bulletin  

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

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...

387

ENVIRONMENTAL HEALTH AND SAFETY GENERAL SAFETY MANUAL  

E-Print Network [OSTI]

ENVIRONMENTAL HEALTH AND SAFETY GENERAL SAFETY MANUAL May 10, 2002 #12;i Acknowledgements Environmental Health and Safety gratefully acknowledges the assistance provided by the University Safety Council extremely helpful. #12;ii Environmental Health and Safety General Safety Manual Table of Contents Section

Maroncelli, Mark

388

LASER SAFETY POLICY MANUAL ENVIRONMENTAL HEALTH & SAFETY  

E-Print Network [OSTI]

LASER SAFETY POLICY MANUAL ISSUED BY ENVIRONMENTAL HEALTH & SAFETY OFFICE OF RADIOLOGICAL SAFETY and GEORGIA TECH LASER SAFETY COMMITTEE July 1, 2010 Revised July 31, 2012 #12;Laser Safety Program 1-1 #12;Laser Safety Policy Manual TABLE OF CONTENTS 1. POLICY AND SCOPE

Houston, Paul L.

389

Oak Ridge Site Specific Advisory Board Meetings | Department...  

Office of Environmental Management (EM)

Meetings Oak Ridge Site Specific Advisory Board Meetings Board Meeting Documents Available for Download January 15, 2015 ORSSAB Meeting - November 2014 Discussion of board...

390

US DOE Perspectives on Advisory Board Effectiveness - 13539  

SciTech Connect (OSTI)

Federal missions on the Oak Ridge Reservation began with the Manhattan Project, and continues today with major facilities supporting the Nation's Science and National Security missions. While most of the land area on the Oak Ridge Reservation is free of environmental impacts from these activities, significant legacy contamination is associated with specific facilities and past waste management areas. In 1989, the Oak Ridge Reservation (ORR) was placed on National Priorities List, and DOE established its Office of Environmental Management that same year. Three years later, in 1992, the Federal Facility Agreement for the reservation was signed. Three years afterward, the Oak Ridge Site Specific Advisory Board was established to augment ongoing public involvement activities related to Oak Ridge Reservation cleanup activities. One of the early and most impactful decisions the board made was to organize the End Use Working Group. This broad-based group of board members, DOE representatives, and members of the public was formed in 1997 to study future uses for contaminated areas of the reservation. The group was instrumental in building consensus in the Oak Ridge community regarding the long-term end state of reservation lands. The group's recommendations were a fundamental input into Record's of Decision subsequently developed to establish cleanup requirements across the ORR, and they continue to influence decisions being made today. In developing its recommendations on end states, the End Use Working Group came to the realization that long-term stewardship of contaminated areas of the reservation would be necessary, in some cases in perpetuity. It was from this concept that the Oak Ridge SSAB's 15-year involvement in stewardship would begin. A stewardship committee formed by the End Use Working Group wrote Volume 1 of the Stakeholder Report on Stewardship. This document-and its companion Volume 2, which was written a year later-form a crucial foundation for stewardship planning in Oak Ridge and have been referenced around the DOE complex as other sites consider stewardship planning. From these two broad-based initiatives, the board's focus has evolved to increasingly hone in on more specific, project-based recommendations and initiatives. The Oak Ridge Reservation Site Specific Advisory Board has been a highly effective forum for soliciting community input on Oak Ridge Reservation cleanup. Experience in Oak Ridge indicates that the utility of Board recommendations is far higher when the Board is asked to focus on broad programmatic issues, and less useful when the Board attempts to provide advice and recommendations on matters related to technical or project management issues. In Oak Ridge the Board has helped shape the program on many levels including definition of end-state cleanup objectives, budget development, program sequencing, waste management, and decisions concerning preservation of history related to missions implemented on the Oak Ridge Reservation. (authors)

Adler, David [US DOE (United States)] [US DOE (United States)

2013-07-01T23:59:59.000Z

391

Lawrence Berkeley National Laboratory Arboricultural Operations Safety Requirements LBNL Arboricultural Operation Safety Requirements  

E-Print Network [OSTI]

Lawrence Berkeley National Laboratory Arboricultural Operations Safety Requirements 1 of 3 LBNL reviewed with LBNL Facilities Electric Shop (6023)? * IF THE ANSWER TO 3E WAS NO, STOP THIS WORK ACTIVITY AND CONTACT FACILITIES ELECTRIC SHOP a. Name of LBNL individual consulted? #12;LBNL Arboricultural Operations

Eisen, Michael

392

Your Supplies: 1 Plinko Board board tacked with nails  

E-Print Network [OSTI]

numbers of runs with hits to the number of runs with misses. A Run = Bombarding Marble falls down it is not considered a run. A Hit = Bombarding Marble falls down the board and hits at least one target marble. It can hit more than one, but the run is only counted as a single "hit". A Miss = Bombarding Marble falls

Smith-Konter, Bridget

393

Safety, Security & Fire Report  

E-Print Network [OSTI]

2013 Safety, Security & Fire Report Stanford University #12;Table of Contents Public Safety About the Stanford University Department of Public Safety Community Outreach & Education Programs Emergency Access Transportation Safety Bicycle Safety The Jeanne Clery and Higher Education Act Timely Warning

Straight, Aaron

394

Accelerator Facility Safety Implementation Guide for DOE O 420.2C, Safety of Accelerator Facilities  

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

This document is a guide to understanding and meeting the requirements of DOE O 420.2C, and shares lessons learned based on valuable experience within the community. Cancels DOE G 420.2-1.

2014-08-01T23:59:59.000Z

395

Accelerator Facility Safety Implementation Guide for DOE Order 420.2C, Safety of Accelerator Facilities  

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

This is a guide to understanding and meeting the requirements of DOE Order 420.2C and shares lessons learned based on valuable experience within the community.

2013-08-30T23:59:59.000Z

396

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

397

Microsoft Word - 11-21605_Nuclear_Facility_Boundary_White_Paper...  

