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1

Maintaining plant safety margins  

SciTech Connect

The Final Safety Analysis Report Forms the basis of demonstrating that the plant can operate safely and meet all applicable acceptance criteria. In order to assure that this continues through each operating cycle, the safety analysis is reexamined for each reload core. Operating limits are set for each reload core to assure that safety limits and applicable acceptance criteria are not exceeded for postulated events within the design basis. These operating limits form the basis for plant operation, providing barriers on various measurable parameters. The barriers are refereed to as limiting conditions for operation (LCO). The operating limits, being influenced by many factors, can change significantly from cycle to cycle. In order to be successful in demonstrating safe operation for each reload core (with adequate operating margin), it is necessary to continue to focus on ways to maintain/improve existing safety margins. Existing safety margins are a function of the plant type (boiling water reactor/pressurized water reactor (BWR/PWR)), nuclear system supply (NSSS) vendor, operating license date, core design features, plant design features, licensing history, and analytical methods used in the safety analysis. This paper summarizes the experience at Yankee Atomic Electric Company (YAEC) in its efforts to provide adequate operating margin for the plants that it supports.

Bergeron, P.A.

1989-01-01T23:59:59.000Z

2

Plutonium Finishing Plant safety evaluation report  

SciTech Connect

The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

Not Available

1995-01-01T23:59:59.000Z

3

Property:Number of Plants included in Capacity Estimate | Open...  

Open Energy Info (EERE)

of Plants included in Capacity Estimate Jump to: navigation, search Property Name Number of Plants included in Capacity Estimate Property Type Number Retrieved from "http:...

4

Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches  

DOE Green Energy (OSTI)

The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

Steven R. Sherman

2007-06-01T23:59:59.000Z

5

Waste Isolation Pilot Plant Safety Analysis Report  

Science Conference Proceedings (OSTI)

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

NONE

1995-11-01T23:59:59.000Z

6

Y-12 PLANT NUCLEAR SAFETY HANDBOOK  

SciTech Connect

Information needed to solve nuclear safety problems is condensed into a reference book for use by persons familiar with the field. Included are a glossary of terms; useful tables; nuclear constants; criticality calculations; basic nuclear safety limits; solution geometries and critical values; metal critical values; criticality values for intermediate, heterogeneous, and interacting systems; miscellaneous and related information; and report number, author, and subject indexes. (C.H.)

Wachter, J.W. ed.; Bailey, M.L.; Cagle, T.J.; Mee, W.T.; Pletz, R.H.; Welfare, F.G.; Youngblood, B.J. comps

1963-03-27T23:59:59.000Z

7

Assessment of Nuclear Safety Culture at the Pantex Plant, November...  

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

the Plant. Human Performance Improvement Coordinator works with the Safety Team and Human Error team from BBS to conduct human performance evaluations. B-12 Data on the...

8

Practical Guide to Vegetable Oil ProcessingChapter 15 Plant Safety Procedures  

Science Conference Proceedings (OSTI)

Practical Guide to Vegetable Oil Processing Chapter 15 Plant Safety Procedures Processing eChapters Processing Press Downloadable pdf of Chapter 15 Plant Safety Procedures from the book ...

9

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

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

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

10

Recent Progress in U.S. Nuclear Power Plant Safety  

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

Recent Progress in U.S. Nuclear Power Plant Safety Speaker(s): Robert Budnitz Date: April 15, 2010 - 12:00pm Location: 90-3122 The U.S. commercial nuclear-power industry consists...

11

Criticality Safety Information Meeting for the Hanford Plutonium Finihsing Plant, May 2012  

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

2-05-14 2-05-14 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-

12

Criticality Safety Information Meeting for the Hanford Plutonium Finihsing Plant, May 2012  

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

2-05-14 2-05-14 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-

13

Industrial Fuel Gas Demonstration Plant Program. Task III, Demonstration plant safety, industrial hygiene, and major disaster plan (Deliverable No. 35)  

SciTech Connect

This Health and Safety Plan has been adopted by the IFG Demonstration Plant managed by Memphis Light, Gas and Water at Memphis, Tennessee. The plan encompasses the following areas of concern: Safety Plan Administration, Industrial Health, Industrial Safety, First Aid, Fire Protection (including fire prevention and control), and Control of Safety Related Losses. The primary objective of this plan is to achieve adequate control of all potentially hazardous activities to assure the health and safety of all employees and eliminate lost work time to both the employees and the company. The second objective is to achieve compliance with all Federal, state and local laws, regulations and codes. Some thirty specific safe practice instruction items are included.

None

1980-03-01T23:59:59.000Z

14

Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

Kisner, Roger A [ORNL; Mullens, James Allen [ORNL; Wilson, Thomas L [ORNL; Wood, Richard Thomas [ORNL; Korsah, Kofi [ORNL; Qualls, A L [ORNL; Muhlheim, Michael David [ORNL; Holcomb, David Eugene [ORNL; Loebl, Andy [ORNL

2007-08-01T23:59:59.000Z

15

The Human Bathtub: Safety and Risk Predictions Including the Dynamic Probability of Operator Errors  

SciTech Connect

Reactor safety and risk are dominated by the potential and major contribution for human error in the design, operation, control, management, regulation and maintenance of the plant, and hence to all accidents. Given the possibility of accidents and errors, now we need to determine the outcome (error) probability, or the chance of failure. Conventionally, reliability engineering is associated with the failure rate of components, or systems, or mechanisms, not of human beings in and interacting with a technological system. The probability of failure requires a prior knowledge of the total number of outcomes, which for any predictive purposes we do not know or have. Analysis of failure rates due to human error and the rate of learning allow a new determination of the dynamic human error rate in technological systems, consistent with and derived from the available world data. The basis for the analysis is the 'learning hypothesis' that humans learn from experience, and consequently the accumulated experience defines the failure rate. A new 'best' equation has been derived for the human error, outcome or failure rate, which allows for calculation and prediction of the probability of human error. We also provide comparisons to the empirical Weibull parameter fitting used in and by conventional reliability engineering and probabilistic safety analysis methods. These new analyses show that arbitrary Weibull fitting parameters and typical empirical hazard function techniques cannot be used to predict the dynamics of human errors and outcomes in the presence of learning. Comparisons of these new insights show agreement with human error data from the world's commercial airlines, the two shuttle failures, and from nuclear plant operator actions and transient control behavior observed in transients in both plants and simulators. The results demonstrate that the human error probability (HEP) is dynamic, and that it may be predicted using the learning hypothesis and the minimum failure rate, and can be utilized for probabilistic risk analysis purposes. (authors)

Duffey, Romney B. [Atomic Energy of Canada, Ltd., 2251 Speakman Drive, Mississauga, ON, L5K 1B2 (Canada); Saull, John W. [International Federation of Airwothiness, 14 Railway Approach, East Grinstead, West Sussex, RH19 1BP (United Kingdom)

2006-07-01T23:59:59.000Z

16

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

Science Conference Proceedings (OSTI)

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

Washington TRU Solutions LLC

2005-09-01T23:59:59.000Z

17

Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant  

SciTech Connect

The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents.

Perkins, W.C.; Durant, W.S.; Dexter, A.H.

1980-12-01T23:59:59.000Z

18

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

SciTech Connect

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

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

1983-08-01T23:59:59.000Z

19

Personnel Safety for Future Magnetic Fusion Power Plants  

Science Conference Proceedings (OSTI)

The safety of personnel at existing fusion experiments is an important concern that requires diligence. Looking to the future, fusion experiments will continue to increase in power and operating time until steady state power plants are achieved; this causes increased concern for personnel safety. This paper addresses four important aspects of personnel safety in the present and extrapolates these aspects to future power plants. The four aspects are personnel exposure to ionizing radiation, chemicals, magnetic fields, and radiofrequency (RF) energy. Ionizing radiation safety is treated well for present and near-term experiments by the use of proven techniques from other nuclear endeavors. There is documentation that suggests decreasing the annual ionizing radiation exposure limits that have remained constant for several decades. Many chemicals are used in fusion research, for parts cleaning, as use as coolants, cooling water cleanliness control, lubrication, and other needs. In present fusion experiments, a typical chemical laboratory safety program, such as those instituted in most industrialized countries, is effective in protecting personnel from chemical exposures. As fusion facilities grow in complexity, the chemical safety program must transition from a laboratory scale to an industrial scale program that addresses chemical use in larger quantity. It is also noted that allowable chemical exposure concentrations for workers have decreased over time and, in some cases, now pose more stringent exposure limits than those for ionizing radiation. Allowable chemical exposure concentrations have been the fastest changing occupational exposure values in the last thirty years. The trend of more restrictive chemical exposure regulations is expected to continue into the future. Other issues of safety importance are magnetic field exposure and RF energy exposure. Magnetic field exposure limits are consensus values adopted as best practices for worker safety; a typical exposure value is ~1000 times the Earth’s magnetic field, but the Earth’s field is a very low value. Allowable static magnetic field exposure limits have remained constant over the recent past and would appear to remain constant for the foreseeable future. Some existing fusion experiments have suffered from RF energy leakage from waveguides, the typical practice to protect personnel is establishing personnel exclusion areas when systems are operating. RF exposure limits have remained fairly constant for overall body exposures, but have become more specific in the exposure frequency values. This paper describes the occupational limits for those types of exposure, how these exposures are managed, and also discusses the likelihood of more restrictive regulations being promulgated that will affect the design of future fusion power plants and safety of their personnel.

Lee Cadwallader

2009-07-01T23:59:59.000Z

20

Property:Number of Plants Included in Planned Estimate | Open Energy  

Open Energy Info (EERE)

Plants Included in Planned Estimate Plants Included in Planned Estimate Jump to: navigation, search Property Name Number of Plants Included in Planned Estimate Property Type String Description Number of plants included in the estimate of planned capacity per GEA Pages using the property "Number of Plants Included in Planned Estimate" Showing 21 pages using this property. A Alaska Geothermal Region + 3 + C Cascades Geothermal Region + 1 + Central Nevada Seismic Zone Geothermal Region + 4 + G Gulf of California Rift Zone Geothermal Region + 7 + H Hawaii Geothermal Region + 1 + Holocene Magmatic Geothermal Region + 4 + I Idaho Batholith Geothermal Region + 1 + N Northern Basin and Range Geothermal Region + 9 + Northern Rockies Geothermal Region + 0 + Northwest Basin and Range Geothermal Region + 6 +

Note: This page contains sample records for the topic "include plant safety" 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

Floating LNG plant will stress reliability and safety  

SciTech Connect

Mobil has developed a unique floating LNG plant design after extensive studies that set safety as the highest priority. The result is a production, storage and offloading platform designed to produce 6 million tons per year of LNG and up to 55,000 bpd of condensate from 1 Bcfd of feed gas. All production and off-loading equipment is supported by a square donut-shaped concrete hull, which is spread-moored. The hull contains storage tanks for 250,000 m{sup 3} of LNG, 6540,000 bbl of condensate and ballast water. Both LNG and condensate can be directly offloaded to shuttle tankers. Since the plant may be moved to produce from several different gas fields during its life, the plant and barge were designed to be generic. It can be used at any location in the Pacific Rim, with up to 15% CO{sub 2}, 100 ppm H{sub 2}S, 55 bbl/MMcf condensate and 650 ft water depth. It can be modified to handle other water depths, depending upon the environment. In addition, it is much more economical than an onshore grassroots LNG plant, with potential capital savings of 25% or more. The paper describes the machinery, meteorology and oceanography, and safety engineering.

Kinney, C.D.; Schulz, H.R.; Spring, W.

1997-07-01T23:59:59.000Z

22

Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Safety and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Enforcement and Oversight Abbreviations Used in this Report i Executive Summary iii Recommendations xi 1.0 Introduction 1 1.1 Background 2 1.2 Scope and Methodology 6 2.0 Current Safety Culture 9 2.1 Background 9 2.2 Scope and Methods 10 2.3 ORP (including DOE-WTP) 11 2.4 BNI 11 2.5 WTP Project 12 3.0 ORP Management of Safety Concerns 15 3.1 Corrective Actions for the 2010 HSS Review 15 3.2 Processes for Managing Issues 16

23

Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Safety and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Enforcement and Oversight Abbreviations Used in this Report i Executive Summary iii Recommendations xi 1.0 Introduction 1 1.1 Background 2 1.2 Scope and Methodology 6 2.0 Current Safety Culture 9 2.1 Background 9 2.2 Scope and Methods 10 2.3 ORP (including DOE-WTP) 11 2.4 BNI 11 2.5 WTP Project 12 3.0 ORP Management of Safety Concerns 15 3.1 Corrective Actions for the 2010 HSS Review 15 3.2 Processes for Managing Issues 16

24

Options for Removing Multiple Pollutants Including CO2 at Existing Coal-Fired Power Plants  

Science Conference Proceedings (OSTI)

This report is a technical review of the fuel changes and technology options for existing coal-fired power plants in response to potential new requirements for increasingly stringent multi-pollutant air emissions reductions, possibly including carbon dioxide (CO2). Preliminary costing of the major options is included. A database of the U.S. coal-fired power plants has been developed for further, more specific analyses.

2002-10-08T23:59:59.000Z

25

Nuclear safety surveillance and control of National Nuclear Safety Administration of PRC during commissioning and operation of nuclear power plants  

Science Conference Proceedings (OSTI)

This article describes the method of nuclear safety surveillance and control of National Nuclear Safety Administration (NNSA) of PRC during commissioning and operation of nuclear power plants (NPPs) and the practice for Qinshan NPP and for Guangdong Daya Bay NPP (GNPS). The results of the practice show that the surveillance models set up for Qinshan NPP and for GNPS commissioning were effective and the surveillance has played an important role for ensuring the quality and safety of the commissioning testing and consequently the nuclear safety of these two plants.

Feng, W.; Zhang, C.

1994-12-31T23:59:59.000Z

26

International Cooperation on Safety of Nuclear Plants - Nuclear...  

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

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

27

Assessment of Nuclear Safety Culture at the Pantex Plant, November 2012  

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

Pantex Plant Pantex Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Pantex Plant Table of Contents 1.0 Introduction........................................................................................................................................... 1 2.0 Scope and Methodology ....................................................................................................................... 2 3.0 Results and Conclusions ....................................................................................................................... 3 4.0 Recommendations................................................................................................................................. 5

28

Supplemnental Volume - Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Volume Volume Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS i Independent Oversight Assessment of Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant Supplemental Volume Table of Contents Foreword ...................................................................................................................................................... iii Acronyms ...................................................................................................................................................... v

29

Survey on the Use of Configuration Risk and Safety Management Tools at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

A joint project of Electricite de France (EDF) and EPRI, this project analyzed use of configuration safety and risk management tools at nuclear power plants.

1998-09-24T23:59:59.000Z

30

Resonance Evaluation of 48Ti Including Covariance for Criticality Safety Applications  

Science Conference Proceedings (OSTI)

In this work we report the methodology and the results of an evaluation carried out for 48Ti in the resolved resonance region for applications in criticality safety calculations. The evaluation was performed using the computer code SAMMY with the reduced R-matrix Reich-Moore formalism. The Bayes scheme was utilized for fitting the experimental data. New transmission and capture data were essential in the evaluation process. A complete set of resonance parameters was obtained in the energy region from thermal to 400 keV. In addition to the resonance parameters, a resonance parameter covariance matrix was also obtained. The impact of the new resonance parameter evaluation in benchmark calculations, as well as the uncertainty, was verified.

Leal, Luiz C [ORNL; Guber, Klaus H [ORNL; Arbanas, Goran [ORNL; Wiarda, Dorothea [ORNL; Koehler, Paul Edward [ORNL; Kahler, A. [Los Alamos National Laboratory (LANL)

2011-01-01T23:59:59.000Z

31

(Safety and reliability of nuclear power plant technology)  

SciTech Connect

The traveler attended the 16th MPA Seminar on the Safety and Reliability of Plant Technology with Special Emphasis on Nuclear Technology. The objective of the trip was to gather information and data that could prove useful to the US Nuclear Regulatory Commission (USNRC) sponsored Heavy-Section Steel Irradiation (HSSI) and Heavy-Section Steel Technology (HSST) Programs and to present a paper entitled, Effects of Irradiation on Initiation and Crack-Arrest Toughness of Two High-Copper Welds and on Stainless Steel Cladding. This paper summarizes results from the 5th, 6th, and 7th Irradiation Series of experiments performed within the HSSI Program by the Metals and Ceramics Division at Oak Ridge National Laboratory (ORNL).

Dickson, T.L.

1990-10-22T23:59:59.000Z

32

Review of the Portsmouth Gaseous Diffusion Plant Integrated Safety...  

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

Criteria, Review and Approach Document DNFSB Defense Nuclear Facilities Safety Board DOE U.S. Department of Energy ESH&Q Environment, Safety, Health, and Quality FBP...

33

Investigation on the Benefits of Safety Margin Improvement in CANDU Nuclear Power Plant Using an FPGA-based Shutdown System.  

E-Print Network (OSTI)

??The relationship between response time and safety margin of CANadian Deuterium Uranium (CANDU) nuclear power plant (NPP) is investigated in this thesis. Implementation of safety… (more)

She, Jingke

2012-01-01T23:59:59.000Z

34

Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant  

Science Conference Proceedings (OSTI)

Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0.88 million, the annual maintenance and surveillance cost is estimated to be about $0.095 million, and deferred decontamination is estimated to cost about $6.50 million. Therefore, passive SAFSTOR for 10 years is estimated to cost $8.33 million in nondiscounted 1981 dollars. DECON with lagoon waste stabilization is estimated to cost about $4.59 million, with an annual cost of $0.011 million for long-term care. All of these estimates include a 25% contingency. Waste management costs for DECON, including the net cost of disposal of the solvent extraction lagoon wastes by shipping those wastes to a uranium mill for recovery of residual uranium, comprise about 38% of the total decommissioning cost. Disposal of lagoon waste at a commercial low-level waste burial ground is estimated to add $10.01 million to decommissioning costs. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year committed dose equivalent to members of the public from airborne releases during normal decommissioning activities is estimated to 'Je about 4.0 man-rem. Radiation doses to the public from accidents are found to be very low for all phases of decommissioning. Occupational radiation doses from normal decommissioning operations (excluding transport operations) are estimated to be about 79 man-rem for DECON and about 80 man-rem for passive SAFSTOR with 10 years of safe storage. Doses from DECON with lagoon waste stabilization are about the same as for DECON except there is less dose resulting from transportation of radioactive waste. The number of fatalities and serious lost-time injuries not related to radiation is found to be very small for all decommissioning alternatives. Comparison of the cost estimates shows that DECON with lagoon waste stabilization is the least expensive method. However, this alternative does not allow unrestricted release of the site. The cumulative cost of maintenance and surveillance and the higher cost of deferred decontamination makes passive SAFSTOR more expensive than DECON. Seve

Elder, H. K.

1981-10-01T23:59:59.000Z

35

Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2  

SciTech Connect

This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC`s overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively.

NONE

1997-12-01T23:59:59.000Z

36

Nondestructive Evaluation: Recommended Practices for Maintaining Radiation Safety of Radiographic Operations at a Nuclear Plant  

Science Conference Proceedings (OSTI)

Radiation safety programs for radiographic operations at nuclear power plants are more complex than for those operations at other types of industrial and commercial facilities. This level of complexity arises because of the numerous challenges to maintenance of excellence in radiation safety at nuclear power facilities where sources of radiation may be found at various locations in the facility and multiple safety functions must be considered at all times. The facilities themselves are also large with mu...

2010-12-23T23:59:59.000Z

37

Concentration of Actinides in Plant Mounds at Safety Test Nuclear Sites in Nevada  

SciTech Connect

Plant mounds or blow-sand mounds are accumulations of soil particles and plant debris around large shrubs and are common features in deserts in the southwestern United States. Believed to be an important factor in their formation, the shrubs create surface roughness that causes wind-suspended particles to be deposited and resist further suspension. Shrub mounds occur in some plant communities on the Nevada Test Site, the Nevada Test and Training Range (NTTR), and Tonopah Test Range (TTR), including areas of surface soil contamination from past nuclear testing. In the 1970s as part of early studies to understand properties of actinides in the environment, the Nevada Applied Ecology Group (NAEG) examined the accumulation of isotopes of Pu, {sup 241}Am, and U in plant mounds at safety test sites. The NAEG studies found concentrations of these contaminants to be greater in shrub mounds than in the surrounding areas of desert pavement. For example, at Project 57 on the NTTR, it was estimated that 15 percent of the radionuclide inventory of the site was associated with shrub mounds, which accounted for 17 percent of the surface area of the site, a ratio of inventory to area of 0.85. At Clean Slate III at the TTR, 29 percent of the inventory was associated with approximately 32 percent of the site covered by shrub mounds, a ratio of 0.91. While the total inventory of radionuclides in intershrub areas was greater, the ratio of radionuclide inventory to area was 0.40 and 0.38, respectively, at the two sites. The comparison between the shrub mounds and adjacent desert pavement areas was made for only the top 5 cm since radionuclides at safety test sites are concentrated in the top 5 cm of intershrub areas. Not accounting for radionuclides associated with the shrub mounds would cause the inventory of contaminants and potential exposure to be underestimated. As part of its Environmental Restoration Soils Subproject, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office has proposed that the majority of its contaminated soil 'Corrective Action Units', including the safety test sites, be closed by fencing and posting with administrative controls. The concentration of actinides in the shrub mounds has important implications for postclosure management of the safety test sites. Because resuspension factors at safety test sites can be three to four orders-of-magnitude higher than soil sites associated with atmospheric tests where criticality occurred, the shrub mounds are an important factor in stabilization of actinide contaminants. Loss of shrubs associated with mounds from fire or plant die-back from drought could cause radionuclides at these sites to become more prone to suspension and water erosion until the sites are stabilized. Alternatively, although shrub mounds are usually composed of predominantly fine sand size particles, smaller silt and clay size particles in them are often high in CaCO{sub 3} content. The CaCO{sub 3} may act as a cementing agent to limit erosion of the shrub mounds even if the vegetation cover is temporarily lost.

David S. Shafer; Jenna Gommes

2008-09-15T23:59:59.000Z

38

Integrating gray system theory and logistic regression into case-based reasoning for safety assessment of thermal power plants  

Science Conference Proceedings (OSTI)

Safety assessment of thermal power plants (TPPs) is one of the important means to guarantee the safety of production in thermal power production enterprises. Due to various technical limitations, existing assessment approaches, such as analytic hierarchy ... Keywords: Case-based reasoning, Gray system theory, Intelligent decision support system, Logistic regression, Management safety assessment, Thermal power plants

Changyong Liang; Dongxiao Gu; Isabelle Bichindaritz; Xingguo Li; Chunrong Zuo; Wenen Cheng

2012-04-01T23:59:59.000Z

39

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

Science Conference Proceedings (OSTI)

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

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

1991-07-01T23:59:59.000Z

40

Risk-Informed and Performance-Based Safety Culture Assessment Method for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report provides an update of the risk management effectiveness assessment (RMEA) described in EPRI Report 1011761, Risk Management Effectiveness Assessment Application Guide. This update was performed to evaluate the capability of the RMEA to assess the effectiveness of the plant safety culture. The update considered results reported in the research literature since the 2005 publication of the application guide. It also evaluated the RMEA against the safety culture components identified by the U.S. ...

2008-12-09T23:59:59.000Z

Note: This page contains sample records for the topic "include plant safety" 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

Integrated safety assessment of an oxygen reduction project at Connecticut Yankee Atomic Power's Haddam Neck plant  

SciTech Connect

Connecticut Yankee Atomic Power Company (CYAPCo) has implemented an Integrated Safety Assessment Program (ISAP) for the integrated evaluation and prioritization of plant-specific licensing issues, regulatory policy issues, and plant improvement projects. As part of the ISAP process, probabilistic risk assessment (PRA) is utilized to evaluate the net safety impact of plant modification projects. On a few occasions, implementation of this approach has resulted in the identification of projects with negative safety impacts that could not be quantified via the normal design review and 10CFR50.59 safety evaluation process. An example is a plant modification that was proposed to reduce the oxygen in the Haddam Neck plant's demineralized water storage tank (DWST). The project involved the design and installation of a nitrogen blanketing system on the DWST. The purpose of the project was to reduce the oxygen content on the secondary side, consistent with recommendations from the Electric Power Research Institute Steam Generator Owners Group. Oxygen is one of the contributors to the corrosion process in systems in contact with the feedwater and can cause damage to associated components if not controlled.

Aubrey, J.E.

1987-01-01T23:59:59.000Z

42

Assessment of modular construction for safety-related structures at advanced nuclear power plants  

SciTech Connect

Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules.

Braverman, J.; Morante, R.; Hofmayer, C.

1997-03-01T23:59:59.000Z

43

Design of Safety Significant Safety Instrumented Systems Used...  

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

both analog and digital control systems are widely used in many industries, including in commercial nuclear power plants, for safety-related applications. SISs are also used in...