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

those specified for the nuclear - industrial facility boundary. g. Functions from NGNP white paper, INLEXT-10-19509, "Structures, Systems, and Components Safety Classification,"...

398

Environment, Safety, and Health Reporting  

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

To ensure timely collection, reporting, analysis, and dissemination of information on environment, safety, and health issues as required by law or regulations or as needed to ensure that the Department of Energy (DOE) and National Nuclear Security Administration (NNSA) are kept fully informed on a timely basis about events that could adversely affect the health and safety of the public or the workers, the environment, the intended purpose of DOE facilities, or the credibility of the Department. Cancels DOE O 210.1, DOE O 231.1, and DOE O 232.1A. Canceled by DOE O 232.2.

2003-08-19T23:59:59.000Z

399

Insulation board and process of making  

DOE Patents [OSTI]

Insulation board capable of bearing a load without significant loss of insulating capacity due to compression, produced by a method wherein the board is made in compliance with specified conditions of time, temperature and pressure.

Nowobilski, Jeffert J. (Orchard Park, NY); Owens, William J. (Kenmore, NY)

1985-01-01T23:59:59.000Z

400

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

. Huppert Noelwah R. Netusil JunJie Wu Cost-Effectiveness of Fish Tagging Technologies and Programs in the Columbia River Basin1 Independent Economic Analysis Board Fish and Wildlife Program Northwest Power and Conservation Council June 2, 2013 1 This report benefitted from the meetings of the Fish Tagging Forum

Note: This page contains sample records for the topic "facilities safety board" 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

Biosecurity Programme Board Silvan House  

E-Print Network [OSTI]

;Biosecurity Programme Board 6) Question of funding assistance for restocking on sites issued with a PH notice: Roger Coppock would convene a meeting with country reps to take this forward. 4. Tree Health and Plant. Action: Jon Heuch would contact tree officers to explore whether P. lateralis was something

402

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Kenneth L. Casavant, Chair Roger Mann, Vice-Chair Joel R Application of the IEAB's Recommendations and Guidance for Economic Analysis in Subbasin Planning improvements related to economic content of the draft Clearwater Subbasin Management Plan (the draft Clearwater

403

Board Advising Jeffrey L. Colesa  

E-Print Network [OSTI]

for advising, as measured by firm complexity, increases: (i) both advising quality and total advising increase; and (ii) the sensitivity of firm value to both advising quality and total advising increase by a director individually and by the board overall. We introduce measures of quality of advising and total

Lin, Xiaodong

404

Maintenance Management Program for DOE Nuclear Facilities  

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

The Order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of Structures, Systems and Components (SSCs) that are part of the safety basis required by 10 CFR 830.202.1 at hazard category 1, 2 and 3 Department of Energy (DOE) nuclear facilities. Cancels DOE O 433.1. Canceled by DOE O 433.1B.

2007-02-13T23:59:59.000Z

405

Maintenance Management Program for DOE Nuclear Facilities  

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

The order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of structures, systems and components that are part of the safety basis required by 10 CFR 830.202 at hazard category 1, 2 and 3 DOE nuclear facilities. Admin Chg 1, dated 3-12-2013. Cancels DOE O 433.1A.

2010-04-21T23:59:59.000Z

406

Maintenance Management Program for DOE Nuclear Facilities  

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

The order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of structures, systems and components that are part of the safety basis required by 10 CFR 830.202 at hazard category 1, 2 and 3 DOE nuclear facilities. Cancels DOE O 433.1A. Admin Chg 1, dated 3-12-2013, cancels DOE O 433.1B.

2010-04-21T23:59:59.000Z

407

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

408

Abbreviations and Acronyms Board U. S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

Abbreviations and Acronyms Board U. S. Nuclear Waste Technical Review Board CFR Code of Federal Commission NWTRB U.S. Nuclear Waste Technical Review Board PCI pellet-cladding interaction PTn Paintbrush, Conceptual Model, and Results of the TSPA-VA." Presentation to Nuclear Waste Technical Review Board's Panel

409

Page 1 of 2 ACADEMIC BOARD  

E-Print Network [OSTI]

Page 1 of 2 ACADEMIC BOARD Type: STATUTORY Nature: Senior academic committee of University Report Line: Authority to act via Articles of Government. Also reports to Board of Governors and Vice-Chancellor Timing: Four per annum Life Cycle: Three years TERMS OF REFERENCE/FUNCTIONS The Academic Board shall

Jones, Graeme A.

410

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

jlc029va UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300, D.C. 20585 Dear Speaker Gingrich, Senator Thurmond, and Secretary Peña: The Nuclear Waste Technical Review Board (the Board) herewith submits this second report of 1997 as required by the Nuclear Waste

411

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington are pleased to transmit a technical report prepared by the Nuclear Waste Technical Review Board (Board. Based on its review of data gathered by the DOE and the Center for Nuclear Waste Regulatory Analyses

412

Carrollton Board of Public Wks | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin: EnergyBostonFacility |Carpentersville, Illinois:Board of Public Wks Jump to:

413

ENVIRONMENTAL HEALTH & SAFETY  

E-Print Network [OSTI]

ENVIRONMENTAL HEALTH & SAFETY ORIENTATION HANDBOOK Environmental Health and Safety Office safety & Safety Office 494-2495 (Phone) 494-2996 (Fax) Safety.Office@dal.ca (E-mail) www.dal.ca/safety (Web) Radiation Safety Office 494-1938 (Phone) 494-2996 (Fax) Melissa.Michaud@dal.ca (E-mail) University

Brownstone, Rob

414

Reactor Safety Research Programs  

SciTech Connect (OSTI)

This document summarizes the work performed by Pacific Northwest laboratory from October 1 through December 31, 1979, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, lspra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Dotson, CW

1980-08-01T23:59:59.000Z

415

Environment, Safety and Health Reporting  

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

The order addresses DOE/NNSA receiving timely, 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. Cancels DOE O 231.1A Chg 1, DOE M 231.1-1A Chg 2 and DOE N 234.1. Admin Chg 1, dated 11-28-12, cancels DOE O 231.1B.

2011-06-27T23:59:59.000Z

416

Environment, Safety and Health Reporting  

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

The order addresses DOE/NNSA receiving timely, 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. Cancels DOE O 231.1A Chg 1, DOE M 231.1-1A Chg 2 and DOE N 234.1. Admin Chg 1, dated 11-28-12.

2011-06-27T23:59:59.000Z

417

Gas Pipeline Safety (Indiana)  

Broader source: Energy.gov [DOE]

This section establishes the Pipeline Safety Division within the Utility Regulatory Commission to administer federal pipeline safety standards and establish minimum state safety standards for...

418

Electrical Safety Committee Charter  

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

ANL Electrical Safety Page DOE Electrical Safety Handbook General Statement Home & Office Equipment Statement APS Electrical Safety Update Guidelines for Working on Voltages < 240...

419

Safety Overview Committee (SOC)  

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

(SOC) Charter 1. Purpose The Safety Overview Committee establishes safety policies and ad hoc safety committees. 2. Membership Membership will include the following individuals:...

420

Asymptotic Safety  

E-Print Network [OSTI]

Asymptotic safety is a set of conditions, based on the existence of a nontrivial fixed point for the renormalization group flow, which would make a quantum field theory consistent up to arbitrarily high energies. After introducing the basic ideas of this approach, I review the present evidence in favor of an asymptotically safe quantum field theory of gravity.

R. Percacci

2008-11-18T23:59:59.000Z

Note: This page contains sample records for the topic "facilities safety board" 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

Water Science and Technology Board annual report 1987  

SciTech Connect (OSTI)

In 1982, the National Research Council chose to recognize the importance of water resource issues by establishing the Water Science and Technology Board (WSTB). During the five years since its first meeting in November 1982, the WSTB has grown and matured. The WSTB has met 14 times to provide guidance and plan activities. Under the WSTB's direction, committees of experts have conducted approximately 30 studies on a broad array of topics, from dam safety to irrigation-induced water quality problems to ground water protection strategies. Studies have ranged in scope from the oversight of specific agency projects and programs to broader scientific reviews, such as a disciplinary assessment of the hydrologic sciences initiated in 1987. In all cases, studies have the general theme of ultimately improving the scientific and technological bases of programs of water management and environmental quality. This fifth annual report of the WSTB summarizes the Board's accomplishments during 1987, its current activities, and its plans for the future. The report also includes information on Board and committee memberships, program organizations, and the reports produced. The report should provide the reader with a basic understanding of the WSTB's interests, achievements, and capabilities. The WSTB welcomes inquiries and suggestions concerning its activities and will provide more detailed information on any aspects of its work to those interested.

Not Available

1988-01-01T23:59:59.000Z

422

Environment, Safety and Health Reporting  

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

To ensure timely collection, reporting, analysis, and dissemination of information on environment, safety, and health issues as required by law or regulations or as needed to ensure that the Department of Energy (DOE) and National Nuclear Security Administration are kept fully informed on a timely basis about events that could adversely affect the health and safety of the public or the workers, the environment, the intended purpose of DOE facilities, or the credibility of the Department. Cancels DOE O 210.1, DOE O 231.1, DOE O 232.1A. Canceled by DOE O 231.1B. DOE O 231.1B cancels all portions pertaining to environment, safety, and health reporting. Occurrence reporting and processing of operations information provisions remain in effect until January 1, 2012.

2012-01-01T23:59:59.000Z

423

Machine Shop Safety Tips & Safety Guidelines GENERAL SAFETY TIPS  

E-Print Network [OSTI]

Machine Shop Safety Tips & Safety Guidelines GENERAL SAFETY TIPS · Safety glasses with side shields distance away from moving machine parts, work pieces, and cutters. · Use hand tools for their designed to oil, clean, adjust, or repair any machine while it is running. Stop the machine and lock the power

Veiga, Pedro Manuel Barbosa

424

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

425

Environmental assessment of general-purpose heat source safety verification testing  

SciTech Connect (OSTI)

This Environmental Assessment (EA) was prepared to identify and evaluate potential environmental, safety, and health impacts associated with the Proposed Action to test General-Purpose Heat Source (GPHS) Radioisotope Thermoelectric Generator (RTG) assemblies at the Sandia National Laboratories (SNL) 10,000-Foot Sled Track Facility, Albuquerque, New Mexico. RTGs are used to provide a reliable source of electrical power on board some spacecraft when solar power is inadequate during long duration space missions. These units are designed to convert heat from the natural decay of radioisotope fuel into electrical power. Impact test data are required to support DOE`s mission to provide radioisotope power systems to NASA and other user agencies. The proposed tests will expand the available safety database regarding RTG performance under postulated accident conditions. Direct observations and measurements of GPHS/RTG performance upon impact with hard, unyielding surfaces are required to verify model predictions and to ensure the continual evolution of the RTG designs that perform safely under varied accident environments. The Proposed Action is to conduct impact testing of RTG sections containing GPHS modules with simulated fuel. End-On and Side-On impact test series are planned.

NONE

1995-02-01T23:59:59.000Z

426

OCCUPATIONAL SAFETY and HEALTH  

E-Print Network [OSTI]

MARYLAND OCCUPATIONAL SAFETY and HEALTH ACT safety and health protection on the job STATE OCCUPATIONAL SAFETY AND HEALTH STANDARDS, AND OTHER APPLICABLE REGULATIONS MAY BE OBTAINED FROM Complaints about State Program administration may be made to Regional Administrator, Occupational Safety

Weaver, Harold A. "Hal"

427

OCCUPATIONAL HEALTH AND SAFETY  

E-Print Network [OSTI]

OCCUPATIONAL HEALTH AND SAFETY MANAGEMENT SYSTEM Department of Occupational Health and Safety Revised December 2009 #12;Occupational Health and Safety (OHS) Management System 1. Introduction.............................................................................................................. 3 2.2 Management of Health and Safety

428

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

429

Safety harness  

DOE Patents [OSTI]

A safety harness to be worn by a worker, especially a worker wearing a plastic suit thereunder for protection in a radioactive or chemically hostile environment, which safety harness comprises a torso surrounding portion with at least one horizontal strap for adjustably securing the harness about the torso, two vertical shoulder straps with rings just forward of the of the peak of the shoulders for attaching a life-line and a pair of adjustable leg supporting straps releasibly attachable to the torso surrounding portion. In the event of a fall, the weight of the worker, when his fall is broken and he is suspended from the rings with his body angled slightly back and chest up, will be borne by the portion of the leg straps behind his buttocks rather than between his legs. Furthermore, the supporting straps do not restrict the air supplied through hoses into his suit when so suspended.