44

Plant Modernization with Digital Reactor Protection System Safety System Upgrades at US Nuclear Power Stations  

SciTech Connect

As the current fleet of nuclear power plants in the US reaches 25+ years of operation, obsolescence is driving many utilities to implement upgrades to both their safety and non-safety-related Instrumentation and Control (I and C) Systems. Digital technology is the predominant replacement technology for these upgrades. Within the last 15 years, digital control systems have been deployed in non-safety- related control applications at many utilities. In addition, a few utilities have replaced small safety-related systems utilizing digital technology. These systems have shown digital technology to be robust, reliable and simpler to maintain. Based upon this success, acceptance of digital technology has gained momentum with both utilities and regulatory agencies. Today, in an effort to extend the operating lives of their nuclear stations and resolve obsolescence of critical components, utilities are now pursuing digital technology for replacement of their primary safety systems. AREVA is leading this effort in the United States with the first significant digital upgrade of a major safety system. AREVA has previously completed upgrades to safety-related control systems emergency diesel engine controls and governor control systems for a hydro station which serves as the emergency power source for a nuclear station. Currently, AREVA is implementing the replacement of both the Reactor Protection System (RPS) and the Engineered Safety Features Actuation System (ESFAS) on all three units at a US PWR site. (authors)

Heckle, Wm. Lloyd; Bolian, Tricia W. [AREVA NP, an AREVA and Siemens Company, 1345 Ridgeland Parkway, Suite 130 (United States)

2006-07-01T23:59:59.000Z

45

Luminant's Big Brown Plant wins for continuous improvement and safety programs  

SciTech Connect

Staff from Luminant's Big Brown Plant accepted the PRB Coal Users' Group's top honour for innovative improvements to coal-handling systems and a sterling safety record. The numbers reveal their accomplishments: an average EFOR less than 4%, an availability factor averaging 90% for a plant that burns a lignite/PRB mix, and staff who worked more than 2.6 million man-hours since March 2000 without a lost-time injury. 13 photos., 1 tab.

Peltier, R.

2008-07-15T23:59:59.000Z

46

Idaho Chemical Processing Plant safety document ICPP hazardous chemical evaluation  

Science Conference Proceedings (OSTI)

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

Harwood, B.J.

1993-01-01T23:59:59.000Z

47

Qualification of safety-critical systems in TVO nuclear power plants  

Science Conference Proceedings (OSTI)

Teollisuuden Voima Oy (TVO) operates two nuclear power plant units in Finland and has started to build a third one. The current nuclear power units have to continuously maintain and update existing instrumentation and control systems (I&C). Each new ... Keywords: FMECA, SPICE, instrumentation and control, qualification, safety-critical systems

Juha Halminen; Risto Nevalainen

2007-11-01T23:59:59.000Z

48

Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper  

SciTech Connect

This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

Pete Jordan

2010-09-01T23:59:59.000Z

49

Single parameter controls for nuclear criticality safety at the Oak Ridge Y-12 Plant  

SciTech Connect

At the Oak Ridge Y-12 Plant, there are numerous situations in which nuclear criticality safety must be assured and subcriticality demonstrated by some method other than the straightforward use of the double contingency principle. Some cases are cited, and the criticality safety evaluation of contaminated combustible waste collectors is considered in detail. The criticality safety evaluation for combustible collectors is based on applying one very good control to the one controllable parameter. Safety can only be defended when the contingency of excess density is limited to a credible value based on process knowledge. No reasonable single failure is found that will result in a criticality accident. The historically accepted viewpoint is that this meets double contingency, even though there are not two independent controls on the single parameter of interest.

Baker, J.S.; Peek, W.M.

1995-01-13T23:59:59.000Z

50

Review of the Portsmouth Gaseous Diffusion Plant Integrated Safety Management System Phase I Verification Review, April 2013  

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

Portsmouth Gaseous Diffusion Plant Portsmouth Gaseous Diffusion Plant Integrated Safety Management System Phase I Verification Review April 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background........................................................................................................................................... 1 4.0 Methodology......................................................................................................................................... 1

51

Review of the Portsmouth Gaseous Diffusion Plant Integrated Safety Management System Phase I Verification Review, April 2013  

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

Portsmouth Gaseous Diffusion Plant Portsmouth Gaseous Diffusion Plant Integrated Safety Management System Phase I Verification Review April 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background........................................................................................................................................... 1 4.0 Methodology......................................................................................................................................... 1

52

Include in Column B cost of all composition produced by plant. Include in Column C cost of all operations not involving printing (Col. A)  

E-Print Network (OSTI)

occupied (whether Government-owned or rented), utilities, etc. (14.5 cents per month per square foot. Amount spent for rental of equipment Total cost (Use col.A total from this line to compute cost per 1 units produced in plant this fiscal quarter Total units produced in plant this fiscal year Cost per 1

US Army Corps of Engineers

53

Nuclear Maintenance Applications Center: Motor Management Guide Supporting Plant License Renewal Including Environmental Qualification Considerations  

Science Conference Proceedings (OSTI)

This report was developed by the Electric Power Research Institute’s Large Electric Motor Users Group Information Working Group, which includes motor engineers, motor specialist consultants, and vendors. Environmental qualification (EQ) program owners were also involved in the development of this report. This report addresses the most important elements of a sound motor management program to support an informed decision on motor preservation and motor life extension. Motor life extensions of ...

2013-06-07T23:59:59.000Z

54

PROBABILISTIC SAFETY ASSESSMENT OF OPERATIONAL ACCIDENTS AT THE WASTE ISOLATION PILOT PLANT  

Science Conference Proceedings (OSTI)

This report presents a probabilistic safety assessment of radioactive doses as consequences from accident scenarios to complement the deterministic assessment presented in the Waste Isolation Pilot Plant (WIPP) Safety Analysis Report (SAR). The International Council of Radiation Protection (ICRP) recommends both assessments be conducted to ensure that ''an adequate level of safety has been achieved and that no major contributors to risk are overlooked'' (ICRP 1993). To that end, the probabilistic assessment for the WIPP accident scenarios addresses the wide range of assumptions, e.g. the range of values representing the radioactive source of an accident, that could possibly have been overlooked by the SAR. Routine releases of radionuclides from the WIPP repository to the environment during the waste emplacement operations are expected to be essentially zero. In contrast, potential accidental releases from postulated accident scenarios during waste handling and emplacement could be substantial, which necessitates the need for radiological air monitoring and confinement barriers (DOE 1999). The WIPP Safety Analysis Report (SAR) calculated doses from accidental releases to the on-site (at 100 m from the source) and off-site (at the Exclusive Use Boundary and Site Boundary) public by a deterministic approach. This approach, as demonstrated in the SAR, uses single-point values of key parameters to assess the 50-year, whole-body committed effective dose equivalent (CEDE). The basic assumptions used in the SAR to formulate the CEDE are retained for this report's probabilistic assessment. However, for the probabilistic assessment, single-point parameter values were replaced with probability density functions (PDF) and were sampled over an expected range. Monte Carlo simulations were run, in which 10,000 iterations were performed by randomly selecting one value for each parameter and calculating the dose. Statistical information was then derived from the 10,000 iteration batch, which included 5%, 50%, and 95% dose likelihood, and the sensitivity of each assumption to the calculated doses. As one would intuitively expect, the doses from the probabilistic assessment for most scenarios were found to be much less than the deterministic assessment. The lower dose of the probabilistic assessment can be attributed to a ''smearing'' of values from the high and low end of the PDF spectrum of the various input parameters. The analysis also found a potential weakness in the deterministic analysis used in the SAR, a detail on drum loading was not taken into consideration. Waste emplacement operations thus far have handled drums from each shipment as a single unit, i.e. drums from each shipment are kept together. Shipments typically come from a single waste stream, and therefore the curie loading of each drum can be considered nearly identical to that of its neighbor. Calculations show that if there are large numbers of drums used in the accident scenario assessment, e.g. 28 drums in the waste hoist failure scenario (CH5), then the probabilistic dose assessment calculations will diverge from the deterministically determined doses. As it is currently calculated, the deterministic dose assessment assumes one drum loaded to the maximum allowable (80 PE-Ci), and the remaining are 10% of the maximum. The effective average of drum curie content is therefore less in the deterministic assessment than the probabilistic assessment for a large number of drums. EEG recommends that the WIPP SAR calculations be revisited and updated to include a probabilistic safety assessment.

Rucker, D.F.

2000-09-01T23:59:59.000Z

55

The Integrated Safety Management System Verification Enhancement Review of the Plutonium Finishing Plant (PFP)  

SciTech Connect

The primary purpose of the verification enhancement review was for the DOE Richland Operations Office (RL) to verify contractor readiness for the independent DOE Integrated Safety Management System Verification (ISMSV) on the Plutonium Finishing Plant (PFP). Secondary objectives included: (1) to reinforce the engagement of management and to gauge management commitment and accountability; (2) to evaluate the ''value added'' benefit of direct public involvement; (3) to evaluate the ''value added'' benefit of direct worker involvement; (4) to evaluate the ''value added'' benefit of the panel-to-panel review approach; and, (5) to evaluate the utility of the review's methodology/adaptability to periodic assessments of ISM status. The review was conducted on December 6-8, 1999, and involved the conduct of two-hour interviews with five separate panels of individuals with various management and operations responsibilities related to PFP. A semi-structured interview process was employed by a team of five ''reviewers'' who directed open-ended questions to the panels which focused on: (1) evidence of management commitment, accountability, and involvement; and, (2) consideration and demonstration of stakeholder (including worker) information and involvement opportunities. The purpose of a panel-to-panel dialogue approach was to better spotlight: (1) areas of mutual reinforcement and alignment that could serve as good examples of the management commitment and accountability aspects of ISMS implementation, and, (2) areas of potential discrepancy that could provide opportunities for improvement. In summary, the Review Team found major strengths to include: (1) the use of multi-disciplinary project work teams to plan and do work; (2) the availability and broad usage of multiple tools to help with planning and integrating work; (3) senior management presence and accessibility; (4) the institutionalization of worker involvement; (5) encouragement of self-reporting and self-assessment by management; (6) the availability of multiple internal communication mechanisms; and, (7) the existence of overall facility-wide safety management goals as well as individualized project work team goals. Major opportunities for improvement identified include: (1) the enhancement of external communications relative to ISM; (2) the institutionalization of ISM-related performance agreements/incentives; (3) the strengthening of feedback loops; (4) fine-tuning the use of tools; and, (5) the formalization of good practices.

BRIGGS, C.R.

2000-02-09T23:59:59.000Z

56

Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant  

SciTech Connect

The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

Meijing Wu; Guozhang Shen [Qinshan Nuclear power company (China)

2006-07-01T23:59:59.000Z

57

Nuclear safety procedure upgrade project at USEC/MMUS gaseous diffusion plants  

SciTech Connect

Martin Marietta Utility Services has embarked on a program to upgrade procedures at both of its Gaseous Diffusion Plant sites. The transition from a U.S. Department of Energy government-operated facility to U.S. Nuclear Regulatory Commission (NRC) regulated has necessitated a complete upgrade of plant operating procedures and practices incorporating human factors as well as a philosophy change in their use. This program is designed to meet the requirements of the newly written 10CFR76, {open_quotes}The Certification of Gaseous Diffusion Plants,{close_quotes} and aid in progression toward NRC certification. A procedures upgrade will help ensure increased nuclear safety, enhance plant operation, and eliminate personnel procedure errors/occurrences.

Kocsis, F.J. III

1994-12-31T23:59:59.000Z

58

Safety implications associated with in-plant pressurized gas storage and distribution systems in nuclear power plants  

SciTech Connect

Storage and handling of compressed gases at nuclear power plants were studied to identify any potential safety hazards. Gases investigated were air, acetylene, carbon dioxide, chlorine, Halon, hydrogen, nitrogen, oxygen, propane, and sulfur hexaflouride. Physical properties of the gases were reviewed as were applicable industrial codes and standards. Incidents involving pressurized gases in general industry and in the nuclear industry were studied. In this report general hazards such as missiles from ruptures, rocketing of cylinders, pipe whipping, asphyxiation, and toxicity are discussed. Even though some serious injuries and deaths over the years have occurred in industries handling and using pressurized gases, the industrial codes, standards, practices, and procedures are very comprehensive. The most important safety consideration in handling gases is the serious enforcement of these well-known and established methods. Recommendations are made concerning compressed gas cylinder missiles, hydrogen line ruptures or leaks, and identification of lines and equipment.

Guymon, R.H.; Casto, W.R.; Compere, E.L.

1985-05-01T23:59:59.000Z

59

Management of the aging of critical safety-related concrete structures in light-water reactor plants  

SciTech Connect

The Structural Aging Program has the overall objective of providing the USNRC with an improved basis for evaluating nuclear power plant safety-related structures for continued service. The program consists of a management task and three technical tasks: materials property data base, structural component assessment/repair technology, and quantitative methodology for continued-service determinations. Objectives, accomplishments, and planned activities under each of these tasks are presented. Major program accomplishments include development of a materials property data base for structural materials as well as an aging assessment methodology for concrete structures in nuclear power plants. Furthermore, a review and assessment of inservice inspection techniques for concrete materials and structures has been complete, and work on development of a methodology which can be used for performing current as well as reliability-based future condition assessment of concrete structures is well under way. 43 refs., 3 tabs.

Naus, D.J.; Oland, C.B. (Oak Ridge National Lab., TN (USA)); Arndt, E.G. (Nuclear Regulatory Commission, Washington, DC (USA))

1990-01-01T23:59:59.000Z

60

Implementation of Recommendations from the One System Comparative Evaluation of the Hanford Tank Farms and Waste Treatment Plant Safety Bases - 14137  

SciTech Connect

A Comparative Evaluation was conducted for One System Integrated Project Team to compare the safety bases for the Hanford Waste Treatment and Immobilization Plant Project (WTP) and Tank Operations Contract (TOC) (i.e., Tank Fanns) by an Expert Review Team. The evaluation had an overarching purpose to facilitate effective integration between WTP and TOC safety bases. It was to provide One System management with an objective evaluation of identified differences in safety basis process requirements, guidance, direction, procedures, and products (including safety controls, key safety basis inputs and assumptions, and consequence calculation methodologies) between WTP and TOC. The evaluation identified 25 recommendations (Opportunities for Integration). The resolution of these recommendations resulted in 16 implementation plans. The completion of these implementation plans will help ensure consistent safety bases for WTP and TOC along with consistent safety basis processes. procedures, and analyses. and should increase the likelihood of a successful startup of the WTP. This early integration will result in long-term cost savings and significant operational improvements. In addition, the implementation plans lead to the development of eight new safety analysis methodologies that can be used at other U.S. Department of Energy (US DOE) complex sites where URS Corporation is involved.

Garrett, Richard L.; Niemi, Belinda J.; Paik, Ingle K.; Buczek, Jeffrey A.; Lietzow, J.; McCoy, F.; Beranek, F.; Gupta, M.

2013-11-07T23:59:59.000Z

Note: This page contains sample records for the topic "include plant safety" 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

Aging of turbine drives for safety-related pumps in nuclear power plants  

SciTech Connect

This study was performed to examine the relationship between time-dependent degradation and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety-related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized-water reactor plants and in the Reactor Core Isolation Cooling and High-Pressure Coolant Injection systems for boiling-water reactor plants. This research has been conducted by examination of failure data in the Nuclear Plant Reliability Data System, review of Licensee Event Reports, discussion of problems with operating plant personnel, and personal observation. The reported failure data were reviewed to determine the cause of the event and the method of discovery. Based on the research results, attempts have been made to determine the predictability of failures and possible preventive measures that may be implemented. Findings in a recent study of AFW systems indicate that the turbine drive is the single largest contributor to AFW system degradation. However, examination of the data shows that the turbine itself is a reliable piece of equipment with a good service record. Most of the problems documented are the result of problems with the turbine controls and the mechanical overspeed trip mechanism; these apparently stem from three major causes which are discussed in the text. Recent improvements in maintenance practices and procedures, combined with a stabilization of the design, have led to improved performance resulting in a reliable safety-related component. However, these improvements have not been universally implemented.

Cox, D.F. [Oak Ridge National Lab., TN (United States)

1995-06-01T23:59:59.000Z

62

The potential role of new technology for enhanced safety and performance of nuclear power plants through improved service maintenance  

E-Print Network (OSTI)

Refinements in the safety and performance of nuclear power plants must be made to maintain public confidence and ensure competitiveness with other power sources. The aircraft industry, US Navy, and other programs have ...

Achorn, Ted Glen

1991-01-01T23:59:59.000Z

63

DISPOSAL OF TRU WASTE FROM THE PLUTONIUM FINISHING PLANT IN PIPE OVERPACK CONTAINERS TO WIPP INCLUDING NEW SECURITY REQUIREMENTS  

Science Conference Proceedings (OSTI)

The Department of Energy is responsible for the safe management and cleanup of the DOE complex. As part of the cleanup and closure of the Plutonium Finishing Plant (PFP) located on the Hanford site, the nuclear material inventory was reviewed to determine the appropriate disposition path. Based on the nuclear material characteristics, the material was designated for stabilization and packaging for long term storage and transfer to the Savannah River Site or, a decision for discard was made. The discarded material was designated as waste material and slated for disposal to the Waste Isolation Pilot Plant (WIPP). Prior to preparing any residue wastes for disposal at the WIPP, several major activities need to be completed. As detailed a processing history as possible of the material including origin of the waste must be researched and documented. A technical basis for termination of safeguards on the material must be prepared and approved. Utilizing process knowledge and processing history, the material must be characterized, sampling requirements determined, acceptable knowledge package and waste designation completed prior to disposal. All of these activities involve several organizations including the contractor, DOE, state representatives and other regulators such as EPA. At PFP, a process has been developed for meeting the many, varied requirements and successfully used to prepare several residue waste streams including Rocky Flats incinerator ash, Hanford incinerator ash and Sand, Slag and Crucible (SS&C) material for disposal. These waste residues are packed into Pipe Overpack Containers for shipment to the WIPP.

Hopkins, A.M.; Sutter, C.; Hulse, G.; Teal, J.

2003-02-27T23:59:59.000Z

64

Nuclear criticality safety  

SciTech Connect

Important facts of the nuclear criticality safety field are covered in this volume. Both theoretical and practical aspects of the subject are included, based on insights provided by criticality experts and published information from many sources. An overview of nuclear criticality safety theory and a variety of practical in-plant operation applications are presented. Underlying principles of nuclear criticality safety are introduced and the state of the art of this technical discipline is reviewed. Criticality safety theoretical concepts, accident experience, standards, experiments computer calculations, integration of safety methods into individual practices, and overall facility operations are all included.

Knief, R.A.

1985-01-01T23:59:59.000Z

65

Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the Orientation Visit to the Pantex Plant - October 26-28, 2010  

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

Orientation Visit to the Pantex Orientation Visit to the Pantex Plant - October 26-28, 2010 The U.S. Department of Energy (DOE) Office of Independent Oversight, within the Office of Health, Safety and Security (HSS), conducted an orientation visit to the DOE Pantex Site Office (PXSO) and the Pantex Plant in Amarillo, Texas, from October 26-28, 2010. The purpose of the visit was to increase HSS personnel's operational awareness of Pantex Plant activities and to determine how HSS can carry out its independent oversight and mission support responsibilities in a way that encourages a partnership with PXSO. PXSO and Pantex Plant staff provided HSS personnel with detailed tours of plant facilities, including warehouses, vaults, shipping and receiving docks, bays, cells, and the

66

Audit of construction of an environmental, safety, and health analytical laboratory at the Pantex Plant  

Science Conference Proceedings (OSTI)

This document is a report from the Office of the Inspector General, US DOE. The report evaluates the need for the construction of an Environmental, Safety, and Health Laboratory at the Pantex Plant and if this project is the most cost effective manner in which to meet mission needs. It was found that: (1) mission needs were being met with existing facilities, (2) required evaluations of alternatives were not performed, (3) decisions were made based on out-dated justifications, and (4) the expenditure of $8.4M was unnecessary. As a result, it was recommended that funded be suspended until the need is clearly established.

NONE

1995-10-01T23:59:59.000Z

67

Plant Application of On-Line Monitoring for Calibration Interval Extension of Safety-Related Instruments: Volume 1 and 2  

Science Conference Proceedings (OSTI)

Temperature, pressure, and other instruments in important applications in nuclear power plants are calibrated periodically to ensure reliable measurements and plant safety. Calibrations are typically performed once every fuel cycle (that is, once every 18 to 24 months). Through calibration activities, substantial labor is devoted to isolating the instruments, calibrating them, and returning them to service. In recent years, reviews of calibration histories of process instruments in nuclear power plants h...

2006-12-22T23:59:59.000Z

68

Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

O, J.M.; Higgins, J.; Stephen Fleger - NRC

2011-09-19T23:59:59.000Z

69

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

SciTech Connect

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

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

1991-06-01T23:59:59.000Z

70

Pilot Application of Risk-Informed Safety Margins to Support Nuclear Plant Long-Term Operation Decisions  

Science Conference Proceedings (OSTI)

This report describes an industry application of the risk-informed safety margin characterization (RISMC) framework to the analysis of the impacts of a power uprate to a loss of main feedwater (LOMFW) event. The primary objective of this effort was to assess the changes in the safety margins for this event that result from the elevated power levels associated with a hypothetical plant power uprate. This analysis focused on the probabilistic risk assessment modeling of feed-and-bleed operation for ...

2012-12-12T23:59:59.000Z

71

Pantex Plant final safety analysis report, Zone 4 magazines. Staging or interim storage for nuclear weapons and components: Issue D  

SciTech Connect

This Safety Analysis Report (SAR) contains a detailed description and evaluation of the significant environmental, safety, and health (ES&H) issues associated with the operations of the Pantex Plant modified-Richmond and steel arch construction (SAC) magazines in Zone 4. It provides (1) an overall description of the magazines, the Pantex Plant, and its surroundings; (2) a systematic evaluations of the hazards that could occur as a result of the operations performed in these magazines; (3) descriptions and analyses of the adequacy of the measures taken to eliminate, control, or mitigate the identified hazards; and (4) analyses of potential accidents and their associated risks.

Not Available

1993-04-01T23:59:59.000Z

72

Steam Generator Replacement and Power Up-rating on Tihange 2 Nuclear Plant Safety Study Analyses  

SciTech Connect

The Tihange2 900 MWe 3-L PWR NPP, operated by the Belgian utility Electrabel, was first commissioned in 1982 with a design core power of 2775 MWth. Following an initial core power up-rating by 4,5% in 1995, Electrabel has since replaced the Steam Generators which has allowed a further core power increase by roughly 5% (total 10%) in 2001. For both of each projects, licensing and implementation studies were successfully performed by Tractebel Energy Engineering and Framatome ANP. The demanding new operating conditions required a complete review of the plant design basis for which advanced methods were applied and licensed through a continuous process of discussions with the client and the Belgian Safety Authorities AVN. The licensing process required flexibility in the methods application in order to meet the specific requirements of the S.A., which was achieved within the time schedule and without jeopardising the technical objectives of the utility. (authors)

Malaval, Andre; Marin-Lafleche, Pascale; Forgeot d'Arc, Myriam; Collin, Celine [Framatome ANP (France)

2002-07-01T23:59:59.000Z

73

Environmental Safety and Health Analytical Laboratory, Pantex Plant, Amarillo, Texas. Final Environmental Assessment  

SciTech Connect

The US Department of Energy (DOE) has prepared an Environmental Assessment (EA) of the construction and operation of an Environmental Safety and Health (ES&H) Analytical Laboratory and subsequent demolition of the existing Analytical Chemistry Laboratory building at Pantex Plant near Amarillo, Texas. In accordance with the Council on Environmental Quality requirements contained in 40 CFR 1500--1508.9, the Environmental Assessment examined the environmental impacts of the Proposed Action and discussed potential alternatives. Based on the analysis of impacts in the EA, conducting the proposed action, construction of an analytical laboratory and demolition of the existing facility, would not significantly effect the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA) and the Council on Environmental Quality regulations in 40 CFR 1508.18 and 1508.27.

NONE

1995-06-01T23:59:59.000Z

74

Privatization of the gaseous diffusion plants and impacts on nuclear criticality safety administration  

SciTech Connect

The Energy Policy Act of 1992 created the United States Enrichment Corporation (USEC) on July 1, 1993. The USEC is a government-owned business that leases those Gaseous Diffusion Plant (GDP) facilities at the Portsmouth, Ohio, and Paducah, Kentucky, sites from the U.S. Department of Energy (DOE) that are required for enriching uranium. Lockheed Martin Utility Services is the operating contractor for the USEC-leased facilities. The DOE has retained use of, and regulation over, some facilities and areas at the Portsmouth and Paducah sites for managing legacy wastes and environmental restoration activities. The USEC is regulated by the DOE, but is currently changing to regulation under the U.S. Nuclear Regulatory Commission (NRC). The USEC is also preparing for privatization of the uranium enrichment enterprise. These changes have significantly affected the nuclear criticality safety (NCS) programs at the sites.