Gunter, Larry W. (615 Sand Pit Rd., Leesville, SC 29070)

1993-01-01T23:59:59.000Z

430

University Policy No.: SS9300 Classification: Safety and Security  

E-Print Network [OSTI]

University Policy No.: SS9300 Classification: Safety and Security Approving Authority: Board of Governors COMMUNICABLE DISEASES POLICY Effective Date: April/04 Supersedes: November/94 Last Editorial Change: Mandated Review: 1. POLICY PURPOSE The purpose of the policy is to provide direction

Victoria, University of

431

FPS 12.1 Life Safety, 5/24/2000  

Broader source: Energy.gov [DOE]

The objective of this surveillance is for the Facility Representative to verify that conditions in the plant provide an appropriate level of life safety for workers conducting operations in the...

432

Safety valve  

DOE Patents [OSTI]

The safety valve contains a resilient gland to be held between a valve seat and a valve member and is secured to the valve member by a sleeve surrounding the end of the valve member adjacent to the valve seat. The sleeve is movable relative to the valve member through a limited axial distance and a gap exists between said valve member and said sleeve.

Bergman, Ulf C. (Malmoe, SE)

1984-01-01T23:59:59.000Z

433

Russell Furr Laboratory Safety &  

E-Print Network [OSTI]

Russell Furr Director 8/20/13 Laboratory Safety & Compliance #12;#12;Research Safety Full Time Students Part- Time #12; Organizational Changes Office of Research Safety Research Safety Advisors Safety Culture Survey Fire Marshal Inspections Laboratory Plans Review New Research Safety Initiatives

434

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

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of Energy fromComments onReplyofRetiring ProcurementReturn onRevenueNOT

435

Final Safety Evaluation Report to license the construction and operation of a facility to receive, store, and dispose of 11e.(2) byproduct material near Clive, Utah (Docket No. 40-8989)  

SciTech Connect (OSTI)

The Final Safety Evaluation Report (FSER) summarizes the US Nuclear Regulatory Commission (NRC) staff`s review of Envirocare of Utah, Inc.`s (Envirocare`s) application for a license to receive, store, and dispose of uranium and thorium byproduct material (as defined in Section 11e.(2) of the Atomic Energy Act of 1954, as amended) at a site near Clive, Utah. Envirocare proposes to dispose of high-volume, low-activity Section 11e.(2) byproduct material in separate earthen disposal cells on a site where the applicant currently disposes of naturally occurring radioactive material (NORM), low-level waste, and mixed waste under license by the Utah Department of Environmental Quality. The NRC staff review of the December 23, 1991, license application, as revised by page changes dated July 2 and August 10, 1992, April 5, 7, and 10, 1993, and May 3, 6, 7, 11, and 21, 1993, has identified open issues in geotechnical engineering, water resources protection, radon attenuation, financial assurance, and radiological safety. The NRC will not issue a license for the proposed action until Envirocare adequately resolves these open issues.

Not Available

1994-01-01T23:59:59.000Z

436

2011 Annual Criticality Safety Program Performance Summary  

SciTech Connect (OSTI)

The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The TSR limits fuel plate bundles to 1085 grams U-235, which is the maximum loading of an ATR fuel element. The overloaded fuel plate bundle contained 1097 grams U-235 and was assembled under an 1100 gram U-235 limit in 1982. In 2003, the limit was reduced to 1085 grams citing a new criticality safety evaluation for ATR fuel elements. The fuel plate bundle inventories were not checked for compliance prior to implementing the reduced limit. A subsequent review of the NMIS inventory did not identify further violations. Requirements Management - The INL Criticality Safety program is organized and well documented. The source requirements for the INL Criticality Safety Program are from 10 CFR 830.204, DOE Order 420.1B, Chapter III, 'Nuclear Criticality Safety,' ANSI/ANS 8-series Industry Standards, and DOE Standards. These source requirements are documented in LRD-18001, 'INL Criticality Safety Program Requirements Manual.' The majority of the criticality safety source requirements are contained in DOE Order 420.1B because it invokes all of the ANSI/ANS 8-Series Standards. DOE Order 420.1B also invokes several DOE Standards, including DOE-STD-3007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities.' DOE Order 420.1B contains requirements for DOE 'Heads of Field Elements' to approve the criticality safety program and specific elements of the program, namely, the qualification of criticality staff and the method for preparing criticality safety evaluations. This was accomplished by the approval of SAR-400, 'INL Standardized Nuclear Safety Basis Manual,' Chapter 6, 'Prevention of Inadvertent Criticality.' Chapter 6 of SAR-400 contains sufficient detail and/or reference to the specific DOE and contractor documents that adequately describe the INL Criticality Safety Program per the elements specified in DOE Order 420.1B. The Safety Evaluation Report for SAR-400 specifically recognizes that the approval of SAR-400 approves the INL Criticality Safety Program. No new source requirements were released in 2011. A revision to LRD-18001 is

Andrea Hoffman

2011-12-01T23:59:59.000Z

437

Audit Report The Procurement of Safety Class/Safety-Significant Items at the Savannah River Site  

SciTech Connect (OSTI)