D`Aquila, D.M.; Holliday, R.T. [Lockheed Martin Utility Services, Inc., Piketon, OH (United States); Dean, J.C. [Lockheed Martin Utility Services, Inc., Paducah, KY (United States)

1996-12-31T23:59:59.000Z

75

Generic Requirements Specification for Upgrading the Safety-Related Reactor Trip and Engineered Safety Features Actuation Systems in Westinghouse PWR Nuclear Power Plants  

Science Conference Proceedings (OSTI)

To address obsolescence concerns, a generic requirements specification for digital upgrades to existing reactor trip systems and engineered safety features actuation systems in a Westinghouse pressurized water reactor (PWR) was developed. System requirements are based on a 4-loop PWR with a solid-state protection system since this typifies the most advanced capability level. However, the specification is applicable to relay-based 2- and 3-loop plants where some or all of the advances in the newest solid-...

2001-10-19T23:59:59.000Z

76

Pilot Application of Risk Informed Safety Margins to Support Nuclear Plant Long-Term Operation Decisions: Impacts on Safety Margins of Extended Power Uprates for BWR Station Blackout Events  

Science Conference Proceedings (OSTI)

The risk-informed safety margin characterization (RISMC) framework is a technically robust approach that could be used to analyze nuclear power plant (NPP) safety margins for issues of significance to NPP safety. This report describes application of the RISMC framework to analysis of the impacts of an extended power uprate (EPU) to a boiling water reactor (BWR) station blackout (SBO) event, with emphasis on changes in safety margins due to elevated power levels. The analysis focused on probabilistic ...

2013-08-27T23:59:59.000Z

77

Application of Data Stream Outlier Mining Techniques in Steam Generator Safety Early Warning System of Nuclear Power Plant  

Science Conference Proceedings (OSTI)

Mining outliers in data streams is a popular research issue in data mining field, which can help to find outliers under abnormal condition and then corresponding measures can be taken. The security guarantee of nuclear power plant is the center topic ... Keywords: safety early warning system, data stream, outlier mining, NPP

Liu Dingping, Zheng Kaitao, Yan Qiqi

2013-01-01T23:59:59.000Z

78

Operational safety enhancement of Soviet-designed nuclear reactors via development of nuclear power plant simulators and transfer of related technology  

SciTech Connect

The US Department of Energy (DOE), under the US government`s International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper.

Kohut, P.; Epel, L.G.; Tutu, N.K. [and others

1998-08-01T23:59:59.000Z

79

Cost update technology, safety, and costs of decommissioning a reference uranium hexafluoride conversion plant  

Science Conference Proceedings (OSTI)

The purpose of this study is to update the cost estimates developed in a previous report, NUREG/CR-1757 (Elder 1980) for decommissioning a reference uranium hexafluoride conversion plant from the original mid-1981 dollars to values representative of January 1993. The cost updates were performed by using escalation factors derived from cost index trends over the past 11.5 years. Contemporary price quotes wee used for costs that have increased drastically or for which is is difficult to find a cost trend. No changes were made in the decommissioning procedures or cost element requirements assumed in NUREG/CR-1757. This report includes only information that was changed from NUREG/CR-1757. Thus, for those interested in detailed descriptions and associated information for the reference uranium hexafluoride conversion plant, a copy of NUREG/CR-1757 will be needed.

Miles, T.L.; Liu, Y.

1995-08-01T23:59:59.000Z

80

Enhanced-safety underground nuclear power plants based on the use of proven ship-building equipment and technology  

SciTech Connect

Investigations performed in the last few years by the State Science Center of the Russian Federation - Academician A. N. Krylov Central Scientific-Research Institute, together with specialized enterprises of the Ministry of Atomic Energy of the Russian Federation, Sudprom, and other agencies of Russia, have shown the promise of marine nuclear power plants for producing underground nuclear power plants with a higher degree of protection from external and internal actions of different intensity. The concept was developed on the basis of an analysis of the energy supply in different regions of Russia and the near-abroad using fossil fuels (lignite, oil, natural gas). The change in the international environment, which makes it possible to convert the military technology, frees the industrial potential and skilled workers in Russia for development of products for the national economy. Stricter international standards and rules for increased safety and protection of nuclear power plants made it necessary to develop a new generation of reactors for ground-based power plants, which under the modern economic conditions cannot be implemented within the time periods acceptable for economics for most of the countries surrounding Russia. In the development of a new generation of ground-based nuclear power plants, the intense improvement of the aviation and space technology must be taken into account. This is connected with the increase in the catastrophes and the threat they present to the safety of unprotected power plants. This article is an abstract of the entire report.

Pashin, V.M.; Petrov, E.L.; Khazov, B.S.

1995-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "include plant safety" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Integrated Safety Management System Phase I Verification for the Plutonium Finishing Plant (PFP) [VOL 1 & 2  

Science Conference Proceedings (OSTI)

U.S. Department of Energy (DOE) Policy 450.4, Safety Management System Policy commits to institutionalizing an Integrated Safety Management System (ISMS) throughout the DOE complex as a means of accomplishing its missions safely. DOE Acquisition Regulation 970.5204-2 requires that contractors manage and perform work in accordance with a documented safety management system.

SETH, S.S.

2000-01-10T23:59:59.000Z

82

Developing Best Practices for Small and Very-Small Pork Processing Plants to Improve Food Safety  

E-Print Network (OSTI)

Best practices have previously been developed for beef slaughter and further processing operations with input from academic and industry leaders. Best practices for pork processors have not been developed, and those developed for the beef industry may not always be applicable to the operations of Small and Very Small establishments. Small and Very Small establishments warrant unique consideration in terms of financial and technological capabilities. While larger processors utilize multiple capital-intensive microbial interventions, smaller establishments often must rely on sanitary practices and more traditional interventions. In order to develop best practices for Small and Very Small pork slaughter and further processing establishments, a survey instrument seeking information on establishment and facility characteristics as well as current sanitary practices was distributed to Small and Very Small establishments in the Southwest region. Additionally, microbiological baselines were established for six Small and Very Small pork slaughter and/or further processing establishments to allow the efficacy of best practices to be assessed following implementation in each of the six plants. Survey responses revealed areas where best practice recommendation efforts may be focused, and microbiological baseline data provided insight to the condition of carcasses and environmental surfaces using current sanitary practices. Combined, the data reveal the opportunities for improvement in the food safety systems of Small and Very Small pork processing establishments.

Hendricks, Matthew Benton

2013-05-01T23:59:59.000Z

83

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

E-Print Network (OSTI)

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

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

2001-01-01T23:59:59.000Z

84

Internal Technical Report, Safety Analysis Report 5 MW(e) Raft River Research and Development Plant  

DOE Green Energy (OSTI)

The Raft River Geothermal Site is located in Southern Idaho's Raft River Valley, southwest of Malta, Idaho, in Cassia County. EG and G idaho, Inc., is the DOE's prime contractor for development of the Raft River geothermal field. Contract work has been progressing for several years towards creating a fully integrated utilization of geothermal water. Developmental progress has resulted in the drilling of seven major DOE wells. Four are producing geothermal water from reservoir temperatures measured to approximately 149 C (approximately 300 F). Closed-in well head pressures range from 69 to 102 kPa (100 to 175 psi). Two wells are scheduled for geothermal cold 60 C (140 F) water reinjection. The prime development effort is for a power plant designed to generate electricity using the heat from the geothermal hot water. The plant is designated as the ''5 MW(e) Raft River Research and Development Plant'' project. General site management assigned to EG and G has resulted in planning and development of many parts of the 5 MW program. Support and development activities have included: (1) engineering design, procurement, and construction support; (2) fluid supply and injection facilities, their study, and control; (3) development and installation of transfer piping systems for geothermal water collection and disposal by injection; and (4) heat exchanger fouling tests.

Brown, E.S.; Homer, G.B.; Shaber, C.R.; Thurow, T.L.

1981-11-17T23:59:59.000Z

85

Internal Technical Report, Safety Analysis Report 5 MW(e) Raft River Pilot Plant  

DOE Green Energy (OSTI)

The Raft River Geothermal Site is located in Southern Idaho's Raft River Valley, southwest of Malta, Idaho, in Cassia County. EG and G idaho, Inc., is the DOE's prime contractor for development of the Raft River geothermal field. Contract work has been progressing for several years towards creating a fully integrated utilization of geothermal water. Developmental progress has resulted in the drilling of seven major DOE wells. Four are producing geothermal water from reservoir temperatures measured to approximately 149 C (approximately 300 F). Closed-in well head pressures range from 69 to 102 kPa (100 to 175 psi). Two wells are scheduled for geothermal cold 60 C (140 F) water reinjection. The prime development effort is for a power plant designed to generate electricity using the heat from the geothermal hot water. The plant is designated as the ''5 MW(e) Raft River Research and Development Plant'' project. General site management assigned to EG and G has resulted in planning and development of many parts of the 5 MW program. Support and development activities have included: (1) engineering design, procurement, and construction support; (2) fluid supply and injection facilities, their study, and control; (3) development and installation of transfer piping systems for geothermal water collection and disposal by injection; and (4) heat exchanger fouling tests.

Brown, E.S.; Homer, G.B.; Spencer, S.G.; Shaber, C.R.

1980-05-30T23:59:59.000Z

86

Qualification of Siemens Power Corporation TELEPERM XS Safety System: Compliance with EPRI TR-107330 "Generic Requirements Specifica tion for Qualifying a Commercially Available PLC for Safety-Related Applications in Nuclear Power Plants"  

Science Conference Proceedings (OSTI)

As its nuclear power plants age, the electric power industry is focusing on the development of cost-effective replacement systems for obsolete instrumentation, control, and safety systems. This report describes the generic qualification of a platform for safety-related applications that incorporates programmable logic controllers (PLCs), a technology with an excellent track record in non-nuclear applications for critical control and safety functions.

1999-11-23T23:59:59.000Z

87

Environment/Health/Safety (EHS): Safety Engineering  

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

Safety Engineering Safety Engineering provides occupational safety services to support the Lab's mission. This includes injury and illness prevention and loss control systems for...

88

Recommended electromagnetic operating envelopes for safety-related I and C systems in nuclear power plants: Draft report for comment  

Science Conference Proceedings (OSTI)

This document presents recommendations for electromagnetic operating envelopes to augment test criteria and test methods addressing electromagnetic interference (EMI), radio-frequency interference (RFI), and power surges that are applicable to safety-related instrumentation and control (I and C) systems in nuclear power plants. The Oak Ridge National Laboratory (ORNL) was engaged by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to assist in developing the technical basis for regulatory guidance on EMI/RFI immunity and power surge withstand capability (SWC). Previous research has provided recommendations on electromagnetic compatibility (EMC) design and installation practices, endorsement of EMI/RFI immunity and SWC test criteria and test methods, and determination of ambient electromagnetic conditions at nuclear power plants. The present research involves development of recommended electromagnetic envelopes that are applicable to nuclear power plant locations where safety-related I and C systems either are or may be installed. These recommended envelopes establish both emissions criteria and the levels of radiated and conducted interference that I and C systems should be able to withstand without upset or malfunction. The EMI/RFI operating envelopes are derived from conditions in comparable military environments and are confirmed by comparison with the nuclear power plant electromagnetic environment based on measured plant emissions profiles. Detailed information on specific power surge conditions in nuclear power plants is not available, so industrial guidance on representative surge characteristics for susceptibility testing is adopted. An engineering assessment of the power surge environment in nuclear power plants leads to the recommendation of operating envelopes based on location categories and exposure levels defined in IEEE Std C62.41-1991, IEEE Recommended Practice on Surge Voltages in Low-Voltage AC Power Circuits.

Ewing, P.D.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

1997-12-01T23:59:59.000Z

89

Review of nuclear power plant safety cable aging studies with recommendations for improved approaches and for future work.  

Science Conference Proceedings (OSTI)

Many U. S. nuclear power plants are approaching 40 years of age and there is a desire to extend their life for up to 100 total years. Safety-related cables were originally qualified for nuclear power plant applications based on IEEE Standards that were published in 1974. The qualifications involved procedures to simulate 40 years of life under ambient power plant aging conditions followed by simulated loss of coolant accident (LOCA). Over the past 35 years or so, substantial efforts were devoted to determining whether the aging assumptions allowed by the original IEEE Standards could be improved upon. These studies led to better accelerated aging methods so that more confident 40-year lifetime predictions became available. Since there is now a desire to potentially extend the life of nuclear power plants way beyond the original 40 year life, there is an interest in reviewing and critiquing the current state-of-the-art in simulating cable aging. These are two of the goals of this report where the discussion is concentrated on the progress made over the past 15 years or so and highlights the most thorough and careful published studies. An additional goal of the report is to suggest work that might prove helpful in answering some of the questions and dealing with some of the issues that still remain with respect to simulating the aging and predicting the lifetimes of safety-related cable materials.

Gillen, Kenneth Todd; Bernstein, Robert

2010-11-01T23:59:59.000Z

90

Independent Oversight Targeted Review of the Safety Significant Blast Door and Personnel Door Interlock Systems and Review of Federal Assurance Capability at the Pantex Plant, December 2013  

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

Targeted Review of the Targeted Review of the Safety Significant Blast Door and Personnel Door Interlock Systems and Review of Federal Assurance Capability at the Pantex Plant December 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background........................................................................................................................................... 2

91

Generic Qualification of the Triconex Corporation TRICON Triple Modular Redundant Programmable Logic Controller System for Safety-Re lated Applications in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

As its nuclear power plants age, the electric power industry is focusing on the development of cost-effective replacement systems for obsolete instrumentation, control, and safety systems. This report describes the generic qualification of a platform for safety-related applications that incorporates triple modular redundant (TMR) programmable logic controllers (PLCs), a technology with an excellent track record in non-nuclear applications for critical control and safety functions.

2000-11-29T23:59:59.000Z

92

Focused Review of Environment, Safety and Health and Emergency Management at the Kansas City Plant - Summary  

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

Environment, Safety and Health Environment, Safety and Health and Emergency Management at the Office of Independent Oversight and Performance Assurance ISM Summary Report OVERSIGHT Table of Contents 1.0 Introduction ..............................................................................1 2.0 Status and Results ....................................................................3 3.0 Conclusions ..............................................................................8 4.0 Ratings .................................................................................... 11 APPENDIX A - SUPPLEMENTAL INFORMATION .................13 APPENDIX B - SITE-SPECIFIC FINDINGS .............................15 Abbreviations Used in This Report AL Albuquerque Operations Office DOE U.S. Department of Energy

93

Nuclear power plants: structure and function  

SciTech Connect

Topics discussed include: steam electric plants; BWR type reactors; PWR type reactors; thermal efficiency of light water reactors; other types of nuclear power plants; the fission process and nuclear fuel; fission products and reactor afterheat; and reactor safety.

Hendrie, J.M.

1983-01-01T23:59:59.000Z

94

ORNL/luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT  

Office of Legacy Management (LM)

luSA-85/6 luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT OF TEE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT May 1985 Work performed as part of the RADIOLOGICAL SURVEY ACCIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U. S. DEPARTMENT OF ENERGY under Contract No. DE-AC05-840R21400 \ .-l__--.-- -- PRELIMINARY RADIOLOGICAL SURVEY OF THE FORMER HAVENS PLAEJT OF THE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT INTRODUCI' ION The Bridgeport Brass Company' s Havens plant located at Kossath and Pulaski Streets, Bridgeport, Connecticut. was used under contract with the Atomic Energy Commission (AEC) to process uranium during the period

95

Guidelines for nuclear-power-plant safety-issue-prioritization information development  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory has developed a methodology, with examples, to calculate - to an approximation serviceable for prioritization purposes - the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report is an applications guide to issue-specific calculations. A description of the approach, mathematical models, worksheets and step-by-step examples are provided. Analysis using this method is intended to provide comparable results for many issues at a cost of two staff-weeks per issue. Results will be used by the NRC to support decisions related to issue priorities in allocation of resources to complete safety issue resolutions.

Andrews, W.B.; Gallucci, R.H.V.; Heaberlin, S.W.; Bickford, W.E.; Konzek, G.J.; Strenge, D.L.; Smith, R.I.; Weakley, S.A.

1983-02-01T23:59:59.000Z

96

Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5  

SciTech Connect

This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983).

Daling, P.M.; Lavender, J.C. [Pacific Northwest National Lab., Richland, WA (United States)

1996-07-01T23:59:59.000Z

97

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

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

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

98

Guidelines for the Repair of Nuclear Power Plant Safety-Related Motors (NCIG-12)  

Science Conference Proceedings (OSTI)

These guidelines, the twelfth in a series cosponsored by NCIG, provide utilities with information on the repair of all classes of safety-related electric motors. Use of this information will permit capable repair shops to repair motors under the extension of utility quality assurance programs or by dedication of a commercially repaired motor.

1990-04-24T23:59:59.000Z

99

Nuclear criticality safety controls for uranium deposits during D and D at the Oak Ridge Gaseous Diffusion Plant  

SciTech Connect

The US Department of Energy (DOE) Deputy Assistant Secretary of Energy for Environmental Management has issued a challenge to complete DOE environmental cleanup within a decade. The response for Oak Ridge facilities is in accordance with the DOE ten-year plan which calls for completion of > 95% of environmental management work by the year 2006. This will result in a 99% risk reduction and in a significant savings in base line costs in waste management (legacy waste); remedial action (groundwater, soil, etc.); and decontamination and decommissioning (D and D). It is assumed that there will be long-term institutional control of cascade equipment, i.e., there will be no walk away from sites, and that there will be firm radioactivity release limits by 1999 for recycle metals. An integral part of these plants is the removal of uranium deposits which pose nuclear criticality safety concerns in the shut down of the Oak Ridge Gaseous Diffusion Plant. DOE has initiated the Nuclear Criticality Stabilization Program to improve nuclear criticality safety by removing the larger uranium deposits from unfavorable geometry equipment. Nondestructive assay (NDA) measurements have identified the location of these deposits. The objective of the K-25 Site Nuclear Criticality Stabilization Program is to remove and place uranium deposits into safe geometry storage containers to meet the double contingency principle. Each step of the removal process results in safer conditions where multiple controls are present. Upon completion of the Program, nuclear criticality risks will be greatly reduced.

Haire, M.J.; Jordan, W.C. [Oak Ridge National Lab., TN (United States); Jollay, L.J. III; Dahl, T.L. [Oak Ridge K-25 Site, TN (United States)

1997-02-01T23:59:59.000Z

100

Inspection of Environment, Safety, and Health Management and Emergency Management at the Pantex Plant - Summary  

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

Pantex Plant Pantex Plant Summary Report Office of Independent Oversight and Performance Assurance Office of the Secretary of Energy November 2002 OVERSIGHT Table of Contents 1.0 INTRODUCTION .................................................................... 1 2.0 RESULTS ................................................................................. 4 2.1 Positive Attributes .............................................................4 2.2 Program Weaknesses ........................................................6 3.0 CONCLUSIONS .......................................................................9 4.0 RATINGS ................................................................................13 APPENDIX A - SUPPLEMENTAL INFORMATION ................... 14 APPENDIX B - SITE-SPECIFIC FINDINGS

Note: This page contains sample records for the topic "include plant safety" 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

Martin Marietta Energy Systems Nuclear Criticality Safety Improvement Program  

SciTech Connect

This report addresses questions raised by criticality safety violation at several DOE plants. Two charts are included that define the severity and reporting requirements for the six levels of accidents. A summary is given of all reported criticality incident at the DOE plants involved. The report concludes with Martin Marietta's Nuclear Criticality Safety Policy Statement. (JDH)

Speas, I.G.

1987-04-29T23:59:59.000Z

102

Plant Engineering: Guideline for the Acceptance of Commercial-Grade Design and Analysis Computer Programs Used in Nuclear Safety-Rel ated Applications  

Science Conference Proceedings (OSTI)

This report provides methodology that can be used to perform safety classification of non-process computer programs, such as design and analysis tools, that are not resident or embedded (installed as part of) plant systems, structures, and components. The report also provides guidance for using commercial-grade dedication methodology to accept commercially procured computer programs that perform a safety-related function. The guidance is intended for use by subject matter experts in the acceptance of com...

2012-06-04T23:59:59.000Z

103

Plant Engineering: Guideline for the Acceptance of Commercial-Grade Design and Analysis Computer Programs Used in Nuclear Safety-Related Applications: Revision 1 of 1025243  

Science Conference Proceedings (OSTI)

This report supersedes EPRI 1025243 and provides methodology that can be used to perform safety classification of non-process computer programs, such as design and analysis tools, that are not resident or embedded (installed as part of) plant systems, structures, and components. The report also provides guidance for using commercial-grade dedication methodology to accept commercially procured computer programs that perform a safety-related function. The guidance is intended for use by subject matter ...

2013-12-19T23:59:59.000Z

104

Assessment of inservice conditions of safety-related nuclear plant structures  

Science Conference Proceedings (OSTI)

The report is a compilation from a number of sources of information related to the condition Of structures and civil engineering features at operating nuclear power plants in the United States. The most significant information came from the hands-on inspection of the six old plants (licensed prior to 1977) performed by the staff of the Civil Engineering and Geosciences Branch (ECGB) in the Division of Engineering of the Office of Nuclear Reactor Regulation. For the containment structures, most of the information related to the degraded conditions came from the licensees as part of the Licensing Event Report System (10 CFR 50.73), or as part of the requirement under limiting condition of operation of the plant-specific Technical Specifications. Most of the information related to the degradation of other Structures and civil engineering features was extracted from the industry survey, the reported incidents, and the plant visits. The report discusses the condition of the structures and civil engineering features at operating nuclear power plants and provides information that would help detect, alleviate, and correct the degraded conditions of the structures and civil engineering features.

Ashar, H.; Bagchi, G.

1995-06-01T23:59:59.000Z

105

Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures  

SciTech Connect

Nuclear power plant (NPP) concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: (1) Degradation mechanisms, damage models, and material performance; (2) Assessment and remediation: i.e., component selection, in- service inspection, non-destructive examinations, and remedial actions; and (3) Estimation of performance at present or some future point in time: i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk. Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

Naus, Dan J [ORNL

2014-01-01T23:59:59.000Z

106

Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures  

SciTech Connect

Nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: degradation mechanisms, damage models, and material performance; assessment and remediation (i.e., component selection, in-service inspection, non-destructive examinations, and remedial actions); and estimation of performance at present or some future point in time (i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk). Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

Naus, Dan J [ORNL

2010-01-01T23:59:59.000Z

107

A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants  

SciTech Connect

The long-term availability of less expensive power and the increasing plant modification and maintenance costs have caused some utilities to re-examine the economics of nuclear power. As a result, several utilities have opted to permanently shutdown their plants. Each licensee of these permanently shutdown (PSD) plants has submitted plant-specific exemption requests for those regulations that they believe are no longer applicable to their facility. This report presents a regulatory assessment for generic BWR and PWR plants that have permanently ceased operation in support of NRC rulemaking activities in this area. After the reactor vessel is defueled, the traditional accident sequences that dominate the operating plant risk are no longer applicable. The remaining source of public risk is associated with the accidents that involve the spent fuel. Previous studies have indicated that complete spent fuel pool drainage is an accident of potential concern. Certain combinations of spent fuel storage configurations and decay times, could cause freshly discharged fuel assemblies to self heat to a temperature where the self sustained oxidation of the zircaloy fuel cladding may cause cladding failure. This study has defined four spent fuel configurations which encompass all of the anticipated spent fuel characteristics and storage modes following permanent shutdown. A representative accident sequence was chosen for each configuration. Consequence analyses were performed using these sequences to estimate onsite and boundary doses, population doses and economic costs. A list of candidate regulations was identified from a screening of 10 CFR Parts 0 to 199. The continued applicability of each regulation was assessed within the context of each spent fuel storage configuration and the results of the consequence analyses.

Travis, R.J.; Davis, R.E.; Grove, E.J.; Azarm, M.A. [Brookhaven National Lab., Upton, NY (United States)

1997-08-01T23:59:59.000Z

108

Occupational Safety Review of High Technology Facilities  

Science Conference Proceedings (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

109

Aging and service wear of air-operated valves used in safety-related systems at nuclear power plants  

SciTech Connect

Air-operated valves (AOVs) are used in a variety of safety-related applications at nuclear power plants. They are often used where rapid stroke times are required or precise control of the valve obturator is required. They can be designed to operate automatically upon loss of power, which is often desirable when selecting components for response to design basis conditions. The purpose of this report is to examine the reported failures of AOVs and determine whether there are identifiable trends in the failures related to predictable causes. This report examines the specific components that comprise a typical AOV, how those components fail, when they fail, and how such failures are discovered. It also examines whether current testing frequencies and methods are effective in predicting such failures.

Cox, D.F.; McElhaney, K.L.; Staunton, R.H.

1995-05-01T23:59:59.000Z

110

Initial Assessment of Sulfur-Iodine Process Safety Issues and How They May Affect Pilot Plant Design and Operation  

DOE Green Energy (OSTI)

The sulfur-iodine process to make hydrogen by the thermochemical splitting of water is under active development as part of a U.S. Department of Energy program. An integrated lab scale system is currently being designed and built. The next planned stage of development is a pilot plant with a thermal input of about 500 kW, equivalent to about 30,000 standard liters per hour of hydrogen production. The sulfur-iodine process contains a variety of hazards, including temperatures up to 850 ºC and hazardous chemical species including SO2, H2SO4, HI, I2, and of course H2. The siting and design of a pilot plant must consider these and other hazards. This report presents an initial analysis of the hazards that might affect pilot plant design and should be considered in the initial planning. The general hazards that have been identified include reactivity, flammability, toxicity, pressure, electrical hazards, and industrial hazards such as lifting and rotating equipment. Personnel exposure to these hazards could occur during normal operations, which includes not only running the process at the design conditions but also initial inventory loading, heatup, startup, shutdown, and system flushing before equipment maintenance. Because of the complexity and severity of the process, these ancillary operations are expected to be performed frequently. In addition, personnel could be exposed to the hazards during various abnormal situations which could include unplanned phase changes of liquids or solids, leaks of process fluids or cooling water into other process streams, unintentional introducion of foreign species into the process, and unexpected side reactions. Design of a pilot plant will also be affected by various codes and regulations such as the International Building Code, the International Fire Code, various National Fire Protection Association Codes, and the Emergency Planning and Community Right-to-Know Act.