The Department of Energy operates several nuclear facilities at its Savannah River Site, and several additional facilities are under construction. This includes the National Nuclear Security Administration's Tritium Extraction Facility (TEF) which is designated to help maintain the reliability of the U.S. nuclear stockpile. The Mixed Oxide Fuel Fabrication Facility (MOX Facility) is being constructed to manufacture commercial nuclear reactor fuel assemblies from weapon-grade plutonium oxide and depleted uranium. The Interim Salt Processing (ISP) project, managed by the Office of Environmental Management, will treat radioactive waste. The Department has committed to procuring products and services for nuclear-related activities that meet or exceed recognized quality assurance standards. Such standards help to ensure the safety and performance of these facilities. To that end, it issued Departmental Order 414.1C, Quality Assurance (QA Order). The QA Order requires the application of Quality Assurance Requirements for Nuclear Facility Applications (NQA-1) for nuclear-related activities. The NQA-1 standard provides requirements and guidelines for the establishment and execution of quality assurance programs during the siting, design, construction, operation, and decommissioning of nuclear facilities. These requirements, promulgated by the American Society of Mechanical Engineers, must be applied to 'safety-class' and 'safety-significant' structures, systems and components (SSCs). Safety-class SSCs are defined as those necessary to prevent exposure off site and to protect the public. Safety-significant SSCs are those whose failure could irreversibly impact worker safety such as a fatality, serious injury, or significant radiological or chemical exposure. Due to the importance of protecting the public, workers, and environment, we initiated an audit to determine whether the Department of Energy procured safety-class and safety-significant SSCs that met NQA-1 standards at the Savannah River Site. Our review disclosed that the Department had procured and installed safety-class and safety-significant SSCs that did not meet NQA-1 quality standards. Specifically, we identified multiple instances in which critical components did not meet required quality and safety standards. For example: (1) Three structural components were procured and installed by the prime contractor at Savannah River during construction of the MOX Facility that did not meet the technical specifications for items relied on for safety. These substandard items necessitated costly and time consuming remedial action to, among other things, ensure that nonconforming materials and equipment would function within safety margins; (2) In six instances, items used in the construction of TEF failed to satisfy quality standards. In one of these situations, operating procedures had to be modified to ensure that the problem item did not compromise safety; and (3) Finally, at the ISP, one component that did not meet quality standards was procured. The failure of the item could have resulted in a spill of up to 15,000 gallons of high-level radioactive waste. Based on an extensive examination of relevant internal controls and procurement practices, we concluded that these failures were attributable to inadequate attention to quality assurance at Savannah River. Simply put, Departmental controls were not adequate to prevent and/or detect quality assurance problems. For example, Federal and prime contractor officials did not expressly require that subcontractors or lower-tiered vendors comply with quality assurance requirements. Additionally, management did not effectively communicate quality assurance concerns between the several Departmental program elements operating at Savannah River. The procurement and installation of these nonconforming components resulted in cost increases. For example, as of October 2008, the MOX Facility had incurred costs of more than $680,000 due to problems associated with the procurement of $11 million of nonconforming safety-class reinforcing steel.

None

2009-04-01T23:59:59.000Z

438

Facility effluent monitoring plan for the plutonium-uranium extraction facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Lohrasbi, J.; Johnson, D.L. [Westinghouse Hanford Co., Richland, WA (United States); De Lorenzo, D.S. [Los Alamos Technical Associates, NM (United States)

1993-12-01T23:59:59.000Z

439

Facility effluent monitoring plan for the Waste Receiving and Processing Facility Module 1  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal state, and local requirements. This facility effluent monitoring plan shall ensure lonq-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

Lewis, C.J.

1995-10-01T23:59:59.000Z

440

Overview of US fast-neutron facilities and testing capabilities  

SciTech Connect (OSTI)

Rather than attempt a cataloging of the various fast neutron facilities developed and used in this country over the last 30 years, this paper will focus on those facilities which have been used to develop, proof test, and explore safety issues of fuels, materials and components for the breeder and fusion program. This survey paper will attempt to relate the evolution of facility capabilities with the evolution of development program which use the facilities. The work horse facilities for the breeder program are EBR-II, FFTF and TREAT. For the fusion program, RTNS-II and FMIT were selected.

Evans, E.A.; Cox, C.M.; Jackson, R.J.

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "facilities safety board" 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

Environmental Health & Safety Office of Radiological Safety  

E-Print Network [OSTI]

Environmental Health & Safety Office of Radiological Safety Page 1 of 2 FORM LU-1 Revision 01 1 safety training and submit this registration to the LSO prior to use of Class 3B or 4 lasers. A copy will be returned to the Laser Supervisor to be filed in the Laboratory Laser Safety Notebook. Both the Laser

Houston, Paul L.

442

Environmental Health and Instructional Safety Employee Safety  

E-Print Network [OSTI]

Environmental Health and Instructional Safety #12;Employee Safety Page 1 To our University an environment for students, faculty, staff, and visitors that will not adversely affect their health and safety task that is unsafe or hazardous. Environmental Health and Instructional Safety can assist departments

de Lijser, Peter

443

Safety Share from National Safety Council  

Broader source: Energy.gov [DOE]

Slide Presentation by Joe Yanek, Fluor Government Group. National Safety Council Safety Share. The Campbell Institute is the “Environmental, Health and Safety (EHS) Center of Excellence” at the National Safety Council and provides a Forum for Leaders in EHS to exchange ideas and collaborate across industry sectors and organizational types.

444

Board of Trustees (Idaho State Board of Education)  

E-Print Network [OSTI]

and Environmental Health -School of Nursing -Radiologic Sciences -Respiratory Care -Research Assistance -Library Ventures -Research Compliance -CAES Energy Policy Institute -Story Initiative -CAES Energy Efficiency & Safety Government* Relations Bruce Newcomb Athletics*¨ Mark Coyle Internal Audit Larry Harmon Boise State

Barrash, Warren

445

The Texas Agricultural Cooperative Board Chairman.  