Robert S. Cherry

2006-09-01T23:59:59.000Z

111

ITER Progress Highlights of the 8 th IAEA Technical Meeting on Fusion Power Plant Safety  

E-Print Network (OSTI)

First, I would like to personally thank Dr. Said Abdel-Khalik, the outgoing chair of the Fusion Energy Division (FED), for his service during his term. Said now serves not only as the past chair, but he has assumed the role of FED’s liaison to the ANS Public Policy Committee. I am pleased to report that the state of our division is quite strong. Division membership has exceeded 750 for three years in a row, and the student membership has grown to more than 200. These numbers reflect the strength and growth in the fusion community. ITER has ramped up dramatically in recent months with many team members moving from Naka and Garching to the Joint Work site in Cadarache, France. Current plans call for delivery of a new baseline design in the late spring of next year. In the U.S., NIF has demonstrated its full system performance on a single beam basis and is expected to have 25 % of the beams operational by January 2007. Truly, it is a very exciting time in the fusion community! Recently, Dr. Susana Reyes left the United States for a new position with the ITER safety team. In order to give her utmost attention to this exciting opportunity, Susana elected to

Plan U. S; Participation Iter

2006-01-01T23:59:59.000Z

112

The (safety-related) heat exchangers aging management guideline for commercial nuclear power plants, and developments since 1994  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE), in cooperation with the Electric Power Research Institute (EPRI) and US nuclear power plant utilities, is preparing a series of aging management guidelines (AMGs) for commodity types of components (e.g., heat exchangers, electrical cable and terminations, pumps). Commodities are included in this series based on their importance to continued nuclear plant operation and license renewal. The AMGs contain a detailed summary of operating history, stressors, aging mechanisms, and various types of maintenance and surveillance practices that can be combined to create an effective aging management program. Each AMG is intended for use by the systems engineers and plant maintenance staff (i.e., an AMG is intended to be a hands-on technical document rather than a licensing document). The heat exchangers AMG, published in June 1994, includes the following information of interest to nondestructive examination (NDE) personnel: aging mechanisms determined to be non-significant for all applications; aging mechanisms determined to be significant for some applications; effective conventional programs for managing aging; and effective unconventional programs for managing aging. Since the AMG on heat exchangers was published four years ago, a brief review has been conducted to identify emerging regulatory issues, if any. The results of this review and lessons learned from the collective set of AMGs are presented.

Clauss, J.M.

1998-08-01T23:59:59.000Z

113

Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 12  

Science Conference Proceedings (OSTI)

Supplement No. 12 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued, and (2) matters that the staff had under review when Supplement No. 11 was issued.

Tam, P.S.

1993-10-01T23:59:59.000Z

114

Safety Standards  

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

US DOE Workshop US DOE Workshop September 19-20, 2012 International perspective on Fukushima accident Miroslav Lipár Head, Operational Safety Section M.Lipar@iaea.org +43 1 2600 22691 2 Content * The IAEA before Fukushima -Severe accidents management * The IAEA actions after Fukushima * The IAEA Action plan on nuclear safety * Measures to improve operational safety * Conclusions THE IAEA BEFORE FUKUSHIMA 4 IAEA Safety Standards IAEA Safety Standards F undamental S afety Principles Safety Fundamentals f o r p ro te c ti n g p e o p l e a n d t h e e n v i ro n m e n t IAEA Safety Standards Regulations for the Safe Transport of Radioactive Material 2005 E dit ion Safety Requirements No. T S-R-1 f o r p ro te c ti n g p e o p l e a n d t h e e n v i ro n m e n t IAEA Safety Standards Design of the Reactor Core for Nuclear Power Plants

115

December 27, 2011, Department letter transmitting the Implementation Plan for Board Recommendation 2011-1, Safety Culture at the Waste Treatment and Immobilization Plant.  

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

December 27,2011 December 27,2011 The Honorable Peter S. Winokur Chairman Defense Nuclear Facilities Safety Board 625 Indiana Avenue, NW, Suite 700 Washington, DC 20004 Dear Mr. Chairman: Enclosed is the Depmiment of Energy's (DOE's) Implementation Plan (IP) for Defense Nuclear Facilities Safety Board (Board) Recommendation 2011-1, Safety Culture at the Waste Treatment and Immobilization Plant (WTP). On June 30, 20 II, the Department accepted Recommendation 20 Il-l in a letter to the Board, which was published in the Federal Register. On August 12,2011, the Board sought additional clarification about this acceptance, and on September 19,2011, I transmitted clarification to the Board, which was also published in the Federal Register. The IP provides DOE's approach to address the Board's three sub-recommendations

116

Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980  

SciTech Connect

This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for each reactor. Full-size keyword and permuted-title indexes to facilitate location of individual abstracts are provided following the text. Tables that summarize the information contained in the bibliography are also provided. The information in the tables includes a listing of the equipment items involved in the reported events and the associated number of reports for each item. Similar information is given for the various kinds of instrumentation and systems, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction).

McCormack, K.E.; Gallaher, R.B.

1982-03-01T23:59:59.000Z

117

BWRVIP-201: BWR Vessel and Internals Project, Technical Basis For Plant Specific Safety Evaluation for Hydrazine Injection for Start up ECP Reduction in BWRs  

Science Conference Proceedings (OSTI)

This report describes the technical basis for a plant-specific safety evaluation of hydrazine injection into the primary system of a BWR during startup, with the objective of minimizing the electrochemical corrosion potential (ECP), and thereby reducing intergranular stress corrosion cracking (IGSCC). PWR operators have been injecting hydrazine into primary systems at startup for many years with no observed adverse impact on fuel or materials. The report concludes that BWR hydrazine injection is feasible...

2008-11-24T23:59:59.000Z

118

Operating experience feedback report-reliability of safety-related steam turbine-driven standby pumps used in US commerical nuclear power plants  

SciTech Connect

Pump failure experience is collected by two primary means: (1) Licensee Event Reports, and (2) Nuclear Plant Reliability Data System failure reports. Certain safety-related turbine-driven standby pumps were identified by these data systems as experiencing significant ongoing repetitive failures of their turbine drivers, resulting in low reliability of the pump units. The root causes of identified failures were determined, and actions to preclude these repetitive failures were identified. 5 refs., 1 tab.

Boardman, J.R. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-01-01T23:59:59.000Z

119

Probabilistic safety assessment and reliability based maintenance policies: application to the emergency diesel generators of a nuclear power plant  

Science Conference Proceedings (OSTI)

This study is performed on the four 2.5 MWe emergency diesel generator (EDG) sets of Hydro-Quebec Gentilly-2 Nuclear Power Station. EDGs are safety related systems for the case of the loss of off-site power. This study establishes the basis of an enhanced ... Keywords: emergency diesel generator, maintenance policy, probabilistic safety assessment

Georges Abdul-Nour; Michel Demers; Raynald Vaillancourt

2002-06-01T23:59:59.000Z

120

Molten salt safety study. Final report  

DOE Green Energy (OSTI)

The considerations concerning safety in using molten salt (40% potassium nitrate, 60% sodium nitrate) in a solar central receiver plant are addressed. The considerations are of a general nature and do not cover any details of equipment or plant operation. The study includes salt chemical reaction, experiments with molten salt, dry storage and handling constraints, and includes data from the National Fire Protection Association. The contents of this report were evaluated by two utility companies and they concluded that no major safety problems exist in using a molten salt solar system.

Not Available

1980-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "include plant safety" 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

Review of the Department of Energy Office of Environmental Management Assessment of the Portsmouth/Paducah Project Office Oversight of the Portsmouth Gaseous Diffusion Plant Criticality Safety Program, May 2012  

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

Department of Energy Department of Energy Office of Environmental Management Assessment of the Portsmouth/Paducah Project Office Oversight of the Portsmouth Gaseous Diffusion Plant Criticality Safety Program May 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2

122

Independent Activity Report, Hanford Plutonium Finishing Plant - May 2012 |  

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

Hanford Plutonium Finishing Plant - Hanford Plutonium Finishing Plant - May 2012 Independent Activity Report, Hanford Plutonium Finishing Plant - May 2012 May 2012 Criticality Safety Information Meeting for the Hanford Plutonium Finishing Plant [HIAR-RL-2012-05-14] The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-Destructive Assay (NDA) in support of criticality safety evaluations.

123

Fast reactor safety program. Progress report, January-March 1980  

Science Conference Proceedings (OSTI)

The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development.

Not Available

1980-05-01T23:59:59.000Z

124

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

Science Conference Proceedings (OSTI)

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

Brown, Tulanda

2003-06-01T23:59:59.000Z

125

Criticality Safety  

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

Left Tab EVENTS Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical...

126

Tiger Team assessment of the Pinellas Plant  

Science Conference Proceedings (OSTI)

This Document contains findings identified during the Tiger Team Compliance Assessment of the Department of Energy's (DOE's) Pinellas Plant, Pinellas County, Florida. The assessment wa directed by the Department's Office of Environment, Safety, and Health (ES H) from January 15 to February 2, 1990. The Pinellas Tiger Team Compliance Assessment is comprehensive in scope. It covers the Environment Safety and Health, and Management areas and determines the plant's compliance with applicable Federal (including DOE), State, and local regulations and requirements.

Not Available

1990-05-01T23:59:59.000Z

127

Plant Support Engineering: Guideline on Nuclear Safety-Related Coatings, Revision 2 (Formerly TR-109937 and 1003102)  

Science Conference Proceedings (OSTI)

This report provides a programmatic overview of the elements that should be considered in establishing a utility-unique coatings program consistent with plant-specific licensing and regulatory requirements.

2009-12-23T23:59:59.000Z

128

Good housekeeping: Safety and order in the scientific laboratory  

SciTech Connect

Laboratory safety might not seem, at first, to be very profoundly related to scientific knowledge. Of course safety is a relatively trivial issue in many scientific settings, especially in comparison to the kind of safety concerns found, say, at a construction site or a chemical plant. However, as scientific work has come to involve more exotic chemicals, biological organisms, and forms of radiation, and generally become more industrial in character, safety has become more of a concern. This has occurred alongside a general expansion of government regulation of workplace safety during the 20thc entury, and a recent trend toward extending work lace safety efforts to new kinds of work, including administrative and professional tasks. As a result of these trends, scientists find that they are increasingly being held responsible for following safety regulations in their re{approx}earc

Sims, B. H. (Benjamin H.)

2002-01-01T23:59:59.000Z

129

Solar Pilot Plant project review No. 9, May 4--5, 1977. CDRL item 10  

DOE Green Energy (OSTI)

Drawings and illustrations for the project review are presented. These are included for the 10 MW(e) solar pilot plant, the collector subsystem, the receiver subsystem, the electrical power generation system and balance of plant, plant controls and transient analysis, availability and safety, pilot and commercial plant designs, and summary and recommendations. (MHR)

None

1977-01-01T23:59:59.000Z

130

Safety Overview Committee (SOC)  

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

Safety Overview Committee (SOC) Charter Safety Overview Committee (SOC) Charter 1. Purpose The Safety Overview Committee establishes safety policies and ad hoc safety committees. 2. Membership Membership will include the following individuals: APS Director APS Division Directors PSC ESH/QA Coordinator - Chair 3. Method The Committee will: Establish safety policies for the management of business within the APS. Create short-term committees, as appropriate, to address safety problems not covered by the existing committee structure. The committee chairperson meets with relevant safety representatives to discuss safety questions. 4. Frequency of Meetings Safety topics and policies normally are discussed and resolved during meetings of the Operations Directorate or the PSC ALD Division Directors. Otherwise, any committee member may request that a meeting be held of the

131

Audit of Construction of an Environmental, Safety, and Health Analytical Laboratory at the Pantex Plant, WR-B-96-02  

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

ENERGY ENERGY OFFICE OF INSPECTOR GENERAL AUDIT OF CONSTRUCTION OF AN ENVIRONMENTAL, SAFETY, AND HEALTH ANALYTICAL LABORATORY AT THE PANTEX PLANT The Office of Inspector General wants to make the distribution of its reports as customer friendly and cost effective as possible. Therefore, this report will be available electronically through the Internet five to seven days after publication at the following alternative addresses: Department of Energy Headquarters Gopher gopher.hr.doe.gov Department of Energy Headquarters Anonymous FTP vml.hqadmin.doe.gov U.S. Department of Energy Human Resources and Administration Home Page http://www.hr.doe.gov/refshelf.html Your comments would be appreciated and can be provided on the Customer Response Form attached to the report.

132

Thermal reactor safety  

SciTech Connect

Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

1980-06-01T23:59:59.000Z

133

Training and qualification program for nuclear criticality safety technical staff. Revision 1  

SciTech Connect

A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification.

Taylor, R.G.; Worley, C.A.

1997-03-05T23:59:59.000Z

134

Safety Resources  

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

Resources Print LBNLPub-3000: Health and Safety Manual Berkeley Lab safety guide, policies and procedures. Environment, Health, and Safety (EH&S) Staff Contact information for the...

135

Nuclear Safety  

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

Nuclear Safety information site that provides assistance and resources to field elements in implementation of requirements and resolving nuclear safety, facility safety, and quality assurance issues.

136

Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Observation of Waste Treatment and Immobilization Plant LAW Melter and Melter Off-gas Process System Hazards Analysis _Oct 21-31  

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

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-10-21 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Observation of Waste Treatment and Immobilization Plant Low Activity Waste Melter and Melter Off-gas Process System Hazards Analysis Activities Dates of Activity : 10/21/13 - 10/31/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS), Office of Safety and Emergency Management Evaluations (Independent Oversight) reviewed the Insight software hazard evaluation (HE) tables for hazard analysis (HA) generated to date for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter and Off-gas systems, observed a

137

Proceedings: Decommissioning, Decontamination, ALARA, and Worker Safety Workshop  

Science Conference Proceedings (OSTI)

This workshop on decontamination, ALARA, and worker safety was the sixth in a series initiated by EPRI to aid utility personnel in assessing the technologies for decommissioning nuclear power plants. The workshop focused on specific aspects of decommissioning related to the management of worker radiation exposure and safety. The information presented will help individual utilities assess benefits of programs in these areas for their projects, including their potential to reduce decommissioning costs.

None

2000-09-01T23:59:59.000Z

138

Proceedings: Decommissioning, Decontamination, ALARA, and Worker Safety Workshop  

Science Conference Proceedings (OSTI)

This workshop on decontamination, ALARA, and worker safety was the sixth in a series initiated by EPRI to aid utility personnel in assessing the technologies for decommissioning nuclear power plants. The workshop focused on specific aspects of decommissioning related to the management of worker radiation exposure and safety. The information presented will help individual utilities assess benefits of programs in these areas for their projects, including their potential to reduce decommissioning costs.

2000-09-07T23:59:59.000Z

139

Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead for the Office of River Protection Waste Treatment Plant and Tank Farms, February 2013  

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

HIAR-HANFORD-2013-02-25 HIAR-HANFORD-2013-02-25 Site: Hanford - Office of River Production Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead Dates of Activity : 02/25/13 - 03/07/13 and 03/18-28/13 Report Preparer: Robert E. Farrell Activity Description/Purpose: The Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations (HS-45) assigned a new Site Lead to provide continuous oversight of activities at the Office of River Protection (ORP) Waste Treatment Plant (WTP) and tank farms. To gain familiarity with the site programs and personnel, the new Site Lead made

140

Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead for the Office of River Protection Waste Treatment Plant and Tank Farms, February 2013  

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

HIAR-HANFORD-2013-02-25 HIAR-HANFORD-2013-02-25 Site: Hanford - Office of River Production Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead Dates of Activity : 02/25/13 - 03/07/13 and 03/18-28/13 Report Preparer: Robert E. Farrell Activity Description/Purpose: The Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations (HS-45) assigned a new Site Lead to provide continuous oversight of activities at the Office of River Protection (ORP) Waste Treatment Plant (WTP) and tank farms. To gain familiarity with the site programs and personnel, the new Site Lead made

Note: This page contains sample records for the topic "include plant safety" 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

NanoFab Safety  

Science Conference Proceedings (OSTI)

... a multi-tiered safety training program; vigilant monitoring of all NanoFab laboratories and infrastructure, including daily inspections complemented ...

2013-10-01T23:59:59.000Z

142

Safety Reference Manual - TMS  

Science Conference Proceedings (OSTI)

Jun 26, 2008 ... This 1.400-page manual provides a thorough overview of industry-relevant safety issues, including OSHA requirements and recommendations ...

143

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

amounts released from coal-fired plants without particulatethorium emissions from coal-fired plants may be compared toemissions from coal-fired plants. This comparison, though,

Nero, A.V.

2010-01-01T23:59:59.000Z

144

Fast reactor safety: proceedings of the international topical meeting. Volume 1  

Science Conference Proceedings (OSTI)

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

Not Available

1985-07-01T23:59:59.000Z

145

Cryogenics safety  

DOE Green Energy (OSTI)

The safety hazards associated with handling cryogenic fluids are discussed in detail. These hazards include pressure buildup when a cryogenic fluid is heated and becomes a gas, potential damage to body tissues due to surface contact, toxic risk from breathing air altered by cryogenic fluids, dangers of air solidification, and hazards of combustible cryogens such as liquified oxygen, hydrogen, or natural gas or of combustible mixtures. Safe operating procedures and emergency planning are described. (LCL)

Reider, R.

1977-01-01T23:59:59.000Z

146

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

U. S. Conunercial Nuclear Power Plants", Report WASH-1400 (for Light-Water Cooled Nuclear Power Plants to Assess PlantStandards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

147

EA-0970: Environmental Safety and Health Analytical Laboratory...  

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

70: Environmental Safety and Health Analytical Laboratory Project No. 94-AA-01 Pantex Plant, Amarillo, Texas EA-0970: Environmental Safety and Health Analytical Laboratory Project...

148

Transportation Safety Excellence in Operations Through Improved Transportation Safety Document  

Science Conference Proceedings (OSTI)

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

Dr. Michael A. Lehto; MAL

2007-05-01T23:59:59.000Z

149

Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 15  

Science Conference Proceedings (OSTI)

This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), and Supplement No. 14 (December 1994) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER.

Tam, P.S.

1995-06-01T23:59:59.000Z

150

Management of National Nuclear Power Programs for assured safety  

SciTech Connect

Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

Connolly, T.J. (ed.)

1985-01-01T23:59:59.000Z

151

Safety Notices  

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

Safety Notices Safety Notices Fatigue August 2011 Sleep deprivation and the resulting fatigue can adversely affect manual dexteri- ty, reaction time, alertness, and judgment, resulting in people putting themselves and their co-workers at risk. Liquid-Gas Cylinder Handtruck Awareness May 2011 Failure of a spring assembly can result in a loss of control, allowing the Dewar to become separated from the hand truck, leading to a very dangerous situation. Safe Transport of Hazardous Materials February 2011 APS users are reminded that hazardous materials, including samples, cannot be packed in personal luggage and brought on public transport. Electrical Incidents September 2010 Two minor electrical incidents in the past months at the APS resulted in a minor shock from inadequately grounded equipment, and a damaged stainless

152

Evolution of Safety Basis Documentation for the Fernald Site  

SciTech Connect

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

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

2004-03-01T23:59:59.000Z

153

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP  

SciTech Connect

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

Kessler, S

2009-04-21T23:59:59.000Z

154

Subsurface safety valves: safety asset or safety liability  

SciTech Connect

This paper summarizes the methods used to compare the risk of a blowout for a well completed with a subsurface safety valve (SSSV) vs. a completion without an SSSV. These methods, which could be applied to any field, include a combination of SSSV reliability and conventional risk analyses. The Kuparuk River Unit Working Interest Owners recently formed a group to examine the risks associated with installing and maintaining SSSV's in the Kuparuk field. The group was charged with answering the question: ''Assuming Kuparuk field operating conditions, are SSSV's a safety asset, or do numerous operating and maintenance procedures make them a safety liability.'' The results indicate that for the Kuparuk River Unit, an SSSV becomes a safety liability when the mean time between SSSV failures is less than one year. Since current SSSV mean time to failure (MTTF) at Kuparuk is approximately 1000 days, they are considered a safety asset.

Busch, J.M.; Llewelyn, D.C.G.; Policky, B.J.

1983-10-01T23:59:59.000Z

155

Lesson 7 - Waste from Nuclear Power Plants | Department of Energy  

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

7 - Waste from Nuclear Power Plants 7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing Decommissioning Lesson 7 - Waste.pptx More Documents & Publications National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

156

Safety and Technical Services  

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

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

157

Safety Management System Policy  

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

POLICY POLICY Washington, D.C. Approved: 4-25-11 SUBJECT: INTEGRATED SAFETY MANAGEMENT POLICY PURPOSE AND SCOPE To establish the Department of Energy's (DOE) expectation for safety, 1 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. This Policy cancels and supersedes DOE Policy (P) 411.1, Safety Management Functions, Responsibilities, and Authorities Policy, dated 1-28-97; DOE P 441.1, DOE Radiological Health and Safety Policy, dated 4-26-96; DOE P 450.2A, Identifying, Implementing and Complying with Environment, Safety and Health Requirements, dated 5-15-96; DOE P 450.4, Safety Management

158

Pipeline Safety  

Science Conference Proceedings (OSTI)

Pipeline Safety. Summary: Our goal is to provide standard test methods and critical data to the pipeline industry to improve safety and reliability. ...

2012-11-13T23:59:59.000Z

159

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

160

Lawrence Livermore National Laborotory Safety Basis Assessment...  

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

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

Note: This page contains sample records for the topic "include plant safety" 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

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

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

Security, Emergency Planning & Safety Records Security, Emergency Planning & Safety Records Protection program records include the various files created by the Department to...

162

WIPP Receives Top Mine Safety Award  

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

September 18, 2013 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) received top safety honors from the New Mexico Bureau of Mine Safety (BMS) and the New...

163

Investigation of the radiological safety concerns and medical history of the late Joseph T. Harding, former employee of the Paducah Gaseous Diffusion Plant  

E-Print Network (OSTI)

An ex-employee's claims that inadequate enforcement of radiation safety regulations allowed excess radiation exposure thereby causing his deteriorating health was not substantiated by a thorough investigation.

Vallario, E J

1981-01-01T23:59:59.000Z

164

Electrical safety in industrial plants  

Science Conference Proceedings (OSTI)

Most electrical engineers and electricians are aware that the principal danger from electricity is that of electrocution, but few really understand just how minute a quantity of electric energy is required for electrocution. Actually, the current drawn ...

Ralph H. Lee

1971-06-01T23:59:59.000Z

165

Plant Support Engineering: Aging Management Program Guidance for Medium- Voltage Cable Systems for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Regulatory and management concern regarding the reliability of medium-voltage cable systems at nuclear plants has been increasing for 5–10 years. The staff of the U.S. Nuclear Regulatory Commission (NRC) are concerned that wetted (up to and including submergence) medium-voltage cable circuits may be degrading to the point at which multiple cable circuits may fail when called on to perform functions affecting safety. Utility managers are concerned that cables may fail, causing adverse safety consequences ...

2010-06-02T23:59:59.000Z

166

Independent Oversight Inspection, Portsmouth Gaseous Diffusion Plant -  

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

Portsmouth Gaseous Diffusion Portsmouth Gaseous Diffusion Plant - November 2006 Independent Oversight Inspection, Portsmouth Gaseous Diffusion Plant - November 2006 November 2006 Inspection of Emergency Management at the Portsmouth Gaseous Diffusion Plant The Secretary of Energy's Office of Independent Oversight, within the Office of Security and Safety Performance Assurance, conducted an inspection of the emergency management program at the Portsmouth Gaseous Diffusion Plant (PORTS) in August and September 2006. The coordination of emergency plans and procedures among USEC and DOE contractor organizations has successfully integrated the emergency management programs into a single cohesive program for the PORTS site. Other strengths include accurate hazards surveys that identify applicable

167

Safety, Security  

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

Safety, Security Safety, Security Safety, Security LANL's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 We do not compromise safety for personal, programmatic, or operational reasons. Safety: we integrate safety, security, and environmental concerns into every step of our work Our commitments We conduct our work safely and responsibly to achieve our mission. We ensure a safe and healthful environment for workers, contractors, visitors, and other on-site personnel. We protect the health, safety, and welfare of the general public. We do not compromise safety for personal, programmatic, or

168

WIPP Receives Top Safety Award  

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

WIPP Receives Top Safety Award CARLSBAD, N.M., November 10, 2011 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) received top accolades from New...