E-Print Network [OSTI]

19 10 7 100 5 Board chairmen usually purchase most of their supplies from cooperatives. Of the supplies that were handled, board chairmen, on the average, purchased 87 percent from their cooperative. Older board chairmen were better supply... patrons than younger ones. However, all age groups purchased a majority of their supplies from their cooperative. Table 6. Relationship of Age of Chairman to the Percent of Inputs Purcha~ from the Cooperative, Texas, 1985. Percent of Inputs Purchased...

Black, William E.; Knutson, Ronald D.

1985-01-01T23:59:59.000Z

446

Secretary of Energy Advisory Board  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administrationcontroller systemsBi (2) Sr (2)ScienceScientistsONDelivered |of Energy Advisory Board

447

Safety, Security  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar HomePromisingStoriesSANDIA1 0-SA-02 SeptemberMaterialsSafety

448

Radiation Safety  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, and 323 RS-PO-0001-001.docW. J:.EnergySafety Home

449

JLF Safety  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region serviceMission Statement Titan Target Chamber The JupiterJLF Safety

450

Reactor Safety Research Programs  

SciTech Connect (OSTI)

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S. K.

1981-07-01T23:59:59.000Z

451

Construction safety in DOE. Part 1, Students guide  

SciTech Connect (OSTI)

This report is the first part of a compilation of safety standards for construction activities on DOE facilities. This report covers the following areas: general safety and health provisions; occupational health and environmental control/haz mat; personal protective equipment; fire protection and prevention; signs, signals, and barricades; materials handling, storage, use, and disposal; hand and power tools; welding and cutting; electrical; and scaffolding.

Handwerk, E.C.

1993-08-01T23:59:59.000Z

452

Ris-R-679(EN) Nuclear Safety Research  

E-Print Network [OSTI]

of the nuclear facilities at Risø. The activities include personnel dosimetry, maintenance and calibra- tionRisø-R-679(EN) mil Nuclear Safety Research Department Annual Progress Report 1992 Edited by B March 1993 #12;Nuclear Safety Research K«*«i Department Annual Progress Report 1992 Edited by B

453

Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements  

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

This Guide provides information to assist in the implementation and interpretation of Title 10 Code of Federal Regulations (CFR) Part 830.203, Unreviewed Safety Question Process, of the Nuclear Safety Management Rules for applicable nuclear facilities owned or operated by the Department of Energy (DOE), including the National Nuclear Security Administration (NNSA). Canceled by DOE N 251.93.

2001-10-24T23:59:59.000Z

454

Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements  

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

This Guide provides information to assist in implementation of Title 10 Code of Federal Regulations Part 830.203, "Unreviewed Safety Question Process," of the Nuclear Safety Management Rules for Category 1, 2, and 3 nuclear facilities owned or operated by the Department of Energy, including the National Nuclear Security Administration. Cancels DOE G 424.1-1.

2006-07-24T23:59:59.000Z

455

Ris-R-1318(EN) Nuclear Safety Research  

E-Print Network [OSTI]

. Risø Decommissioning has the task of preparing for the decommissioning of Risø's nuclear facilitiesRisø-R-1318(EN) Nuclear Safety Research Department Annual Report 2001 Edited by B. Majborn, A This report presents a summary of the work of the Nuclear Safety Research Department in 2001. The department

456

Safety Guidelines for Fieldwork Industrial Hygiene and Occupational Safety Department  

E-Print Network [OSTI]

Safety Guidelines for Fieldwork Industrial Hygiene and Occupational Safety Department Environmental Safety Division University of Georgia Adapted from the Safety Guidelines for Field Researchers published by the Office of Environment, Health & Safety at University of California, Berkeley #12;Safety Guidelines

Arnold, Jonathan

457

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

458

High Exposure Facility Technical Description  

SciTech Connect (OSTI)

The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

2008-02-12T23:59:59.000Z

459

Processing A Printed Wiring Board By Single Bath Electrodeposition  

SciTech Connect (OSTI)

A method of processing a printed wiring board by single bath electrodeposition. Initial processing steps are implemented on the printed wiring board. Copper is plated on the printed wiring board from a bath containing nickel and copper. Nickel is plated on the printed wiring board from the bath containing nickel and copper and final processing steps are implemented on the printed wiring board.

Meltzer, Michael P. (Oakland, CA); Steffani, Christopher P. (Livermore, CA); Gonfiotti, Ray A. (Livermore, CA)

2003-04-15T23:59:59.000Z

460

Processing a printed wiring board by single bath electrodeposition  

SciTech Connect (OSTI)

A method of processing a printed wiring board. Initial processing steps are implemented on the printed wiring board. Copper is plated on the printed wiring board from a bath containing nickel and copper. Nickel is plated on the printed wiring board from a bath containing nickel and copper and final processing steps are implemented on the printed wiring board.

Meltzer, Michael P. (Oakland, CA); Steffani, Christopher P. (Livermore, CA); Gonfiotti, Ray A. (Livermore, CA)

2010-12-07T23:59:59.000Z

Note: This page contains sample records for the topic "facilities safety board" 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

Labor and Safety: Mines and Mining Safety (Indiana)  

Broader source: Energy.gov [DOE]

This section contains labor regulations pertaining specifically to coal mine workers. The law establishes the Indiana Mining Board. The Board's duties include: collecting and distributing...

462

ARTISAN/FARMSTEAD CHEESEMAKER FOOD SAFETY WORKSHOP  

E-Print Network [OSTI]

cheesemakers understand best practices and techniques for pathogen control in their facilities to assure. The workshop will include topics such as GMPs, sanitation, preventative and microbial controls, environmental looking to protect consumers and their businesses through good food safety practices · Extension

Alpay, S. Pamir

463

Preliminary hazards analysis for the National Ignition Facility  

SciTech Connect (OSTI)

This report documents the Preliminary Hazards Analysis (PHA) for the National Ignition Facility (NIF). In summary, it provides: a general description of the facility and its operation; identification of hazards at the facility; and details of the hazards analysis, including inventories, bounding releases, consequences, and conclusions. As part of the safety analysis procedure set forth by DOE, a PHA must be performed for the NIF. The PHA characterizes the level of intrinsic potential hazard associated with a facility, and provides the basis for hazard classification. The hazard classification determines the level of safety documentation required, and the DOE Order governing the safety analysis. The hazard classification also determines the level of review and approval required for the safety analysis report. The hazards of primary concern associated with NIF are radiological and toxicological in nature. The hazard classification is determined by comparing facility inventories of radionuclides and chemicals with threshold values for the various hazard classification levels and by examining postulated bounding accidents associated with the hazards of greatest significance. Such postulated bounding accidents cannot take into account active mitigative features; they must assume the unmitigated consequences of a release, taking into account only passive safety features. In this way, the intrinsic hazard level of the facility can be ascertained.