169

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Plants", Report WASH-1400 (NUREG-75/0l4), October 1975. u ICooled Reactors (GESMO), NUREG -0002,ES, August 1976. W. B.Plants", report WASH-1400 (NUREG-75/014), October 1975. See

Nero, A.V.

2010-01-01T23:59:59.000Z

170

Electric power monthly, September 1990. [Glossary included  

SciTech Connect

The purpose of this report is to provide energy decision makers with accurate and timely information that may be used in forming various perspectives on electric issues. The power plants considered include coal, petroleum, natural gas, hydroelectric, and nuclear power plants. Data are presented for power generation, fuel consumption, fuel receipts and cost, sales of electricity, and unusual occurrences at power plants. Data are compared at the national, Census division, and state levels. 4 figs., 52 tabs. (CK)

1990-12-17T23:59:59.000Z

171

Westar's Lawrence Energy Center wins for not blinking on safety  

SciTech Connect

It took Westar Energy eight years to upgrade the Lawrence Energy Center to burn Powder River Basin coal. Its zero lost-time accident record during the eight-year, million-man-hour project is a testament to Westar's commitment to workplace safety. The plant won the Powder River Basin Coal Users' Group plant of the year award for 2006. The article describes all the changes implemented at the plant, including replacing and upgrading controls for the belt conveyor, replacing the coal crushers, minimising dust and modifying coal bunkers, to cope with the increased volatility of Powder River Basin coal. Modifications were made to minimise slagging and fouling of boilers. 10 photos.

Peltier, R.

2007-07-15T23:59:59.000Z

172

ENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION  

E-Print Network (OSTI)

SERVICES ENVIRONMENTAL HEALTH & SAFETY Discovery 2 Building, Room 265 8888 University Drive BurnabyENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION SIMON FRASER UNIVERSITY SAFETY & RISK SIGNAGE 26740 INCIDENT INVESTIGATION Supervisors, Safety Committees, EHS LABORATORY SAFETY 27265

173

2. Electrical safety  

Science Conference Proceedings (OSTI)

Correct use of medical equipment within the clinical environment is of prime importance. This includes awareness of the safety issues regarding equipment, particular when it is an electrically powered device. Incidents can occur in the clinic in which ...

Jacques Jossinet

2010-01-01T23:59:59.000Z

174

Carbon Monoxide Safety Tips  

E-Print Network (OSTI)

Protect yourself and your family from the deadly effects of carbon monoxide--a colorless, odorless poisonous gas. This publication describes the warning signs of carbon monoxide exposure and includes a home safety checklist.

Shaw, Bryan W.; Garcia, Monica L.

1999-07-26T23:59:59.000Z

175

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

in a com- munity. NAS-NRC: National Academy of Sciences -Regulatory Guide (NRC) - Safety Analysis Report - UnitedICRU LET LWR MPBB MPC NCRP NRC PAG PWR RBE RG SAR UNSCEAR

Nero, A.V.

2010-01-01T23:59:59.000Z

176

Safety Bulletins  

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

2009-01: Sulfur Hexafluoride Awareness Safety Bulletin 2008-03: Reporting Work-Related Heart Attacks Safety Bulletin 2008-02: Quality Assurance Concern at Wright Industries, Inc....

177

Embrittlement of Power Plant Steels  

Science Conference Proceedings (OSTI)

Plant operators seek to adopt approaches that can minimize costs, prevent forced outages, and maximize safety and reliability. Rigorous life assessment methodologies have been developed over the years and are commonly employed to determine component integrity and life. Such assessments examine key operational characteristics including: elevated temperature exposure, cycling operation, loading, environmental exposure, etc., to determine remaining life. Many of these characteristics can have a ...

2013-12-19T23:59:59.000Z

178

An Overview of the Safety Case for Small Modular Reactors  

SciTech Connect

Several small modular reactor (SMR) designs emerged in the late 1970s and early 1980s in response to lessons learned from the many technical and operational challenges of the large Generation II light-water reactors. After the accident at the Three Mile Island plant in 1979, an ensuing reactor redesign effort spawned the term inherently safe designs, which later evolved into passively safe terminology. Several new designs were engineered to be deliberately small in order to fully exploit the benefits of passive safety. Today, new SMR designs are emerging with a similar philosophy of offering highly robust and resilient designs with increased safety margins. Additionally, because these contemporary designs are being developed subsequent to the September 11, 2001, terrorist attack, they incorporate a number of intrinsic design features to further strengthen their safety and security. Several SMR designs are being developed in the United States spanning the full spectrum of reactor technologies, including water-, gas-, and liquid-metal-cooled ones. Despite a number of design differences, most of these designs share a common set of design principles to enhance plant safety and robustness, such as eliminating plant design vulnerabilities where possible, reducing accident probabilities, and mitigating accident consequences. An important consequence of the added resilience provided by these design approaches is that the individual reactor units and the entire plant should be able to survive a broader range of extreme conditions. This will enable them to not only ensure the safety of the general public but also help protect the investment of the owner and continued availability of the power-generating asset. Examples of typical SMR design features and their implications for improved plant safety are given for specific SMR designs being developed in the United States.

Ingersoll, Daniel T [ORNL

2011-01-01T23:59:59.000Z

179

Safety Communications  

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

Communications Communications New Staff & Guests Safety Topics ISM Plan Safety Communications Questions about safety and environmental compliance should first be directed to your supervisor or work lead. The Life Sciences Division Safety Coordinator Scott Taylor at setaylor@lbl.gov , 486-6133 (office), or (925) 899-4355 (cell); and Facilities Manager Peter Marietta at PMarietta@lbl.gov, 486-6031 (office), or 967-6596 (cell), are also sources of information. Your work group has a representative to the Division Environment, Health, & Safety Committee. This representative can provide safety guidance and offer a conduit for you to pass on your concerns or ideas. A list of current representatives is provided below. Additional safety information can be obtained on-line from the Berkeley Lab

180

Project: Safety of Building Occupants  

Science Conference Proceedings (OSTI)

... focuses on multiple aspects of life safety, including fundamentals of human ... to evacuate a building by stairs (using SFPE Handbook movement on ...

2013-01-02T23:59:59.000Z

Note: This page contains sample records for the topic "include plant safety" 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

Recommended practice for fire protection for electric generating plants and high voltage direct current converter stations. 2005 ed.  

Science Conference Proceedings (OSTI)

The standard outlines fire safety recommendations for gas, oil, coal, and alternative fuel electric generating plants including high voltage direct current converter stations and combustion turbine units greater than 7500 hp used for electric generation. Provisions apply to both new and existing plants. The document provides fire prevention and fire protection recommendations for the: safety of construction and operating personnel; physical integrity of plant components; and continuity of plant operations. The 2005 edition includes revisions and new art that clarify existing provisions. 5 annexes.

NONE

2005-07-01T23:59:59.000Z

182

Safety Analysis: Evaluation of Accident Risks in the Transporation of Hazardous Materials by Truck and Rail at the Savannah River Plant  

Science Conference Proceedings (OSTI)

This report presents an analysis of the consequences and risks of accidents resulting from hazardous material transportation at the Savannah River Plant.

Blanchard, A.

1999-04-15T23:59:59.000Z

183

August 3, 2011, Board letter forwarding public comments concerning Recommendation 2011-1, Safety Culture at the Waste Treatment and Immobilization Plant  

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

S. W S. W i n o h , C h a i n ~ ~ a ~ ~ DEFENSE NUCLEAR FACILITIES Icssie H. Roberson, Vice Chairmall SAFETY BOARD Jofm E. Mansfield Waslhgton, DC 20004-2901 Joseph F. Bader August 3,201 1 The Honorable Steven Chu Secretary of Energy U.S. Department of Energy 1000 Independence Avenue, SW Washington, DC 20585-1000 Dear Secretary Chu: Pursuant to 42 U.S.C. 6 2286d(a), the Defense Nuclear Facilities Safety Board (Board) published Recommendation 201 1-1, Safety Cultlcl-e at the Waste Trentineitt aiid I~nmzobilizatio~i Pinlit, in the Federal Register and invited comments, data, views, or argutnents concerning the Recomtnendation frotn interested persons by July 20, 2011. The enclosed comments concerning Recommendation 201 1-1 have been received by the Board and made available to the public on the Board's internet web site, As required by 42

184

Nuclear Safety (Pennsylvania) | Department of Energy  

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

Nuclear Safety (Pennsylvania) Nuclear Safety (Pennsylvania) Nuclear Safety (Pennsylvania) < Back Eligibility Utility Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Program Info State Pennsylvania Program Type Environmental Regulations Safety and Operational Guidelines Provider Pennsylvania Department of Environmental Protection The Nuclear Safety Division conducts a comprehensive nuclear power plant oversight review program of the nine reactors at the five nuclear power sites in Pennsylvania. It also monitors the activities associated with management and disposal of a low-level radioactive waste disposal facility in Pennsylvania and provides planning and support for Bureau response to incidents involving nuclear power plants and/or radioactive material in

185

Key Issues for the Safety and Licensing of Fusion  

SciTech Connect

Studies of the safety and environmental impacts of fusion, both of future power plants and of ITER, have shown that a good performance can be achieved. Although it is difficult to anticipate the regulatory regime in which future fusion power stations will be licensed, the areas of public and occupational safety and short and long-term environmental impact are likely to remain important. In each of these areas, the outcome of various studies have been reviewed, leading to a list of issues which should be given attention to facilitate eventual licensing of a fusion power plant. Many of these relate to reducing conservatisms and uncertainties in the analyses, but also included are improved understanding of tritium retention and of dust generation, and development of materials to provide long component lifetimes. A full appraisal is also recommended of the viability of recycling of active materials after end of plant life.

Taylor, Neill P. [Culham Science Centre (United Kingdom)

2005-05-15T23:59:59.000Z

186

Five-megawatt geothermal-power pilot-plant project  

DOE Green Energy (OSTI)

This is a report on the Raft River Geothermal-Power Pilot-Plant Project (Geothermal Plant), located near Malta, Idaho; the review took place between July 20 and July 27, 1979. The Geothermal Plant is part of the Department of Energy's (DOE) overall effort to help commercialize the operation of electric power plants using geothermal energy sources. Numerous reasons were found to commend management for its achievements on the project. Some of these are highlighted, including: (a) a well-qualified and professional management team; (b) effective cost control, performance, and project scheduling; and (c) an effective and efficient quality-assurance program. Problem areas delineated, along with recommendations for solution, include: (1) project planning; (2) facility design; (3) facility construction costs; (4) geothermal resource; (5) drilling program; (6) two facility construction safety hazards; and (7) health and safety program. Appendices include comments from the Assistant Secretary for Resource Applications, the Controller, and the Acting Deputy Director, Procurement and Contracts Management.

Not Available

1980-08-29T23:59:59.000Z

187

Safety Advisories  

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

Safety Advisories Safety Advisories 2010 2010-08 Safety Advisory - Software Quality Assurance Firmware Defect in Programmable Logic Controller 2010-07 Safety Advisory - Revised Counterfeit Integrated Circuits Indictment 2010-06 Safety Advisory - Counterfeit Integrated Circuits Indictment 2010-05 Safety Advisory - Contact with Overhead Lines and Ground Step Potential 2010-04 Update - Leaking Acetylene Cylinder Shutoff Valves 2010-03 - Software Quality Assurance Microsoft Excel Software Issue 2010-02 - Leaking Acetylene Cylinder Shutoff Valves 2010-01 Update - Defective Frangible Ammunition 2009 2009-05 Software Quality Assurance - Errors in MACCS2 x/Q Calculations 2009-04 Update - SEELER Exothermic Torch 2009-03 - Defective Frangible Ammunition 2009-02 - Recall of Defense Technology Distraction Devices

188

ORISE: Integrated Safety Management (ISM)  

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

Integrated Safety Management (ISM) Integrated Safety Management (ISM) Oak Ridge Associated Universities (ORAU) is committed to performing work safely as it operates the Oak Ridge Institute for Science and Education (ORISE). ORAU supports the U.S. Department of Energy (DOE) policy of using management systems to integrate safety into work practices at all levels. ORAU defines "safety" as encompassing environment, safety and health, and also includes waste minimization and pollution prevention. All ORAU programs and departments actively pursue continuous improvement, and the addition of Integrated Safety Management (ISM) concepts further strengthens safety as a standard in ORISE's culture. ORAU has accepted the ISM concept by contract under DOE Acquisition Regulations Clause 970.5204-2 and DOE Policy 450.4, Safety Management System Policy.

189

Health effects and related standards for fossil-fuel and geothermal power plants. Volume 6 of health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. [In California  

DOE Green Energy (OSTI)

This report reviews health effects and related standards for fossil-fuel and geothermal power plants, emphasizing impacts which may occur through emissions into the atmosphere, and treating other impacts briefly. Federal regulations as well as California state and local regulations are reviewed. Emissions are characterized by power plant type, including: coal-fired, oil-fired, gas-fired, combined cycle and advanced fossil-fuel plants; and liquid and vapor geothermal systems. Dispersion and transformation of emissions are treated. The state of knowledge of health effects, based on epidemiological, physiological, and biomedical studies, is reviewed.

Case, G.D.; Bertolli, T.A.; Bodington, J.C.; Choy, T.A.; Nero, A.V.

1977-01-01T23:59:59.000Z

190

Bromine Safety  

SciTech Connect

The production and handling in 1999 of about 200 million kilograms of bromine plus substantial derivatives thereof by Great Lakes Chemical Corp. and Albemarle Corporation in their southern Arkansas refineries gave OSHA Occupational Injury/Illness Rates (OIIR) in the range of 0.74 to 1.60 reportable OIIRs per 200,000 man hours. OIIRs for similar industries and a wide selection of other U.S. industries range from 1.6 to 23.9 in the most recent OSHA report. Occupational fatalities for the two companies in 1999 were zero compared to a range in the U.S.of zero for all computer manufacturing to 0.0445 percent for all of agriculture, forestry and fishing in the most recent OSHA report. These results show that bromine and its compounds can be considered as safe chemicals as a result of the bromine safety standards and practices at the two companies. The use of hydrobromic acid as an electrical energy storage medium in reversible PEM fuel cells is discussed. A study in 1979 of 20 megawatt halogen working fluid power plants by Oronzio de Nora Group found such energy to cost 2 to 2.5 times the prevailing base rate at that time. New conditions may reduce this relative cost. The energy storage aspect allows energy delivery at maximum demand times where the energy commands premium rates. The study also found marginal cost and performance advantages for hydrobromic acid over hydrochloric acid working fluid. Separate studies in the late 70s by General Electric also showed marginal performance advantages for hydrobromic acid.

Meyers, B

2001-04-09T23:59:59.000Z

191

DOE - Safety of Radioactive Material Transportation  

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

How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Packagings are used to safely transport radioactive materials across the United States in over 1.6 million shipments per year. [Weiner et. al., 1991, Risk Analysis, Vol. 11, No. 4, p. 663] Most shipments are destined for hospitals and medical facilities. Other destinations include industrial, research and manufacturing plants, nuclear power plants and national defense facilities. The last comprehensive survey showed that less than 1 percent of these shipments involve high-level radioactive material. [Javitz et. al., 1985, SAND84-7174, Tables 4 and 8] The types of materials transported include: Surface Contaminated Object (SCO) Low Specific Activity (LSA) materials, Low-Level Waste (LLW),

192

Safety - Cyclotron  

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

Safety The Nuclear Sciences Division (NSD) is committed to providing a safe workplace for its employees, contractors, and guests and conducting its research and operations in a...

193

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

refabrication. through which nuclear fuel passes. Fusion.with the experience at the Nuclear Fuel Services Plant (seecommitment from the nuclear fuel cycle; see Section 3.2.3. )

Nero, A.V.

2010-01-01T23:59:59.000Z

194

Safety Bulletin  

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

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

195

Integrated Safety Management (ISM) - Safety Culture Resources  

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

Safety Culture Resources Integrated Safety Management (ISM) Safety from the Operator's Perspective: We are All in this Together (2005) - Jim Ellis, President and CEO, Institute of...

196

ORISE: Safety is our top priority  

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

Safety Safety Integrated Safety Management Voluntary Protection Program VPP Star Status Environment Work Smart Standards Oak Ridge Institute for Science Education Safety at ORISE At the Oak Ridge Institute for Science and Education (ORISE) safety is our number one priority. We not only have a tradition of safety at work, but strongly encourage our employees to carry this mindset beyond the workplace and into their homes and communities. Employees are trained in how to work safely and are required to sign a safety pledge that affirms their commitment to safety. The pledge also obligates them to watch out for each another, challenge and report unsafe working conditions, follow all safety policies and procedures, and never take shortcuts at the expense of safety. For ORISE employees, the word "safety" includes the environment, as

197

Preparation of design specifications and design reports for pumps, valves, piping, and piping supports used in safety-related portions of nuclear power plants  

SciTech Connect

Section III of the ASME Boiler and Pressure Vessel Code requires the preparation of Design Specifications and Design Reports as part of the design process leading to construction of a nuclear power plant, in compliance with provisions of Title 10 of the Code of Federal Regulations (10 CFR). Guidelines for preparing this documentation are contained in nonmandatory Appendixes B and C of the ASME Code. This report gives an in-depth review of the ASME Code requirements and guidance, beginning with the first edition of the Code in 1963 through the 1983 edition, Summer 1985 Addenda. Recommendations for substantial revisions to the Code are presented based on the authors experience in conducting design documentation audits of pumps, valves, piping, and piping supports for nuclear power plants undergoing Nuclear Regulatory Commission (NRC) review for Operating Licenses. It is concluded that adequate Design Specifications and Design Reports are absolutely necessary for the normal operating life of a plant and are vital if plant life extension is planned.

Rodabaugh, E.C.; Moore, S.E.

1987-06-01T23:59:59.000Z

198

Safety Bulletins  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

199

Safety Advisories  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

200

Safety Alerts  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

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


201

Safety Bulletin  

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

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

202

Biological Safety  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

203

Normalization of Process Safety Metrics  

E-Print Network (OSTI)

This study is aimed at exploring new process safety metrics for measuring the process safety performance in processing industries. Following a series of catastrophic incidents such as the Bhopal chemical tragedy (1984) and Phillips 66 explosion (1989), process safety became a more important subject than ever. These incidents triggered the development and promulgation of the Process Safety Management (PSM) standard in 1992. While PSM enables management to optimize their process safety programs and organizational risks, there is an emerging need to evaluate the process safety implementation across an organization through measurements. Thus, the process safety metric is applied as a powerful tool that measures safety activities, status, and performance within PSM. In this study, process safety lagging metrics were introduced to describe the contribution of process related parameters in determining the safety performance of an organization. Lagging metrics take process safety incidents as the numerator and divide it by different process-related denominators. Currently a process lagging metric (uses work hours as denominator) introduced by the Center for Chemical Process Safety (CCPS) has been used to evaluate the safety performance in processing industries. However, this lagging metric doesn't include enough process safety information. Therefore, modified denominators are proposed in this study and compared with the existing time-based denominator to validate the effectiveness and applicability of the new metrics. Each proposed metric was validated using available industry data. Statistical unitization method has converted incident rates of different ranges for the convenience of comparison. Trend line analysis was the key indication for determining the appropriateness of new metrics. Results showed that some proposed process-related metrics have the potential as alternatives, along with the time-based metric, to evaluate process safety performance within organizations.

Wang, Mengtian

2012-08-01T23:59:59.000Z

204

DOE P 450.4A, Integrated Safety Management Policy  

Directives, Delegations, and Requirements

The policy establishes DOE's expectation for safety, including integrated safety management that will enable the Departmentâ??s mission goals to be accomplished ...

2011-04-25T23:59:59.000Z

205

Audit of Construction of an Environmental, Safety, and Health...  

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

Construction of an Environmental, Safety, and Health Analytical Laboratory at the Pantex Plant, WR-B-96-02 Audit of Construction of an Environmental, Safety, and Health Analytical...

206

Independent Oversight Inspection, Waste Isolation Pilot Plant, Summary Report- August 2002  

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

Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant

207

HSS Safety Shares  

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

Safety Shares Safety Shares HSS Safety Shares Home Health, Safety and Security Home HSS Safety Shares 2013 Safety Shares National Weather Service - Lightning Safety General Lightning Safety 7 Important Parts of a Cleaning Label Kitchen Knife Safety Lawn and Garden Tool Hazards Rabies Hearing Loss Winter Driving Tips 2012 Safety Shares Holiday Decoration Safety Tips Countdown to Thanksgiving Holiday Fall Season Safety Tips Slips, Trips and Fall Safety Back To School Safety Tips for Motorists Grills Safety and Cleaning Tips Glass Cookware Safety Water Heater Safety FAQs Root Out Lawn and Garden Tool Hazards First Aid for the Workplace Preventing Colon Cancer Yard Work Safety Yard Work Safety - Part 1 Yard Work Safety - Part 2 High Sodium Risks Heart Risk Stair Safety New Ways To Spot Dangerous Tires

208

Nuclear safety as applied to space power reactor systems  

SciTech Connect

To develop a strategy for incorporating and demonstrating safety, it is necessary to enumerate the unique aspects of space power reactor systems from a safety standpoint. These features must be differentiated from terrestrial nuclear power plants so that our experience can be applied properly. Some ideas can then be developed on how safe designs can be achieved so that they are safe and perceived to be safe by the public. These ideas include operating only after achieving a stable orbit, developing an inherently safe design, ''designing'' in safety from the start and managing the system development (design) so that it is perceived safe. These and other ideas are explored further in this paper.

Cummings, G.E.

1987-01-01T23:59:59.000Z

209

Public Safety Communications  

Science Conference Proceedings (OSTI)

Public Safety Communication. Summary: ... the development of quantitative requirements for public safety communications. ...

2011-12-12T23:59:59.000Z

210

Life Cycle Management Planning at V.C. Summer Nuclear Plant: Main Condenser, Radiation Monitoring System, and Nuclear Safety-Related HVAC Chilled Water  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes very important to keep the plant economically viable throughout its remaining licensed operating term (either a 40-year or 60-year term). This report provides the industry with lessons learned from applying the EPRI LCM planning process to three SSCs at V.C. Summer Generating Station.

2001-12-21T23:59:59.000Z

211

Radiation Safety  

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

Brotherhood of Locomotive Brotherhood of Locomotive Engineers & Trainmen Scott Palmer BLET Radiation Safety Officer New Hire Training New Hire study topics * GCOR * ABTH * SSI * Employee Safety * HazMat * Railroad terminology * OJT * 15-week class * Final test Hazardous Materials * Initial new-hire training * Required by OSHA * No specified class length * Open book test * Triennial module Locomotive Engineer Training A little bit older...a little bit wiser... * Typically 2-4 years' seniority * Pass-or-get-fired promotion * Intensive program * Perpetually tested to a higher standard * 20 Weeks of training * 15 of that is OJT * General Code of Operating Rules * Air Brake & Train Handling * System Special Instructions * Safety Instructions * Federal Regulations * Locomotive Simulators * Test Ride * Pass test with 90% Engineer Recertification

212

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

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

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

213

Geothermal: Sponsored by OSTI -- Internal Technical Report, Safety...  

Office of Scientific and Technical Information (OSTI)

Internal Technical Report, Safety Analysis Report 5 MW(e) Raft River Research and Development Plant Geothermal Technologies Legacy Collection HelpFAQ | Site Map | Contact Us |...

214

Criticality Safety Information Meeting for the Hanford Plutonium...  

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

Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus...

215

Boulder Safety Reps Receive 2010 NIST Safety Award  

Science Conference Proceedings (OSTI)

NIST Safety Award. Award Winner: Boulder Division Safety Representatives. Description: The NIST Safety Award, first presented ...

2011-10-25T23:59:59.000Z

216

Independent Oversight Review, Pantex Plant, December 2013 | Department...  

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

Pantex Plant, December 2013 Independent Oversight Review, Pantex Plant, December 2013 December 2013 Targeted Review of the Safety Significant Blast Door and Personnel Door...

217

Strategic Safety Goals  

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

Fatalities Fatalities Radiological exposures > 2 rem Radiological releases above regulatory limits Chemical/hazardous material releases above regulatory limits Infrastructure Losses > $5 million Total 2 4 1 3 1 1 (Vehicle) 1 3 1 0 0 1 2007 2008 2009 2010 2011 2012 (Yr to Date) Total 1 1 0 1 1* 0 Total 1 0 0 0 0 0 Total 2 3 2 0 2 0 Total 0 0 0 0 1 0 Safety Performance for 2 nd Quarter 2012 Strategic Safety Goals: Events DOE Strives to Avoid 1 * In 2012, to date, there has been a single fatality involving a motor vehicle accident outside the boundary of the Waste Isolation Pilot Plant (WIPP) when a dump trailer and a General Services Administration (GSA) pickup driven by a WIPP employee collided. * Two occurrences have been added to the 2011 calendar year total for chemical and hazardous material releases above regulatory

218

Methanol production from eucalyptus wood chips. Attachment IV. Health and safety aspects of the eucalypt biomass to methanol energy system  

DOE Green Energy (OSTI)

The basic eucalyptus-to-methanol energy process is described and possible health and safety risks are identified at all steps of the process. The toxicology and treatment for exposure to these substances are described and mitigating measures are proposed. The health and safety impacts and risks of the wood gasification/methanol synthesis system are compared to those of the coal liquefaction and conversion system. The scope of this report includes the health and safety risks of workers (1) in the laboratory and greenhouse, where eucalyptus seedlings are developed, (2) at the biomass plantation, where these seedlings are planted and mature trees harvested, (3) transporting these logs and chips to the refinery, (4) in the hammermill, where the logs and chips will be reduced to small particles, (5) in the methanol synthesis plant, where the wood particles will be converted to methanol, and (6) transporting and dispensing the methanol. Finally, the health and safety risks of consumers using methanol is discussed.