Brereton, S.J.

1993-10-01T23:59:59.000Z

464

Chemical Safety Vulnerability Working Group report. Volume 1  

SciTech Connect (OSTI)

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms.

Not Available

1994-09-01T23:59:59.000Z

465

SCHOOL OF EDUCATION SAFETY STATEMENT  

E-Print Network [OSTI]

................................................................... 13 #12;HEALTH & SAFETY Health & Safety is important. The Safety, Health and Welfare at Work Act 1989SCHOOL OF EDUCATION SAFETY STATEMENT March 2009 1 #12;2 Health & Safety Statement Contents HEALTH & SAFETY................................................................... 3 EMERGENCY DETAILS

O'Mahony, Donal E.

466

Facilities Services Overview & Discussion  

E-Print Network [OSTI]

& Finance Facilities Services Director: Jeff Butler Human Resources Administrative Services Engineering) Environmental Services Morrison (3) Admin Services Evans (1) Human Resources Engineering (4) ·EngineeringFacilities Services Overview & Discussion Jeff Butler Director ­ Facilities Services November 2011

Maxwell, Bruce D.

467

Campus Public Safety Office Michael Soto, Director of Public Safety  

E-Print Network [OSTI]

Campus Public Safety Office Michael Soto, Director of Public Safety Service Resource, teaching, research and service. Michael D. Soto Director of Public Safety Public Safety Office Service

Bertini, Robert L.

468

National Safety Council Safety Share | Department of Energy  

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

Safety Council Safety Share National Safety Council Safety Share May 16, 2013 Presenter: Joe Yanek, Fluor Government Group, Washington, D.C. Topics Covered: The Campbell Institute...

469

EMPLOYEE SAFETY ORIENTATION  

E-Print Network [OSTI]

Page | 0 EMPLOYEE SAFETY ORIENTATION _________________ Risk, Safety & Security 3333 University Way to be acquainted with the safety program, welcome! Risk, Safety & Security at UNBC is dynamic. With more than 3 worksite and safe work procedures which pertain to your job. The role of the Risk and Safety Office

Bolch, Tobias

470

ENVIRONMENTAL, HEALTH AND SAFETY  

E-Print Network [OSTI]

ENVIRONMENTAL, HEALTH AND SAFETY PROGRAMS SPRING 2012 Including: Free Information Session New Program in Health and Safety CONTINUING AND PROFESSIONAL EDUCATION #12;2 Our Health and Safety Programs Workplace Health and Safety Certificate Program For every dollar invested in workplace safety, organizations

California at Davis, University of

471

GEORGE MASON UNIVERSITY BOARD OF VISITORS  

E-Print Network [OSTI]

1 GEORGE MASON UNIVERSITY BOARD OF VISITORS Bylaws ARTICLE I Membership 1. The Board shall consist of the members appointed each year shall be an alumnus of George Mason University. Appointments shall from office for malfeasance, misfeasance, incompetence, or gross neglect of duty, and fill the vacancy

472

of the Board of Regents CHARTER PROVISIONS  

E-Print Network [OSTI]

of the Board 5.04 Secretary 5.05 Chief Financial Officer 5.06 General Counsel 5.07 Inspector General 5.08 Chief and shall be interpreted accordingly. 1.02 AMENDMENT These bylaws may be amended at any meeting of the Board

Mathis, Wayne N.

473

Hans M. Amman Executive Board Utrecht University  

E-Print Network [OSTI]

Hans M. Amman Executive Board Utrecht University Current Positions 2006­present Executive Board Member (lid College van Bestuur), Utrecht University, Utrecht, the Netherlands. 2006­present Professor of Economics and Management, Utrecht School of Economics, Utrecht University, Utrecht, the Netherlands

Utrecht, Universiteit

474

United States Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

United States Nuclear Waste Technical Review Board Experience Gained From Programs to Manage High-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other Countries A Report to Congress and the Secretary of Energy April 2011 #12;#12;U.S. Nuclear Waste Technical Review Board Experience Gained From

475

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

JEC187V3 UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 of Energy 1000 Independence Avenue, SW Washington, DC 20585 Dear Secretary O'Leary: At the Nuclear Waste UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington, VA

476

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington is intended to update Congress and the Secretary of Energy on the U.S. Nuclear Waste Technical Review Board-level radioactive waste (HLW) is evolving. The letter is issued in accordance with provisions of the Nuclear Waste

477

BOARD OF PORT COMMISSIONERS CITY OF OAKLAND  

E-Print Network [OSTI]

BOARD OF PORT COMMISSIONERS CITY OF OAKLAND RESOLUTION NO. 13-141 RESOLUTION APPROVING AND ADOPTING THE FIRST AMENDED AND RESTATED RENEWABLE ENERGY RESOURCE PROCUREMENT PLAN. I WHEREAS, the Board of Port (the "Agenda Report") and related agenda materials, has received the expert testimony of Port

478

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

the Department of Energy's (DOE) work related to the packaging and transport of such waste. Consistent with its and waste package performance. In light of continuing technical challenges, the Board believes that the DOEcon144vf UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300

479

RULES AND REGULATIONS ENVIRONMENTAL QUALITY BOARD  

E-Print Network [OSTI]

on best management practices to protect and restore that important resource, and to meet PennsylvaniaRULES AND REGULATIONS ENVIRONMENTAL QUALITY BOARD [25 PA. CODE CHS. 91 AND 92] Concentrated Animal Feeding Operations and Other Agricultural Operations [35 Pa.B. 5796] The Environmental Quality Board

Guiltinan, Mark

480

from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Facility April 13, 2012 Isotope Production Facility produces cancer-fighting actinium 2:32 Isotope cancer treatment...