Fishkind, H.H.

1982-06-01T23:59:59.000Z

219

Independent Oversight Review, Portsmouth Gaseous Diffusion Plant- April 2013  

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

Review of the Integrated Safety Management System Phase I Verification Review at the Portsmouth Gaseous Diffusion Plant

220

Independent Activity Report, Hanford Plutonium Finishing Plant- May 2012  

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

Criticality Safety Information Meeting for the Hanford Plutonium Finishing Plant [HIAR-RL-2012-05-14

Note: This page contains sample records for the topic "include plant safety" 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

SSRL Safety Office Memo  

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

Safety Office SSO 01/24/06 Safety Office SSO 01/24/06 Memo to SSRL staff concerning operation of Circuit Breakers and Disconnect Switches Recently SLAC has adopted new regulations (NFPA70E) which outline the "Standard for Electrical Safety in the Workplace". Specifically it requires that the Arc Flash Hazard be categorized and PPE stated for all circuit breakers and disconnect switches. This memo identifies requirement for operating circuit breakers or disconnect switches at SSRL. SSRL staff members shall be authorized to operate CB's and disconnect switches only if they meet the following requirement The staff member: 1. Has the task identified and authorized in their routine JHAM, which includes: a. Reading and understand the SSRL Breaker and Disconnect Switch Operation

222

(Great Plains Coal Gasification project): Quarterly environmental, safety, medical, and industrial hygiene report, fourth quarter 1986  

SciTech Connect

Contents of this quarterly report include: (1) environmental monitoring program; (2) supplemental environmental program; (3) quality assurance/quality control activities; (4) schedule of activities for next reporting period; (5) safety; (6) medical services; and (7) industrial hygiene. The environmental monitoring program covers: permitting activities; ambient monitoring; plant discharge monitoring; pollution control unit emissions; surface mining and reclamation; environmental incident summary; and regulatory environmental inspections. Supplemental environmental program includes: performance survey; toxicity screening study; data base management system; epidemiology; and contingency program.

Not Available

1987-01-01T23:59:59.000Z

223

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESSPlanning for Nuclear Power Plants Determination of Accidentnuclear power plants . . . . . . . . . • . . . . .2.2.4.3.

Yen, W.W.S.

2010-01-01T23:59:59.000Z

224

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

~ ties Surrounding Nuclear Power Plants. LBlr5921, Lawrencein U. S. Commercial Nuclear Power Plants. WASH-1400. Octoberand Content of for Nuclear Power Plants. Regulatory Guide

Yen, W.W.S.

2010-01-01T23:59:59.000Z

225

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Summary of Nuclear Power Plant Operating Experience forResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, A.V.

2010-01-01T23:59:59.000Z

226

Siting of nuclear facilities. Selections from Nuclear Safety  

SciTech Connect

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Buchanan, J.R.

1976-07-01T23:59:59.000Z

227

Safety evaluation for packaging CPC metal boxes  

Science Conference Proceedings (OSTI)

This Safety Evaluation for Packaging (SEP) provides authorization for the use of Container Products Corporation (CPC) metal boxes, as described in this document, for the interarea shipment of radioactive contaminated equipment and debris for storage in the Central Waste Complex (CWC) or T Plant located in the 200 West Area. Authorization is granted until November 30, 1995. The CPC boxes included in this SEP were originally procured as US Department of Transportation (DOT) Specification 7A Type A boxes. A review of the documentation provided by the manufacturer revealed the documentation did not adequately demonstrate compliance to the 4 ft drop test requirement of 49 CFR 173.465(c). Preparation of a SEP is necessary to document the equivalent safety of the onsite shipment in lieu of meeting DOT packaging requirements until adequate documentation is received. The equivalent safety of the shipment is based on the fact that the radioactive contents consist of contaminated equipment and debris which are not dispersible. Each piece is wrapped in two layers of no less than 4 mil plastic prior to being placed in the box which has an additional 10 mil liner. Pointed objects and sharp edges are padded to prevent puncture of the plastic liner and wrapping.

Romano, T.

1995-05-15T23:59:59.000Z

228

Gas Pipeline Safety (Indiana)  

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

229

Electrical Safety Committee Charter  

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

safety and electrical safety awareness within the APS. The committee shall implement policies and practices adopted by the ANL Electrical Safety Committee and shall assist the ANL...

230

Safety implications from 20 years of operating experience at EBR-II  

Science Conference Proceedings (OSTI)

EBR-II recently passed a major milestone in its operating history, 20 years of operation on August 13, 1984. The plant has gone through three major program phases during this time and is now entering a fourth. Those are: (1) demonstration of the feasibility of a complete LMFBR power plant, including on-site reprocessing of metal fuel, (2) irradiation testing of fuels and materials to support core and fuel design for CRBR and FFTF, (3) operational-safety testing to establish and demonstrate the inherent safety of LMFBRs and now, (4) the integration of this technology into demonstration of the integral fast reactor (IFR) concept. As EBR-II has progressed through these phases, much has been learned that is relevant to fast-reactor safety.

Sackett, J.I.; Buschman, H.W.

1985-01-01T23:59:59.000Z

231

Pinellas Plant Annual Site Environmental Report for calendar year 1994  

Science Conference Proceedings (OSTI)

This report presents a comprehensive summary of the results of the Environmental Monitoring, Waste Management, and Environmental Restoration Programs at the Pinellas Plant, in Pinellas County, Florida for 1994. This report also includes the plant`s performance in the areas of compliance with applicable regulatory requirements and standards and identifies major Environmental, Safety and Health Program initiatives and accomplishments for 1994. As a result of the end of Department of Energy Defense Programs mission production on September 30, 1994, considerable changes at the Pinellas Plant occurred. These changes, which included transitioning the plant toward alternate use in support of economic development and safe shutdown, both increased and heightened Environmental, Safety and Health responsibilities. In December 1994, the Department of Energy announced it had reached an agreement to sell the Pinellas Plant to the Pinellas County Industry Council in March 1995. The plant is being leased back by the Department of Energy through September 1997 to complete safe shutdown, reconfiguration, transfer of equipment to other Department of Energy production facilities, and transition to commercial ventures. Permit modifications and transfers will be completed during 1995 to reflect the new ownership by the Pinellas County Industry Council and to include new tenants as needed.

NONE

1995-06-01T23:59:59.000Z

232

Reactor operation safety information document  

Science Conference Proceedings (OSTI)

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

Not Available

1990-01-01T23:59:59.000Z

233

Manpower analysis in transportation safety. Final report  

DOE Green Energy (OSTI)

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

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

1977-05-01T23:59:59.000Z

234

THE IMPACT OF THE GLOBAL NUCLEAR SAFETY REGIME IN BRAZIL  

SciTech Connect

A turning point of the world nuclear industry with respect to safety occurred due to the accident at Chernobyl, in 1986. A side from the tragic personal losses and the enormous financial damage, the Chernobyl accident has literally demonstrated that ''a nuclear accident anywhere is an accident everywhere''. The impact was felt immediately by the nuclear industry, with plant cancellations (e.g. Austria), elimination of national programs (e.g. Italy) and general construction delays. However, the reaction of the nuclear industry was equally immediate, which led to the proposal and establishment of a Global Nuclear Safety Regime. This regime is composed of biding international safety conventions, globally accepted safety standard, and a voluntary peer review system. In a previous work, the author has presented in detail the components of this Regime, and briefly discussed its impact in the Brazilian nuclear power organizations, including the Regulatory Body. This work, on the opposite, briefly reviews the Global Nuclear Safety Regime, and concentrates in detail in the discussion of its impact in Brazil, showing how it has produced some changes, and where the peer pressure regime has failed to produce real results.

Almeida, C.

2004-10-06T23:59:59.000Z

235

Electrical Safety  

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

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE HANDBOOK ELECTRICAL SAFETY DOE-HDBK-1092-2013 July 2013 Superseding DOE-HDBK-1092-2004 December 2004 U.S. Department of Energy AREA SAFT Washington, D.C.20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1092-2013 Available on the Department of Energy Technical Standards Program Web site at http://www.hss.doe.gov/nuclearsafety/techstds/ ii DOE-HDBK-1092-2013 FOREWORD 1. This Department of Energy (DOE) Handbook is approved for use by the Office of Health, Safety and Security and is available to all DOE components and their contractors. 2. Specific comments (recommendations, additions, deletions, and any pertinent data) to enhance this document should be sent to: Patrick Tran

236

Stair Safety  

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

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

237

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

238

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. The 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, L.W.

1991-04-08T23:59:59.000Z

239

Explosives Safety  

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

212-2012 212-2012 June 2012 DOE STANDARD EXPLOSIVES SAFETY U.S. Department of Energy AREA SAFT Washington, DC 20585 MEASUREMENT SENSITIVE DOE-STD-1212-2012 i TABLE OF CONTENTS CHAPTER I. PURPOSE, SCOPE and APPLICABILITY, EXEMPTIONS, WAIVERS, ABBREVIATIONS, ACRONYMS, AND DEFINITIONS .......... 1 1.0. PURPOSE ............................................................................................................. 1 1.1. Scope and Applicability.............................................................................. 1 2.0. STANDARD ADMINISTRATION AND MANAGEMENT ...................................... 3 3.0. EXEMPTIONS ....................................................................................................... 4

240

Safety valve  

SciTech Connect

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

Note: This page contains sample records for the topic "include plant safety" 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

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

population growth surrounding a nuclear power plant once thegrowth by requiring that certification of nuclear power plant

Yen, W.W.S.

2010-01-01T23:59:59.000Z

242

Environment/Health/Safety (EHS): Safety Minute  

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

(PDF, PPT) Badge Return (LBNL) (PDF, PPT) Battery Management (PDF, PPT) Bicycle Safety (PDF, PPT) Construction-Related Mercury Spills (PDF, PPT) Construction Vehicle Safety...

243

Office of Health & Safety  

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

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

244

A literature review of safety culture.  

SciTech Connect

Workplace safety has been historically neglected by organizations in order to enhance profitability. Over the past 30 years, safety concerns and attention to safety have increased due to a series of disastrous events occurring across many different industries (e.g., Chernobyl, Upper Big-Branch Mine, Davis-Besse etc.). Many organizations have focused on promoting a healthy safety culture as a way to understand past incidents, and to prevent future disasters. There is an extensive academic literature devoted to safety culture, and the Department of Energy has also published a significant number of documents related to safety culture. The purpose of the current endeavor was to conduct a review of the safety culture literature in order to understand definitions, methodologies, models, and successful interventions for improving safety culture. After reviewing the literature, we observed four emerging themes. First, it was apparent that although safety culture is a valuable construct, it has some inherent weaknesses. For example, there is no common definition of safety culture and no standard way for assessing the construct. Second, it is apparent that researchers know how to measure particular components of safety culture, with specific focus on individual and organizational factors. Such existing methodologies can be leveraged for future assessments. Third, based on the published literature, the relationship between safety culture and performance is tenuous at best. There are few empirical studies that examine the relationship between safety culture and safety performance metrics. Further, most of these studies do not include a description of the implementation of interventions to improve safety culture, or do not measure the effect of these interventions on safety culture or performance. Fourth, safety culture is best viewed as a dynamic, multi-faceted overall system composed of individual, engineered and organizational models. By addressing all three components of safety culture, organizations have a better chance of understanding, evaluating, and making positive changes towards safety within their own organization.

Cole, Kerstan Suzanne; Stevens-Adams, Susan Marie; Wenner, Caren A.

2013-03-01T23:59:59.000Z

245

An analysis of the impacts of economic incentive programs on commercial nuclear power plant operations and maintenance costs  

SciTech Connect

Operations and Maintenance (O and M) expenditures by nuclear power plant owner/operators possess a very logical and vital link in considerations relating to plant safety and reliability. Since the determinants of O and M outlays are considerable and varied, the potential linkages to plant safety, both directly and indirectly, can likewise be substantial. One significant issue before the US Nuclear Regulatory Commission is the impact, if any, on O and M spending from state programs that attempt to improve plant operating performance, and how and to what extent these programs may affect plant safety and pose public health risks. The purpose of this study is to examine the role and degree of impacts from state promulgated economic incentive programs (EIPs) on plant O and M spending. A multivariate regression framework is specified, and the model is estimated on industry data over a five-year period, 1986--1990. Explanatory variables for the O and M spending model include plant characteristics, regulatory effects, financial strength factors, replacement power costs, and the performance incentive programs. EIPs are found to have statistically significant effects on plant O and M outlays, albeit small in relation to other factors. Moreover, the results indicate that the relatively financially weaker firms are more sensitive in their O and M spending to the presence of such programs. Formulations for linking spending behavior and EIPs with plant safety performance remains for future analysis.

Kavanaugh, D.C.; Monroe, W.H. [Pacific Northwest Lab., Richland, WA (United States); Wood, R.S. [Nuclear Regulatory Commission, Washington, DC (United States)

1996-02-01T23:59:59.000Z

246

Disaster City Safety  

Science Conference Proceedings (OSTI)

Safety. What Personal Protective Equipment (PPE) is needed to participate in this event? Personal ... On Site Safety Comes First. Be ...

2012-08-21T23:59:59.000Z

247

Engineered Fire Safety Group  

Science Conference Proceedings (OSTI)

Engineered Fire Safety Group. Welcome. ... Employment/Research Opportunities. Contact. Jason Averill, Leader. Engineered Fire Safety Group. ...

2012-06-05T23:59:59.000Z

248

Current Safety Performance Trends  

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

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

249

Safety & Emergency Management  

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

Coordination Management andor Coordination of APS Site WorkServices Safety & Emergency Management Database Maintenance Personnel Safety & Emergency Management Area...

250

Office of Nuclear Safety - Directives  

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

Nuclear and Facility Safety Directives Nuclear and Facility Safety Directives The HSS Office of Nuclear Safety is the responsible office for the development, interpretation, and revision of the following Department of Energy (DOE) directives. Go to DOE's Directives Web Page to view these directives. DOE Order (O) 252.1A, Technical Standards Program DOE O 252.1A promotes DOE's use of Voluntary Consensus Standards (VCS) as the primary method for application of technical standards and establishes and manages the DOE Technical Standards Program (TSP) including technical standards development, information, activities, issues, and interactions. HS-30 Contact: Jeff Feit DOE Policy (P) 420.1, Department of Energy Nuclear Safety Policy DOE P 420.1, documents the Department's nuclear safety policy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment.

251

The Office of Health, Safety and Security  

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

Office Assignments Office Assignments Recommendation Issue Leads No. Recommendation Issue Lead Backup 2012-2 Hanford Tank Farms Flammable Gas Safety Strategy Brian DiNunno Dale Govan 2012-1 Savannah River Site Building 235-F Safety Daniel Sigg Mark Do 2011-1 Safety Culture at the Waste Treatment and Immobilization Plant Daniel Sigg Brian DiNunno 2010-2 Pulse Jet Mixing at the Waste Treatment and Immobilization Plant Brian DiNunno Dale Govan 2010-1 Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers Brian DiNunno Daniel Sigg 2009-2 Los Alamos National Laboratory Plutonium Facility Seismic Safety Amanda Anderson Brian DiNunno 2009-1 Risk Assessment Methodologies at Defense Nuclear Facilities Brian DiNunno Dale Govan

252

Safety | Data.gov  

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

Safety Safety Safety Data/Tools Apps Challenges Resources Blogs Let's Talk Safety Welcome to the Safety Community The Safety Community is where data and insight are combined to facilitate a discussion around and awareness of our Nation's public safety activities. Whether you are interested in crime, roadway safety, or safety in the workplace, we have something for you. Check out the data, browse and use the apps, and be part of the discussion. Check out talks from the White House Safety Datapalooza Previous Pause Next One year of public safety data at Safety.Data.gov! Safety NHTSA releases SaferCar APIs and mobile app NHTSA releases SaferCar APIs and mobile app View More Todd Park, U.S. Chief Technology Officer at the Safety Datapalooza View More New APIs New APIs FRA launches new safety data dashboard and APIs.

253

Hanford Waste Treatment Plant Construction Quality Review  

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

ARPT-WTP-2011-002 Site: DOE Hanford Waste Treatment Plant Subject: Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the...

254

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 of this dissertation are to develop and demonstrate a novel useful conceptual model that could be used to allocate maintenance funds for a nuclear power plant in such a way as to meet all specified safety requirements and objectives, while achieving a high degree of economic performance. The model is based on the general theory that the reliability of a plant at any time is a function of its initial reliability and the maintenance history of the individual plant components (Smith, 1997). Such a model can assist in evaluating strategic management decisions regarding allocation of funds for nuclear power plant maintenance. It could be used as a simulation tool; various scenarios could be studied to answer "what if" questions. Simulations of this type will allow a better understanding of the relationship between maintenance, economic performance, and safety, and consequently will lead to better decision making. The novelty of this model is tied to the intimate relationship that it develops between maintenance activities at a nuclear plant, and their relationship to prescribed safety requirements and to the economic performance of that plant.

Erguina, Vera

2005-05-01T23:59:59.000Z

255

Electrical Safety - Monthly Analyses of Electrical Safety Occurrences  

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

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

256

Plutonium Finishing Plant (PFP) HVAC System Component Index  

Science Conference Proceedings (OSTI)

The Plutonium Finishing Plant (PFP) WAC System includes sub-systems 25A through 25K. Specific system boundaries and justifications are contained in HNF-SD-CP-SDD-005, ''Definition and Means of Maintaining the Ventilation System Confinement Portion of the PFP Safety Envelope.'' The procurement requirements associated with the system necessitates procurement of some system equipment as Commercial Grade Items in accordance with HNF-PRO-268, ''Control of Purchased Items and Services.'' This document lists safety class and safety significant components for the Heating Ventilation Air Conditioning and specifies the critical characteristics for Commercial Grade Items, as required by HNF-PRO-268 and HNF-PRO-1819. These are the minimum specifications that the equipment must meet in order to properly perform its safety function. There may be several manufacturers or models that meet the critical characteristics for any one item.

DICK, J.D.

2000-02-28T23:59:59.000Z

257

Plutonium Finishing Plant (PFP) HVAC System Component Index  

SciTech Connect

This document lists safety class (SC) and safety significant (SS) components for the Heating Ventilation Air Conditioning (HVAC) and specifies the critical characteristics for Commercial Grade Items (CGI), as required by HNF-PRO-268 and HNF-PRO-18 19. These are the minimum specifications that the equipment must meet in order to properly perform its safety function. There may be several manufacturers or models that meet the critical characteristics for any one item. The Plutonium Finishing Plant (PFP) HVAC System includes sub-systems 25A through 25K. Specific system boundaries and justifications are contained in HNF-SD-CP-SDD-005, ''Definition and Means of Maintaining the Ventilation System Confinement Portion of the PFP Safety Envelope.'' The procurement requirements associated with the system necessitates procurement of some system equipment as Commercial Grade Items in accordance with HNF-PRO-268, ''Control of Purchased Items and Services.''

DIAZ, E.N.

2000-03-30T23:59:59.000Z

258

Criticality and safeguards at the Idaho Chemical Processing Plant  

SciTech Connect

Reprocessing of high enriched irradiated reactor fuel at the Idaho Chemical Processing Plant (ICPP) presents significant potential problems to the Criticality Safety (CS) and Safeguards and Security (S and S) Sections. Two major interactions between these sections occurs when irradiated fuel is stored and fuel is dissolved. S and S is assigned the responsibility of maintaining a centralized records and reporting system which provides detailed, timely knowledge of the location, quantity and measurement uncertainties associated with accountable nuclear material, including uranium and plutonium. The Criticality Safety Section uses this information in providing criticality safety evaluations with support analyses, inspection, field surveillance and audits to ensure criticality safety implementation. The interactions of these sections has minimized operational constraints and maximized criticality safeguards controls.

Kodman, G.P.; Wilson, R.E.

1980-01-01T23:59:59.000Z

259

Using Hydrogen Safety Best Practices and Learning from Safety Events  

DOE Green Energy (OSTI)

A best practice is a technique or methodology that has reliably led to a desired result. A wealth of experience regarding the safe use and handling of hydrogen exists as a result of an extensive history in a wide variety of industrial and aerospace settings. Hydrogen Safety Best Practices (www.h2bestpractices.org) captures this vast knowledge base and makes it publically available to those working with hydrogen and related systems, including those just starting to work with hydrogen. This online manual is organized under a number of hierarchical technical content categories. References, including publications and other online links, that deal with the safety aspects of hydrogen are compiled for easy access. This paper discusses the development of Hydrogen Safety Best Practices as a safety knowledge tool, the nature of its technical content, and the steps taken to enhance its value and usefulness. Specific safety event examples are provided to illustrate the link between technical content in the online best practices manual and a companion safety knowledge tool, Hydrogen Incident Reporting and Lessons Learned (www.h2incidents.org), which encourages the sharing of lessons learned and other safety event information.

Weiner, Steven C.; Fassbender, Linda L.; Quick, Kathleen A.

2011-02-28T23:59:59.000Z

260

February 28, 2006, Department letter reporting completion of NNSA portion of Commitment 23 in the 2004-1 implementation plan, Oversight of Complex, High-Hazard Nuclear Operations, which requires the development of site office action plans to improve the consistency and reliability of work planning and work control at the activity level, including the incorporation of Integrated Safety Management core functions  

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

Washington, DC 20585 Washington, DC 20585 February 28, 2006 OFFICE O F THE ADMINISTRATOR The Honorable A. J. Eggenberger Ch a i rm an Defensc Nuclear Facilities Safety Board 625 Indiana Avenue, NW., Suite 700 Washington, D.C. 20004-2901 Dear Mr. Chairman: On Julie 10, 2005, Secretary Bodnian submitted the Department's Iiizplenzentution Plun to Itizpt-ove Oversight qf'Nucleur Operutions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2004- I , Oversight qf Complex, High-Hrrzurd Nucleur Openrtiotzs. Section 5.3 of the Implementation Plan (IP) addresses Revitalizing Integruted SU/i-'ty Munagernent Implementution, and Subsection 5.3.2 addresses Work Plunning mil Work Control ut the Activity Level. Commitment 23 of the 1P requires development of site office action plans to improve the consistency and reliability of work

Note: This page contains sample records for the topic "include plant safety" 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

Incentive regulation of nuclear power plants by state public utility commissions  

Science Conference Proceedings (OSTI)

This report on incentive regulation of nuclear power plants by state public utility commissions (PUCs). Economic performance incentives established by state PUCs are applicable to the construction or operation of about 45 nuclear power reactors owned by 30 utilities in 17 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant.

Petersen, J.C.

1987-12-01T23:59:59.000Z

262

Incentive regulation of nuclear power plants by state Public Utility Commissions  

Science Conference Proceedings (OSTI)

Economic performance incentives established by state Public Utility Commissions (PUCs) currently are applicable to the construction or operation of approximately 73 nuclear power reactors owned by 27 utilities with investment greater than 10% in 18 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its headquarters and regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report on incentive regulation of nuclear power plants by state PUCs presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant.

Martin, R.L.; Olson, J. (Battelle Human Affairs Research Center, Seattle, WA (USA)); Hendrickson, P. (Pacific Northwest Lab., Richland, WA (USA))

1989-12-01T23:59:59.000Z

263

Performance-Based Regulation: Prospects and Limitations in Health, Safety, and Environmental Regulation  

E-Print Network (OSTI)

simulations of nuclear power plants) from those that area meltdown of a nuclear power plant or a pipeline explosion)level of safety at nuclear power plants, they may require

Coglianese, Cary; Nash, Jennifer; Olmstead, Todd

2004-01-01T23:59:59.000Z

264

Laboratory Safety Certificate Course Completion Form  

E-Print Network (OSTI)

) Carcinogen Safety (2330) Centrifuge Safety (2335) Compressed Gas Safety (3835) Corrosive Safety (3055

Pawlowski, Wojtek

265

Next Generation Nuclear Plant GAP Analysis Report  

DOE Green Energy (OSTI)

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

2008-12-01T23:59:59.000Z

266

FAQS Qualification Card - Nuclear Safety Specialist | Department of  

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

Nuclear Safety Specialist Nuclear Safety Specialist FAQS Qualification Card - Nuclear Safety Specialist A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NuclearSafetySpecialist-2007.docx Description Nuclear Safety Specialist Qualification Card - 2007 FAQC-NuclearSafetySpecialist-2004.docx

267

Lawrence Berkeley National Lab/ Site Specific Safety Plan  

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

Lab/ Site Specific Safety Plan Lab/ Site Specific Safety Plan Site Specific Safety Plan Site Specific Safety Plan shall contain at a minimum: List by name & phone numbers the following person who will be on the project: Submit: Name of the On-site Superintendent & Phone. Submit: Name of the On-site Health and Safety Representative & Phone. Submit: Name of the person who is responsible for the implementation of safety plan. Submit: Resume & qualification of the person who is responsible for implantation of this projects safety plan. Include OSHA certifications. Submit: The companies' Policy statement on environment, safety and health. Submit: The companies' Policy on substance abuse and testing policy.

268

FAQS Qualification Card - Criticality Safety | Department of Energy  

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

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

269

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

Nero, jA.V.

2010-01-01T23:59:59.000Z

270

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.Fuel and Geo- thermal Power Plants," by G.D. Case, T.A.

Nero, A.V.

2010-01-01T23:59:59.000Z

271

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Response Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, jA.V.

2010-01-01T23:59:59.000Z

272

Secure Safety: Secure Remote Access to Critical Safety Systems in Offshore Installations  

Science Conference Proceedings (OSTI)

Safety Instrumented Systems (SIS) as defined in IEC 61508 and IEC 61511 are very important for the safety of offshore oil & natural gas installations. SIS typically include the Emergency Shutdown System (ESD) that ensures that process systems return ... Keywords: Offshore, Process Control, Safety Instrumented Systems, Secure remote access

Martin Gilje Jaatun; Tor Olav Grøtan; Maria B. Line

2008-06-01T23:59:59.000Z

273

Tag: Safety  

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

8/all en Red light, green light 8/all en Red light, green light http://www.y12.doe.gov/employees-retirees/y-12-times/red-light-green-light

Even in the face of a furlough, we were thorough, professional and kept an eye on safety and security.
  • RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

    E-Print Network (OSTI)

    to the nuclear power plant, the Marine Corps base, thePower Plant Emergency Response Plan, July 1975. United States Marine

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    275

    Nuclear power plants: Ecology and health physics. (Latest citations from the NTIS bibliographic database). Published Search  

    Science Conference Proceedings (OSTI)

    The bibliography contains citations concerning ecological and health aspects related to nuclear power plants. References cover radiation protection, occupational exposure, reactor safety and shielding, reactor accidents, and radiation measuring instruments. Genetic radiation effects, radiation-induced neoplasms, and radiation contaminants are examined. (Contains 50-250 citations and includes a subject term index and title list.)

    NONE

    1995-08-01T23:59:59.000Z

    276

    Safety of liquid hydrogen in air transportation  

    DOE Green Energy (OSTI)

    Safety is an important consideration in the use of hydrogen in air transportation. The use of cryogenic hydrogen involves the hazards arising from low temperatures as well as those of combustibles. An understanding of safety-related properties and their consequences is necessary for safe design and operation. Here we discuss hydrogen properties and their effect upon airline operation. Several safety problems require additional experimental work before they can be sufficiently understood. To maintain the good safety record associated with the previous use of liquid hydrogen requires a continuing safety engineering effort including planning, design, construction of equipment, and continuous training of personnel.

    Edeskuty, F.J.

    1979-01-01T23:59:59.000Z

    277

    Hydrogen Use and Safety  

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

    USE AND SAFETY USE AND SAFETY The lightest and most common element in the universe, hydrogen has been safely used for decades in industrial applications. Currently, over 9 million tons of hydrogen are produced in the U.S. each year and 3.2 trillion cubic feet are used to make many common products. They include glass, margarine, soap, vitamins, peanut butter, toothpaste and almost all metal products. Hydrogen has been used as a fuel since the 1950s by the National Aeronautics & Space Administration (NASA) in the U.S. space program. Hydrogen - A Safe, Clean Fuel for Vehicles Hydrogen has another use - one that can help our nation reduce its consumption of fossil fuels. Hydrogen can be used to power fuel cell vehicles. When combined with oxygen in a fuel cell, hydrogen generates electricity used

    278

    Independent Oversight Inspection, Pantex Plant - August 2005 | Department  

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

    Pantex Plant - August 2005 Pantex Plant - August 2005 Independent Oversight Inspection, Pantex Plant - August 2005 August 2005 Inspection of Emergency Management at the Pantex Site Office and the Pantex Plant The Secretary of Energy's Office of Independent Oversight and Performance Assurance (OA), within the Office of Security and Safety Performance Assurance, conducted an inspection of the emergency management program at the U.S. Department of Energy (DOE) Pantex Plant in July and August 2005. The inspection was performed by the OA Office of Emergency Management Oversight. This 2005 OA inspection found that PXSO and BWXT have adequately addressed most of these weaknesses and have improvement initiatives underway in some other areas. The resulting changes include a substantially improved

    279

    Safety Engineer | Princeton Plasma Physics Lab  

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

    Safety Engineer Safety Engineer Department: ESH&S Supervisor(s): Bill Slavin Staff: ADM 02 Requisition Number: 1300826 The Safety Engineer will help ensure that all work conducted for the Laboratory is done in a manner that does not compromise the safety and health of workers. The incumbent will provide oversight of the implementation of PPPL's safety programs, including development and /or support of associated policies and procedures. Programs include, but are not limited to the following: fall protection, machine guarding, hoisting and rigging, ladders, scaffolds, aerial lifts, fork lifts, personal protective equipment, compressed gases and other general industrial or construction safety related topics. Additional responsibilities include conducting periodic assessments to ensure the effectiveness of the PPPL's

    280

    Physical Plant Operations & Planning Health & Safety Program  

    E-Print Network (OSTI)

    Apprentice Consolidated Electrical Distributors, Inc. X X Management Trainee County of Sonoma X X X X A list

    Morris, Joy

    Note: This page contains sample records for the topic "include plant safety" 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

    APS Experiment Safety Review Board  

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

    Meeting Minutes * Laser Safety Notifications Charter for the APS Laser Safety Committee 1. Purpose The Laser Safety Committee advises APS Management on laser safety matters,...

    282

    Environment/Health/Safety (EHS): Laser Safety  

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

    Laser Safety Home Whom to Call Analysis of Laser Safety Occurrences: 2005-2011 Laser Bio-effects Laser Classification Laser Disposal Guide Laser Forms Laser Newsletter Laser Lab...

    283

    Independent Oversight Inspection of Environment, Safety, and Health  

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

    Inspection of Environment, Safety, and Health Inspection of Environment, Safety, and Health Programs at the Pantex Plant, Technical Appendices, Volume II, February 2005 Independent Oversight Inspection of Environment, Safety, and Health Programs at the Pantex Plant, Technical Appendices, Volume II, February 2005 The U.S. Department of Energy (DOE) Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) programs at the DOE Pantex Plant during January and February 2005. The inspection was performed by the OA Office of Environment, Safety and Health Evaluations. OA reports to the Director of the Office of Security and Safety Performance Assurance, who reports directly to the Secretary of Energy. This volume of the report provides four technical appendices (C through F)

    284

    Office of Nuclear Safety  

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

    Office of Nuclear Safety (HS-30) Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us

    285

    Safety for Users  

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

    Safety for Users Safety for Users Print Tuesday, 01 September 2009 08:01 Safety at the ALS The mission of the ALS is "Support users in doing outstanding science in a safe...

    286

    H. UNREVIEWED SAFETY QUESTIONS  

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

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

    287

    DUF6 Storage Safety  

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

    Storage Safety Depleted UF6 Storage line line How DUF6 is Stored Where DUF6 is Stored DUF6 Storage Safety Cylinder Leakage Depleted UF6 Storage Safety Continued cylinder storage is...

    288

    Acceptable NSLS Safety Documentation  

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

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

    289

    Balance of Plant Requirements for a Nuclear Hydrogen Plant  

    DOE Green Energy (OSTI)

    This document describes the requirements for the components and systems that support the hydrogen production portion of a 600 megawatt thermal (MWt) Next Generation Nuclear Plant (NGNP). These systems, defined as the "balance-of-plant" (BOP), are essential to operate an effective hydrogen production plant. Examples of BOP items are: heat recovery and heat rejection equipment, process material transport systems (pumps, valves, piping, etc.), control systems, safety systems, waste collection and disposal systems, maintenance and repair equipment, heating, ventilation, and air conditioning (HVAC), electrical supply and distribution, and others. The requirements in this document are applicable to the two hydrogen production processes currently under consideration in the DOE Nuclear Hydrogen Initiative. These processes are the sulfur iodide (S-I) process and the high temperature electrolysis (HTE) process. At present, the other two hydrogen production process - the hybrid sulfur-iodide electrolytic process (SE) and the calcium-bromide process (Ca-Br) -are under flow sheet development and not included in this report. While some features of the balance-of-plant requirements are common to all hydrogen production processes, some details will apply only to the specific needs of individual processes.

    Bradley Ward

    2006-04-01T23:59:59.000Z

    290

    Oversight Reports - Pantex Plant | Department of Energy  

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

    Oversight Reports - Pantex Plant Oversight Reports - Pantex Plant Oversight Reports - Pantex Plant December 31, 2013 Independent Oversight Review, Pantex Plant, December 2013 Targeted Review of the Safety Significant Blast Door and Personnel Door Interlock Systems and Review of Federal Assurance Capability at the Pantex Plant June 6, 2013 Independent Activity Report, Pantex Plant - May 2013 Operational Awareness Oversight of the Pantex Plant [HIAR PTX-2013-05-20] December 11, 2012 Independent Activity Report, Pantex Plant - November 2012 Pantex Plant Operational Awareness Site Visit [HIAR PTX-2012-11-08] November 28, 2012 Independent Oversight Assessment, Pantex Plant - November 2012 Assessment of Nuclear Safety Culture at the Pantex Plant August 8, 2012 Independent Activity Report, Pantex Plant - July 2012

    291

    EA-0970: Environmental Safety and Health Analytical Laboratory Project No.  

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

    70: Environmental Safety and Health Analytical Laboratory 70: Environmental Safety and Health Analytical Laboratory Project No. 94-AA-01 Pantex Plant, Amarillo, Texas EA-0970: Environmental Safety and Health Analytical Laboratory Project No. 94-AA-01 Pantex Plant, Amarillo, Texas SUMMARY This EA evaluates the environmental impacts of the proposal to construct and operate an Environmental Safety and Health Analytical Laboratory and subsequent demolition of the existing Analytical Chemistry Laboratory building at the U.S. Department of Energy's Pantex Plant near Amarillo, Texas. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 6, 1995 EA-0970: Finding of No Significant Impact Environmental Safety and Health Analytical Laboratory Project No. 94-AA-01 Pantex Plant Amarillo, TX

    292

    2007 Integrated Safety Management Workshop  

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

    ISM ISM Workshop 2007 a vision for Integrated Safety Management in the Department of Energy complex ISM Workshop 2007 ® Sample of how the graphic may be used on documents where the "Good to Great" verbiage is not includ "Good to Great" is a registered trademark of Jim Collins and is being used with permission. November 27-30, 2007 Hosted by Brookhaven National Laboratory "Good to Great" is a registered trademark of Jim Collins and is being used with permission. 2 Special Thanks Brookhaven National Laboratory Safety, Emergency and Traffic Information Safety, Health and Security Environment, Safety & Health Hotline: 631-344-8800 Occupational Medicine Clinic: 631-344-3670 Security Badging Office: 631-344-5149 Computer Security: 631-344-5522

    293

    Safety and Security Directives Reform  

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

    Reforming a "Mountain" of Policy Reforming a "Mountain" of Policy Beginning with his confirmation hearings in January 2009, Energy Secretary Steven Chu challenged the Department of Energy to take a fresh look at how we conduct business. This challenge provided the opportunity for DOE to put in place the most effective and efficient strategies to accomplish the Department's missions safely and securely. In response to the Secretary's challenge and building on the results of Deputy Secretary Poneman's Safety and Security Reform studies, the Office of Health, Safety and Security (HSS) broadened its directives review activities during 2009. By November 2009 HSS had initiated a disciplined review of all health, safety, and security directives, which included a systematic review of the Department's safety and security regulatory model.

    294

    Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor  

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

    Risk Informed Safety Margin Characterization (RISMC) Advanced Test Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC)

    295

    NanoFab Safety  

    Science Conference Proceedings (OSTI)

    Safety in the NanoFab. ... Detailed guidance on working safely in the NanoFab can be found in the CNST NanoFab Safety Manual. ...

    2013-09-21T23:59:59.000Z

    296

    Nuclear Safety Workshops  

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

    Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical Standards Program Search Approved Standards Recently Approved RevCom...

    297

    Nuclear criticality safety guide  

    Science Conference Proceedings (OSTI)

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

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

    1996-09-01T23:59:59.000Z

    298

    Dam Safety (Pennsylvania)  

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

    299

    Safety aspects of the US advanced LMR (liquid metal reactor) design  

    SciTech Connect

    The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. This paper discusses the US regulatory framework for design of an ALMR, safety aspects of the IFR program at ANL, the IFR fuel cycle and actinide recycle, and the ALMR plant design program at GE. 6 refs., 5 figs.

    Pedersen, D.R.; Gyorey, G.L.; Marchaterre, J.F.; Rosen, S. (Argonne National Lab., IL (USA); General Electric Co., San Jose, CA (USA); Argonne National Lab., IL (USA); USDOE Assistant Secretary for Nuclear Energy, Washington, DC (USA))

    1989-01-01T23:59:59.000Z

    300

    Embrittlement of Components in Fossil Fueled Power Plants  

    Science Conference Proceedings (OSTI)

    Plant operators seek to adopt approaches that can minimize costs, prevent forced outages, and maximize safety and reliability. Rigorous life assessment methodologies have been developed over the years and are commonly employed to determine component integrity and life. Such assessments examine key operational characteristics, including elevated temperature exposure, cycling operation, loading, environmental exposure, and other characteristics to determine remaining life. Many of these characteristics can...

    2003-11-26T23:59:59.000Z

    Note: This page contains sample records for the topic "include plant safety" 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

    Management of Process Wastewater at Coal-Fired Power Plants  

    Science Conference Proceedings (OSTI)

    A confluence of drivers is causing utilities to consider closing ash ponds and converting to dry ash handling. These drivers include wastewater discharge regulations on salinity, chlorides, nutrients, and metals, as well as solid waste regulations resulting from concerns with pond safety. Because ash ponds at many sites receive a variety of wastewaters, even if a plant converts to dry ash handling and thereby reduces or eliminates ash sluice water, other wastewater streams will still require treatment. E...

    2012-04-30T23:59:59.000Z

    302

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

    Science Conference Proceedings (OSTI)

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

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

    1993-10-01T23:59:59.000Z

    303

    Recent Changes to the Criticality Safety Program at LLNL  

    SciTech Connect

    During the 1996 audit, a corrective action program was developed and implemented to enhance the Criticality Safety Program at Lawrence Livermore National Laboratory. The Criticality Safety Program at LLNL has been rebuilt to combine a strong core criticality safety program with direct field support to floor operations. Field staff are integrated into the supported facility and program efforts. This method of operation effects all aspects of the criticality safety program including, as examples, development of criticality safety controls and training.

    Pearson, J.S.; Burch, J.G.; Huang, S.T.

    2001-08-22T23:59:59.000Z

    304

    Dynamic Safety Systems (DSS) Technology  

    Science Conference Proceedings (OSTI)

    This report considers several aspects of Dynamic Safety System (DSS) technology and its use in United States (U.S.) light-water reactor (LWR) safety systems. The topics include: the capability of DSS technology to function in an LWR protection system, the feasibility of licensing DSS technology under Code of Federal Regulations 10 CFR 50.59 for use in a reactor protection system (RPS), and the possibility of extending the automatic self-testing regime to include the front-end neutron sensors that feed si...

    1998-05-27T23:59:59.000Z

    305

    Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1  

    Science Conference Proceedings (OSTI)

    This report was prepared in response to regulatory and management concern regarding the reliability of medium-voltage cable systems at nuclear plants. The staff of the U.S. Nuclear Regulatory Commission (NRC) have been concerned that wetted (up to and including submergence) medium-voltage cable circuits may be degrading to the point at which multiple cable circuits may fail when called on to perform functions affecting safety. A utility manager’s concern is that cables may fail, causing ...

    2013-06-03T23:59:59.000Z

    306

    Complete Safety Training  

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

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

    307

    Complete Safety Training  

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

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

    308

    Complete Safety Training  

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

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

    309

    1,200 To Attend DOE Safety Workshop - Integrated Safety Management (ISM)  

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

    1,200 To Attend DOE Safety Workshop - Integrated Safety Management 1,200 To Attend DOE Safety Workshop - Integrated Safety Management (ISM) Workshop Features Nationally Renowned Speakers 1,200 To Attend DOE Safety Workshop - Integrated Safety Management (ISM) Workshop Features Nationally Renowned Speakers September 9, 2011 - 12:00pm Addthis KENNEWICK, WASH. - The Department of Energy (DOE) offices at Hanford will host the 2011 Integrated Safety Management (ISM) Champions Workshop at the Three Rivers Convention Center in Kennewick for DOE and contractor employees from sites across the country on September 12-15. More than 1,200 people are expected to attend the workshop, which features nationally acclaimed keynote speakers and high-level DOE officials. The workshop agenda also includes tours of Hanford, a safety symposium,

    310

    JM to Revise DOE O 420.1B, Facility Safety (9-23-10)  

    Directives, Delegations, and Requirements

    This approval includes revision of the three implementing Guides: DOE G 420.1-1, Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide ...

    2010-09-23T23:59:59.000Z

    311

    Ice maker safety control  

    Science Conference Proceedings (OSTI)

    In a refrigeration apparatus including an evaporator, a defrost heater for defrosting the evaporator, a defrost thermostat having a switch for de-energizing the defrost heater at a preselected high temperature of the evaporator, and an ice making apparatus having a mold, a mold heater, and a control circuit controllably energized the mold heater, a safety control for the ice making apparatus is described comprising: means for thermally coupling the defrost thermostat with the mold; and means electrically connecting the defrost thermostat switch with the control circuit for de-energizing the mold heater at a preselected high temperature of the mold to prevent overheating thereof.

    Linstromberg, W.J.

    1988-05-03T23:59:59.000Z

    312

    Safety culture in the nuclear power industry : attributes for regulatory assessment  

    E-Print Network (OSTI)

    Safety culture refers to the attitudes, behaviors, and conditions that affect safety performance and often arises in discussions following incidents at nuclear power plants. As it involves both operational and management ...

    Alexander, Erin L

    2004-01-01T23:59:59.000Z

    313

    What Does Self-Assessment of Safety Culture Look Like? Discussion...  

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

    Does Self-Assessment of Safety Culture Look Like? Discussion from the Pantex Plant Perspective What Does Self-Assessment of Safety Culture Look Like? Discussion from the Pantex...

    314

    FAQS Qualification Card - Senior Technical Safety Manager | Department of  

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

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

    315

    FAQS Qualification Card - Safety Software Quality Assurance | Department  

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

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

    316

    FAQS Qualification Card - Aviation Safety Officer | Department of Energy  

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

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

    317

    FAQS Qualification Card - Nuclear Explosive Safety Study | Department of  

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

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

    318

    FAQS Qualification Card - Occupational Safety | Department of Energy  

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

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

    319

    Waste Isolation Pilot Plant - Reports  

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

    Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

    320

    RISK-INFORMED SAFETY MARGIN CHARACTERIZATION  

    Science Conference Proceedings (OSTI)

    The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system’s “loading” and its “capacity”, plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons.

    Nam Dinh; Ronaldo Szilard

    2009-07-01T23:59:59.000Z

    Note: This page contains sample records for the topic "include plant safety" 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

    DOE safety goals comparison using NUREG-1150 PRA (probabilistic risk assessment) methodology  

    Science Conference Proceedings (OSTI)

    A full-scope Level 3 probabilistic risk assessment (PRA) including external events has been performed for N Reactor, a US Department of Energy (DOE) Category A production reactor. This four-year, multi-million dollar task was a joint effort by Westinghouse Hanford Company, Science Applications International Corporation (SAIC), and Sandia National Laboratories (SNL). Technical lead in external events and NUREG-1150 methodology was provided by SNL. SAIC led the effort in the Level 1 analysis for the internally initiated events. Westinghouse Hanford supported the task in many key areas, such as data collection and interpretation, accident progression, system interaction, human factor analyses, expert elicitation, peers review, etc. The main objective of this Level 3 PRA are to assess the risks to the public and onsite workers posed by the operation of N Reactor, to identify modifications to the plant that could reduce the overall risk, and to compare those risks to the proposed DOE and Nuclear Regulatory Commission (NRC) quantitative safety goals. This paper presents the methodology adopted by Westinghouse Hanford and SNL for estimating individual health risks, and the comparison of the N Reactor results and DOE quantitative nuclear safety guidelines. This paper is devoted to DOE quantitative safety guidelines interpretation and comparison; the NRC safety objectives are also presented in order to compare N Reactor results to commercial nuclear power plants included in the NUREG-1150 study. 7 refs., 7 tabs.

    Wang., O.S.; Zentner, M.D.; Rainey, T.E.

    1990-06-01T23:59:59.000Z

    322

    Appendix F Cultural Resources, Including  

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

    Appendix F Appendix F Cultural Resources, Including Section 106 Consultation STATE OF CALIFORNIA - THE RESOURCES AGENCY EDMUND G. BROWN, JR., Governor OFFICE OF HISTORIC PRESERVATION DEPARTMENT OF PARKS AND RECREATION 1725 23 rd Street, Suite 100 SACRAMENTO, CA 95816-7100 (916) 445-7000 Fax: (916) 445-7053 calshpo@parks.ca.gov www.ohp.parks.ca.gov June 14, 2011 Reply in Reference To: DOE110407A Angela Colamaria Loan Programs Office Environmental Compliance Division Department of Energy 1000 Independence Ave SW, LP-10 Washington, DC 20585 Re: Topaz Solar Farm, San Luis Obispo County, California Dear Ms. Colamaria: Thank you for seeking my consultation regarding the above noted undertaking. Pursuant to 36 CFR Part 800 (as amended 8-05-04) regulations implementing Section

    323

    RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

    E-Print Network (OSTI)

    Power Plants. WASH~1400 (NUREG 75/014). October 1975. S.Power Plants -LWR Edison." NUREG-75! 094, October 1975. NRCof Fixed Nuclear Facilities, NUREG-75/l1l (Reprint of WASH-

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    324

    CHEMICAL SAFETY Emergency Numbers  

    E-Print Network (OSTI)

    - 1 - CHEMICAL SAFETY MANUAL 2010 #12;- 2 - Emergency Numbers UNBC Prince George Campus Security Prince George Campus Chemstores 6472 Chemical Safety 6472 Radiation Safety 5530 Biological Safety 5530 use, storage, handling, waste and emergency management of chemicals on the University of Northern

    Bolch, Tobias

    325

    Countries Gasoline Prices Including Taxes  

    Gasoline and Diesel Fuel Update (EIA)

    Countries (U.S. dollars per gallon, including taxes) Countries (U.S. dollars per gallon, including taxes) Date Belgium France Germany Italy Netherlands UK US 01/13/14 7.83 7.76 7.90 8.91 8.76 8.11 3.68 01/06/14 8.00 7.78 7.94 8.92 8.74 8.09 3.69 12/30/13 NA NA NA NA NA NA 3.68 12/23/13 NA NA NA NA NA NA 3.63 12/16/13 7.86 7.79 8.05 9.00 8.78 8.08 3.61 12/9/13 7.95 7.81 8.14 8.99 8.80 8.12 3.63 12/2/13 7.91 7.68 8.07 8.85 8.68 8.08 3.64 11/25/13 7.69 7.61 8.07 8.77 8.63 7.97 3.65 11/18/13 7.99 7.54 8.00 8.70 8.57 7.92 3.57 11/11/13 7.63 7.44 7.79 8.63 8.46 7.85 3.55 11/4/13 7.70 7.51 7.98 8.70 8.59 7.86 3.61 10/28/13 8.02 7.74 8.08 8.96 8.79 8.04 3.64 10/21/13 7.91 7.71 8.11 8.94 8.80 8.05 3.70 10/14/13 7.88 7.62 8.05 8.87 8.74 7.97 3.69

    326

    Passive Safety Features for Small Modular Reactors  

    Science Conference Proceedings (OSTI)

    The rapid growth in the size and complexity of commercial nuclear power plants in the 1970s spawned an interest in smaller, simpler designs that are inherently or intrinsically safe through the use of passive design features. Several designs were developed, but none were ever built, although some of their passive safety features were incorporated into large commercial plant designs that are being planned or built today. In recent years, several reactor vendors are actively redeveloping small modular reactor (SMR) designs with even greater use of passive features. Several designs incorporate the ultimate in passive safety they completely eliminate specific accident initiators from the design. Other design features help to reduce the likelihood of an accident or help to mitigate the accident s consequences, should one occur. While some passive safety features are common to most SMR designs, irrespective of the coolant technology, other features are specific to water, gas, or liquid-metal cooled SMR designs. The extensive use of passive safety features in SMRs promise to make these plants highly robust, protecting both the general public and the owner/investor. Once demonstrated, these plants should allow nuclear power to be used confidently for a broader range of customers and applications than will be possible with large plants alone.