Note: This page contains sample records for the topic "facilities safety board" 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

Fuel Fabrication Facility  

National Nuclear Security Administration (NNSA)

Construction of the Mixed Oxide Fuel Fabrication Facility Construction of the Mixed Oxide Fuel Fabrication Facility November 2005 May 2007 June 2008 May 2012...

482

DOE appoints four new members to advisory board  

Broader source: Energy.gov [DOE]

DOE has appointed four new members to its Environmental Management advisory board in Oak Ridge. Leon Baker, Richard Burroughs, Terri Likens and Ed Trujillo were introduced during the Oak Ridge Site Specific Advisory Board’s February meeting.

483

RADIATION SAFETY OFFICE UNIVERSITYOF MARYLAND  

E-Print Network [OSTI]

RADIATION SAFETY OFFICE UNIVERSITYOF MARYLAND RADIATION SAFETY MANUAL UNIVERSITY OF MARYLAND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2. Radiation Safety Committee (RSC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.4. Radiation Safety Office (RSO

Rubloff, Gary W.

484

Guide to research facilities  

SciTech Connect (OSTI)

This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

Not Available

1993-06-01T23:59:59.000Z

485

Acceptable NSLS Safety Documentation  

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

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

486

Third Radiation Effects Research Foundation Board of Councilors...  

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

Third Radiation Effects Research Foundation Board of Councilors Meeting Held in Hiroshima Third Radiation Effects Research Foundation Board of Councilors Meeting Held in Hiroshima...

487

Hydrogen Storage Materials Requirements to Meet the 2017 On Board...  

Energy Savers [EERE]

Materials Requirements to Meet the 2017 On Board Hydrogen Storage Technical Targets Hydrogen Storage Materials Requirements to Meet the 2017 On Board Hydrogen Storage Technical...

488

Department of Energy to Host Secretary of Energy Advisory Board...  

Energy Savers [EERE]

Department of Energy to Host Secretary of Energy Advisory Board Natural Gas Subcommittee Meeting Department of Energy to Host Secretary of Energy Advisory Board Natural Gas...

489

Oak Ridge Site Specific Advisory Board Committees | Department...  

Office of Environmental Management (EM)

Committees Oak Ridge Site Specific Advisory Board Committees Oak Ridge's Site Specific Advisory Board uses its committee structure to achieve its mission and conduct many of its...

490

Los Alamos National Laboratory board renews plan for education...  

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

renews giving plan Los Alamos National Laboratory board renews plan for education, economic development, charitable giving The Los Alamos National Security, LLC Board of...

491

Secretary of Energy Advisory Board Hosts Conference Call on Shale...  

Office of Environmental Management (EM)

Secretary of Energy Advisory Board Hosts Conference Call on Shale Gas Draft Report Secretary of Energy Advisory Board Hosts Conference Call on Shale Gas Draft Report November 10,...

492

Independent Scientific Advisory Board: Member Resume Brian E. Riddell  

E-Print Network [OSTI]

Independent Scientific Advisory Board: Member Resume Brian E. Riddell Appointed to Board: 1996:\\my documents\\ww\\isab\\riddell resume.doc (Chip Mcconnaha) #12;

493

Type B Accident Investigation Board Report on the September 7...  

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

Accident Investigation Board Report on the September 7, 2001, Burn Accident at Oak Ridge National Laboratory, Building 9210 Type B Accident Investigation Board Report on the...

494

Feasibility of OnBoard Thermoelectric Generation for Improved...  

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

OnBoard Thermoelectric Generation for Improved Vehicle Fuel Economy Feasibility of OnBoard Thermoelectric Generation for Improved Vehicle Fuel Economy Poster presentation at the...

495

Unreviewed Safety Question Requirements  

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

Unreviewed Safety Question Requirements FUNCTIONAL AREA GOAL: A fully compliant Unreviewed Safety Question (USQ) program is implemented and maintained across the site....

496

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

497

Dam Safety (Pennsylvania)  

Broader source: Energy.gov [DOE]

The Pennsylvania Department of Environmental Protection's Division of Dam Safety provides for the regulation and safety of dams and reservoirs throughout the Commonwealth in order to protect the...

498

RADIATION SAFETY TRAINING MANUAL Radiation Safety Office  

E-Print Network [OSTI]

RADIATION SAFETY TRAINING MANUAL Radiation Safety Office 130 DeSoto Street G-7 Parran with sources of ionizing radiation are required to be instructed in the basic principles of radiation protection and the potential risks of ionizing radiation. Radiation Safety Office personnel provide

Sibille, Etienne

499

uWaterloo Annual Department Health, Safety and Environment (HSE) Report (Workwell Version) Reporting Year: 2012 Department: ______________________________________________  

E-Print Network [OSTI]

out health, safety and environment duties under Policy #34 and HSE Management System, I attest to myuWaterloo Annual Department Health, Safety and Environment (HSE) Report (Workwell Version.safetyoffice.uwaterloo.ca Yes N/A Remarks 1. Are the following posted on Departmental HSE Bulletin Boards: a) First Aid

Czarnecki, Krzysztof

500

Future Fixed Target Facilities  

SciTech Connect (OSTI)

We review plans for future fixed target lepton- and hadron-scattering facilities, including the 12 GeV upgraded CEBAF accelerator at Jefferson Lab, neutrino beam facilities at Fermilab, and the antiproton PANDA facility at FAIR. We also briefly review recent theoretical developments which will aid in the interpretation of the data expected from these facilities.

Melnitchouk, Wolodymyr

2009-01-01T23:59:59.000Z