    Ingersoll, Daniel T [ORNL

    2010-01-01T23:59:59.000Z

    327

    2012 Nuclear Safety Workshop Presentations | Department of Energy  

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

    2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations Wednesday, September 19 - Plenary Session September 19, 2012 Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company September 19, 2012 A Commissioner's Perspective on USNRC Actions in Response to the Fukushima Nuclear Accident Presenter: Honorable William C. Ostendorff, Commissioner US Nuclear Regulatory Commission September 19, 2012 International Perspective on Fukushima Accident Presenter: Miroslav Lipár, Head, Operational Safety Section, Department of

    328

    RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

    E-Print Network (OSTI)

    20555. u. S. Nuclear U. S. NRC. Reactor Safety Study: AnNUREG-75! 094, October 1975. NRC Regulatory Guide 1. 101. "Report on Current Activities NRC and the Federal Interagency

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    329

    Integrated Safety Management Policy  

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

    INTEGRATED SAFETY INTEGRATED SAFETY MANAGEMENT SYSTEM DESCRIPTION U.S. DEPARTMENT OF ENERGY Office of Environmental Management Headquarters May 2008 Preparation: Braj K. sin& Occupational Safety and Health Manager Office of Safety Management Concurrence: Chuan-Fu wu Director, Offlce of Safety Management Deputy Assistant Secretary for safe& Management andoperations Operations Officer for 1 Environmental Management Approval: Date p/-g Date Environmental Management TABLE OF CONTENTS ACRONYMS................................................................................................................................................................v EXECUTIVE SUMMARY .........................................................................................................................................1

    330

    Bog Plants  

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

    Bog Plants Bog Plants Nature Bulletin No. 385-A June 6, 1970 Forest Preserve District of Cook County George W. Dunne, President Roland F. Eisenbeis, Supt. of Conservation BOG PLANTS Fifty years ago there were probably more different kinds of plants within a 50 mile radius from the Loop than anywhere else in the Temperate Zone. Industrial, commercial and residential developments, plus drainage and fires have erased the habitats where many of the more uncommon kinds flourished, including almost all of the tamarack swamps and quaking bogs. These bogs were a heritage from the last glacier. Its front had advanced in a great curve, from 10 to 20 miles beyond what is now the shoreline of Lake Michigan, before the climate changed and it began to melt back. Apparently the retreat was so rapid that huge blocks of ice were left behind, surrounded by the outwash of boulders, gravel and ground-up rock called "drift". These undrained depressions; became lakes. Sphagnum moss invaded many of them and eventually the thick floating mats of it supported a variety of bog-loving plants including certain shrubs, tamarack, and a small species of birch. Such lakes became bogs.

    331

    2011 Annual Criticality Safety Program Performance Summary  

    SciTech Connect

    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

    332

    2011 Annual Criticality Safety Program Performance Summary  

    SciTech Connect

    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 Progra

    Andrea Hoffman

    2011-12-01T23:59:59.000Z

    333

    Recommended research on LNG safety  

    Science Conference Proceedings (OSTI)

    The US Department of Energy (DOE) is conducting research on the safety and other environmental aspects of liquefied energy gases including liquefied natural gas (LNG). The effort reported here was conducted as part of the planning for further research into the safety aspects of transporting and storing LNG, with primary emphasis on public safety. Although the modern LNG industry has enjoyed excellent success in providing for safe operations, significant questions remain on the part of many, the expressions of which were intensified with the addition of marine-based LNG import terminals. Public safety with regard to large-scale importation of this fuel has received widespread attention in the US Congress, state legislatures, county and city governments, and from various individuals and public groups, with coverage in all the news media, including books published on the subject. The safety concerns have centered around the consequences to the public of a large spill of the cryogenic liquid from an ocean tanker or a larger storage tank, either of which might hold as much as 125,000 m/sup 3/ of LNG.

    Carpenter, H.J.; Gilmore, F.R.

    1981-03-01T23:59:59.000Z

    334

    Inspection, Kansas City Plant - May 2004 | Department of Energy  

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

    Inspection, Kansas City Plant - May 2004 Inspection, Kansas City Plant - May 2004 Inspection, Kansas City Plant - May 2004 May 2004 Inspection of Environment, Safety, and Health Management at the Kansas City Plant The Secretary of Energy's Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) at the U.S. Department of Energy (DOE) Kansas City Plant (KCP) site during April and May 2004. The inspection was performed by the OA Office of Environment, Safety and Health Evaluations. Overall, FM&T management, ES&H subject matter experts, and the individuals who conduct work activities and safety management at KCP are experienced and exhibit a commitment to safety and quality work. The site has a good safety record, and safety performance metrics indicate improving trends.

    335

    Workers Deliver Award-Winning Respiratory Safety | Department of Energy  

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

    Workers Deliver Award-Winning Respiratory Safety Workers Deliver Award-Winning Respiratory Safety Workers Deliver Award-Winning Respiratory Safety April 2, 2013 - 12:00pm Addthis Workers wear air purifying respirators in the Plutonium Finishing Plant. Workers wear air purifying respirators in the Plutonium Finishing Plant. A program developed by employees enhances use of respiratory equipment in the Plutonium Finishing Plant. A program developed by employees enhances use of respiratory equipment in the Plutonium Finishing Plant. Workers wear air purifying respirators in the Plutonium Finishing Plant. A program developed by employees enhances use of respiratory equipment in the Plutonium Finishing Plant. RICHLAND, Wash. - Workers supporting the Richland Operations Office at the Hanford site found a way to make their everyday work even safer.

    336

    Workers Deliver Award-Winning Respiratory Safety | Department of Energy  

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

    Deliver Award-Winning Respiratory Safety Deliver Award-Winning Respiratory Safety Workers Deliver Award-Winning Respiratory Safety April 2, 2013 - 12:00pm Addthis Workers wear air purifying respirators in the Plutonium Finishing Plant. Workers wear air purifying respirators in the Plutonium Finishing Plant. A program developed by employees enhances use of respiratory equipment in the Plutonium Finishing Plant. A program developed by employees enhances use of respiratory equipment in the Plutonium Finishing Plant. Workers wear air purifying respirators in the Plutonium Finishing Plant. A program developed by employees enhances use of respiratory equipment in the Plutonium Finishing Plant. RICHLAND, Wash. - Workers supporting the Richland Operations Office at the Hanford site found a way to make their everyday work even safer.

    337

    ACTIVITY SPECIFIC FIREARMS SAFETY PLAN FOR  

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

    Atmospheric Radiation Measurement Climate Research Facility/ Atmospheric Radiation Measurement Climate Research Facility/ North Slope of Alaska/Adjacent Arctic Ocean (ACRF/NSA/AAO) Activity Specific Firearm Safety Plan for ACRF/North Slope of Alaska Sandia National Laboratories Department 6383, Energy, Climate & Atmospheric Management ACRF/NSA/AAO Revision 14 Activity Specific Firearm Safety Plan for June 2010 ACRF/North Slope of Alaska Signature Page This safety plan is approved by the undersigned and includes the firearm and ammunition storage practices described in this document. Mark D Ivey ACRF/NSA/AAO Site Manager _________________________________Date: ______ Mark D Ivey Department 06339 Manager _________________________________Date: _______ Michael L Heister SNL Safety Engineer _________________________________Date:________

    338

    DOE Seeks Proposals for Portsmouth Plant Technical Services | Department of  

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

    Plant Technical Services Plant Technical Services DOE Seeks Proposals for Portsmouth Plant Technical Services August 21, 2012 - 12:00pm Addthis Media Contact Bill Taylor bill.taylor@srs.gov 803-952-8564 Cincinnati - The Department of Energy today issued a Request for Proposals (RFP) for an Environmental Technical Services acquisition at the Portsmouth Gaseous Diffusion Plant near Piketon, Ohio. The RFP proposes a cost-plus-award-fee contract for three-years with a one-time option out to five-years. The estimated cost and fee amount for the technical services contract is approximately $55-65 million. The major support areas within the draft RFP include: Program Management Planning and Integration Environmental Safety and Health (ES&H) and Quality Assurance (QA) Waste Management Regulatory Support

    339

    Inspection of Environment, Safety, and Health Management at the Waste  

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

    Environment, Safety, and Health Management at the Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002 The Secretary of Energy's Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) and emergency management programs at the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) in July and August 2002. The inspection was performed as a joint effort by the OA Office of Environment, Safety and Health Evaluations and the Office of Emergency Management Oversight. This volume discusses the results of the review of the WIPP ES&H programs. The results of the review of the WIPP emergency management program are

    340

    Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor  

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

    (RISMC) Advanced Test (RISMC) Advanced Test Reactor Demonstration Case Study Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for

    Note: This page contains sample records for the topic "include plant safety" 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

    Environment/Health/Safety (EHS): Safety Minute  

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

    Numbers & Contacts (PDF, PPT) Emergency Response Guide (PDF, PPT) Occurence Reporting (ORPS) (PDF, PPT) Reporting Hazardous Conditions (PDF, PPT) Reporting Safety Concerns (PDF,...

    342

    Environment/Health/Safety (EHS): Safety Minute  

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

    at Home (PDF, PPT) Emergency Response - Tips for Home (PDF, PPT) Household Hazardous Waste (PDF, PPT) Preventing Fires at Home (PDF, PPT) Tire Safety (PDF, PPT) Vehicle Inspections...

    343

    Environment/Health/Safety (EHS): Safety Minute  

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

    Shop Area (PDF, PPT) Chemical Inventory (PDF, PPT) Chemical Management System - Consumer Products (PDF, PPT) Earthquake Restraints (PDF, PPT) Equipment Use (PDF, PPT) Ladder Safety...

    344

    Environment/Health/Safety (EHS): Safety Minute  

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

    Mistakes in Managing (PDF, PPT) Biohazardous Waste, Managing (PDF, PPT) Chemical Inventory (PDF, PPT) Chemical Management System - Consumer Products (PDF, PPT) Chemical Safety...

    345

    100-MW NUCLEAR POWER PLANT UTILIZING A SODIUM COOLED, GRAPHITE MODERATED REACTOR  

    SciTech Connect

    The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel handling, instrumentation, turbine-generator, buildings. and safety measures are described. Engineering drawings are included. (W.D.M.)

    1958-02-28T23:59:59.000Z

    346

    OSIRIS and SOMBRERO Inertial Fusion Power Plant Designs, Volume 2: Designs, Assessments, and Comparisons  

    Science Conference Proceedings (OSTI)

    This is a comprehensive design study of two Inertial Fusion Energy (IFE) electric power plants. Conceptual designs are presented for a fusion reactor (called Osiris) using an induction-linac heavy-ion beam driver, and another (called SOMBRERO) using a KrF laser driver. The designs covered all aspects of IFE power plants, including the chambers, heat transport and power conversion systems, balance-of-plant facilities, target fabrication, target injection and tracking, as well as the heavy-ion and KrF drivers. The point designs were assessed and compared in terms of their environmental & safety aspects, reliability and availability, economics, and technology development needs.

    Meier, W. R.; Bieri, R. L.; Monsler, M. J.; Hendricks, C. D.; Laybourne, P.; Shillito, K. R.

    1992-03-01T23:59:59.000Z

    347

    Independent Oversight Assessment, Pantex Plant - November 2012 | Department  

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

    Pantex Plant - November 2012 Pantex Plant - November 2012 Independent Oversight Assessment, Pantex Plant - November 2012 November 2012 Assessment of Nuclear Safety Culture at the Pantex Plant The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent assessment of nuclear safety culture at the Pantex Plant. The primary objective of the evaluation was to provide information regarding the status of the safety culture at the Pantex Plant. The data collection phase of the assessment occurred during June - August 2012. The safety culture evaluation performed by the external independent safety culture experts is provided in Appendix B, which provides positive observations and identifies areas in need of attention for each of the nine

    348

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

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

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

    349

    SI Safety Information  

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

    Information Information Policies and Procedures Radiation Safety Device List (full version)(compressed version) APS QA APS Safety Page DOE Orders DOE Order 420.2 (11/08/95) DOE Order 420.2A (01/08/01) Accelerator Safety Implementation Guide for DOE Order 420.2 DOE Order 420.2B (07/23/04) Expires (07/23/08) (html) (pdf) Accelerator Facility Safety Implementation Guide for DOE O 420.2B (html) (pdf) Safety of Accelerator Facilities (02/18/05) Accelerator Facility Safety Implementation Guide for DOE O 420.2B (pdf) Safety of Accelerator Facilities (7/1/05) ESH Manual Guidance 5480.25 Guidance for an Accelerator Facility Safety Program 5480.25 Guidance (09/01/93) Bases & Rationale for Guidance for an Accelerator Facitlity Safety Program (October 1994) NCRP Report No. 88 "Radiation Alarms and Access Control Systems" (1987) ISBN

    350

    Integrated Safety Management (ISM)  

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

    Integrated Safety Management Integrated Safety Management Home ISM Policy ISM Champions ISM Workshops Resources Archives Contact Us Health and Safety HSS Logo Integrated Safety Management (ISM) ism logo Welcome to the Department of Energy's Office of Health, Safety and Security (HSS) Integrated Safety Management (ISM) Web Site. The Department and its contractors remain firmly committed to ISM as first defined in 1996. The objective of ISM is to perform work in a safe and environmentally sound manner. More specifically, as described in DOE P 450.4, Safety Management System Policy: "The Department and Contractors must systematically integrate safety into management and work practices at all levels so that missions are accomplished while protecting the public, the worker, and the environment. This is to be accomplished through effective integration of safety management into all facets of work planning and execution." "

    351

    Genetic Engineered Food and Safety  

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

    Genetic Engineered Food and Safety Genetic Engineered Food and Safety Name: Christopher Location: N/A Country: N/A Date: N/A Question: Is genetically engineered food safe to eat? Replies: Well, I hope so, since I and you and all of us have been eating it for centuries. All common foodstuffs have been seriously engineered since they were discovered. The modern tomato plant, apple tree, wheat stalk, and corn plant bear only a general resemblance to their ancestors, as farmers have engineered them to increase their yield, shelf life, resistance to disease, etc. It is, however, true that up until recently changes to the genetic code of foodstuffs could only be made via natural mutation (which occurs via naturally-occuring ionizing radiation and mutagenic chemicals), and the food engineer's job was limited to selecting those changes he wanted to preserve, and those he wanted to weed out. Now you can induce mutations directly, with intention and forethought, and avoid much of the waiting around for natural mutation that was heretofore necessary in plant breeding.

    352

    Development of a hierarchical fuzzy model for the evaluation of inherent safety  

    E-Print Network (OSTI)

    Inherent safety has been recognized as a design approach useful to remove or reduce hazards at the source instead of controlling them with add-on protective barriers. However, inherent safety is based on qualitative principles that cannot easily be evaluated and analyzed, and this is one of the major difficulties for the systematic application and quantification of inherent safety in plant design. The present research introduces the use of fuzzy logic for the measurement of inherent safety by proposing a hierarchical fuzzy model. This dissertation establishes a novel conceptual framework for the analysis of inherent safety and proposes a methodology that addresses several of the limitations of the methodologies available for current inherent safety analysis. This research proposes a methodology based on a hierarchical fuzzy model that analyzes the interaction of variables relevant for inherent safety and process safety in general. The use of fuzzy logic is helpful for modeling uncertainty and subjectivities implied in evaluation of certain variables and it is helpful for combining quantitative data with qualitative information. Fuzzy logic offers the advantage of being able to model numerical and heuristic expert knowledge by using fuzzy IF-THEN rules. Safety is traditionally considered a subjective issue because of the high uncertainty associated with its significant descriptors and parameters; however, this research recognizes that rather than subjective, "safety" is a vague problem. Vagueness derives from the fact that it is not possible to define sharp boundaries between safe and unsafe states; therefore the problem is a "matter of degree". The proposed method is computer-based and process simulator-oriented in order to reduce the time and expertise required for the analysis. It is expected that in the future, by linking the present approach to a process simulator, process engineers can develop safety analysis during the early stages of the design in a rapid and systematic way. Another important aspect of inherent safety, rarely addressed, is transportation of chemical substances; this dissertation includes the analysis of transportation hazard by truck using a fuzzy logic-based approach.

    Gentile, Michela

    2004-08-01T23:59:59.000Z

    353

    Performance and safety design of the advanced liquid metal reactor  

    SciTech Connect

    The Advanced Liquid Metal Reactor (ALMR) program led by General Electric is developing, under U.S. Department of Energy sponsorship, a conceptual design for an advanced sodium-cooled liquid metal reactor plant. This design is intended to improve the already excellent level of plant safety achieved by the nuclear power industry while at the same time providing significant reductions in plant construction and operating costs. In this paper, the plant design and performance are reviewed, with emphasis on the ALMR's unique passive design safety features and its capability to utilize as fuel the actinides in LWR spent fuel.

    Berglund, R.C.; Magee, P.M.; Boardman, C.E.; Gyorey, G.L. (General Electric Co., San Jose, CA (United States). Advanced Nuclear Technology)

    1991-01-01T23:59:59.000Z

    354

    Nuclear Safety Regulatory Framework  

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

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

    355

    The Safety Concept of the SWR 1000  

    SciTech Connect

    The SWR 1000 blends years of experience in design, construction and operation of BWRs with new concepts to achieve an optimum blend of increased safety and reduced costs. These objectives were met by introducing passive systems for performing safety-related functions in the event of transients or accidents. Compared to the fleet of currently operating reactors, the technology employed in these systems is much simpler, operation is independent of a power supply, activation by instrumentation and control (I and C) systems is not required, and fewer supporting systems are required. The passive safety equipment is capable of controlling any postulated transient conditions arising during power operation. Nevertheless, service-proven active safety systems are still intended to operate, if possible, before passive safety equipment takes over. The functional scope and degree of redundancy of these active systems can, however, be reduced. This safety concept is supplemented by systems and actions for controlling a postulated core melt accident; i.e. for retaining the molten core inside the reactor pressure vessel (RPV) so that even the consequences of this type of severe accident will remain restricted to within the plant itself and no emergency response actions will be necessary in the plant environs. (author)

    Pasler, Doris [Framatome ANP GmbH, NGPS5, Berliner Str. 295, 63067 Offenbach (Germany)

    2004-07-01T23:59:59.000Z

    356

    FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter  

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

    Safety, Codes & Standards Search Search Help Safety, Codes & Standards EERE Fuel Cell Technologies Office Safety, Codes & Standards Printable Version Share this...

    357

    CCE CHEMICAL SAFETY MANUAL CHEMICAL SAFETY MANUAL  

    E-Print Network (OSTI)

    . Chemicals--Safety measures. 3. Hazardous wastes. I. National Research Council (U.S.). Committee on Prudent) produced two major reports on laboratory safety and laboratory waste disposal: Prudent Practices Nanomaterials, 77 4.G Biohazards, 79 4.H Hazards from Radioactivity, 79 5 Management of Chemicals 83 5.A

    Tai, Yu-Chong

    358

    A risk-informed approach to safety margins analysis  

    SciTech Connect

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

    Curtis Smith; Diego Mandelli

    2013-07-01T23:59:59.000Z

    359

    POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

    E-Print Network (OSTI)

    NP-263, October 1976. Edison Electric Institute, "Report onREGULATION Data from the Edison Electric Institute annualpower plants. However, the Edison Electric Institute, in its

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    360

    POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

    E-Print Network (OSTI)

    Power Plant Reliability-Availability and State Regulation,"Report on Equipment Availability: Fossil and NuclearBasic Definitions* Availability: Reliability: Base Loading:

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    Note: This page contains sample records for the topic "include plant safety" 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

    Onsite Wastewater Treatment Systems: Graywater Safety  

    E-Print Network (OSTI)

    Homeowners who use graywater to water their lawns need to understand the risks and safety issues associated with this practice. This publication discusses the constituents of graywater; their potential effects on human, soil, plant and environmental health and steps to prevent harm to them. 6 pp., 1 figure, 3 tables

    Melton, Rebecca; Lesikar, Bruce J.

    2008-10-23T23:59:59.000Z

    362

    Westinghouse Hanford Company health and safety performance report  

    SciTech Connect

    Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% from the CY 1995 rate of 1.03 (page 2-8). The reengineering of the Radiological Control organization has resulted in an increase in the availability of personnel to help facilities with the procurement and use of practical ALARA measures. In addition, there seems to be more awareness of the need to use ALARA, resulting in a significant increase in the number of calls received by the ALARA Program Office for help in solving radiological problems (page 1-3). The Figure 3-2-1 chart data includes WHC, BCSR, and ICF KH employee exposure. The first quarter CY 1996 results represent the exposure of 1,913 quarterly-badged employees and an average of 846 monthly-badged employees. There were three instances of potential loss of contamination control during the calendar quarter involving three workers where internal dosimetry follow-up was performed. No intakes of contamination were detected (page 3-6). There were five skin contaminations and 18 clothing contaminations reported during this quarter in all WHC-managed facilities/areas. This represents an improvement in performance compared to the first quarter of CY 1995 (page 3-9). A monthly average of 76 Radiological Problem Reports (RPR) was issued during the first quarter of CY 1996 for a total issuance of 227 RPRS. The monthly average for the same quarter in CY 1995 was 76; a total of 228 for the quarter (Figure 3-5-1). At the end of March, WHC Dosimetry was monitoring the following employees/sub- contractors: 631 monthly standard dosimeters, 251 monthly combination dosimeters, 1,386 quarterly standard dosimeters, 472 quarterly combination dosimeters, and 3,716 annual dosimeters. During this period, Dosimetry had 987 requests for changes to the frequency, and terminated 731 dosimetry records.

    Rogers, L.

    1996-05-15T23:59:59.000Z

    363

    Framework for Risk-Informed Safety Margin Characterization  

    Science Conference Proceedings (OSTI)

    Commercial nuclear power plants in operation continue to undergo design and operational changes to support cost-effective long-term operation. Additionally, as plant operational lifetimes are extended, it is imperative that they effectively manage aging degradation, prevent the occurrence of any safety-significant operational events, and analytically demonstrate acceptable (and even improved) nuclear safety risk. This report describes initial research to develop and validate an integrated framework and a...

    2009-12-22T23:59:59.000Z

    364

    Safety and Relief Valve Testing and Maintenance Guide  

    Science Conference Proceedings (OSTI)

    This guide gives a broad overview of self actuated and power operated pressure relief devices (PRDs) -- safety, relief, safety relief, and power-operated relief valves -- and their application and maintenance. The non-reclosing devices, like the rupture discs, are outside the scope of this guide. The information in this guide, though directed towards the nuclear power plant personnel, will assist all power plant personnel responsible for the maintenance of PRDs. This guide can also be used by training in...

    1996-10-02T23:59:59.000Z

    365

    Orientation Visit to the Waste Isolation Pilot Plant, September...  

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

    WIPP-2011-09-07 Site: Waste Isolation Pilot Plant Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the...

    366

    Orientation Visit to the Paducah Gaseous Diffusion Plant  

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

    PAD-2011-07-27 Site: Paducah Gaseous Diffusion Plant Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the...

    367

    Activity Report for Waste Treatment and Immobilizationi Plant...  

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

    and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Waste Treatment and Immobilization Plant Low Activity Waste Melter Off-gas Process...

    368

    Review of the Pantex Plant Implementation Verification Review...  

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

    of the Pantex Plant Implementation Verification Review Processes February 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of...

    369

    Operational Awareness Site Visi to the Pantex Plant, October...  

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

    Activity Report - Rev. 0 Report Number: HIAR PTX-2011-10-28 Site: Pantex Plant Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations...

    370

    Pantex Plant Operational Awareness Oversight Report _July 2012  

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

    PTX-2012-07-19 Site: Pantex Plant Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Operational Awareness...

    371

    Safety and Health Services Division  

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

    The Safety & Health Services Division (SHSD) provides subject matter expertise and services in industrial hygiene, safety engineering, and safety & health programs for the Lab....

    372

    Safety System Oversight: Steering Committee  

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

    Safety Home Safety System Oversight Home Annual SSOFR Workshop DOE Safety Links ORPS Info Operating Experience Summary DOE Lessons Learned Accident...

    373

    Coal Mine Safety Act (Virginia)  

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

    This Act is the primary legislation pertaining to coal mine safety in Virginia. It contains information on safety rules, safety standards and required certifications for mine workers, prohibited...

    374

    Safety posters | Argonne National Laboratory  

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

    34 Leaders in Safety: Electrical Safety Labels Inspect equipment for approved electrical safety labels before plugging in... "Before I plug in electric-powered equipment, I check...

    375

    Technical Safety Requirements  

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

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

    376

    Documented Safety Analysis  

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

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

    377

    Conceptual Safety Design RM  

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

    The Conceptual Safety Design (CSD) Review Module (RM) is a tool that assists DOE federal project review teams in evaluating the adequacy of the Conceptual Safety Design work, processes and...

    378

    Safety Design Strategy RM  

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

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

    379

    Preliminary Safety Design RM  

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

    The Preliminary Safety Design (PSD) Review Module (RM) is a tool that assists DOE federal project review teams in evaluating the adequacy of the Preliminary Safety Design work, processes and...

    380

    Aviation safety analysis  

    E-Print Network (OSTI)

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

    Ausrotas, Raymond A.

    1984-01-01T23:59:59.000Z

    Note: This page contains sample records for the topic "include plant safety" 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

    Argonne CNM: Safety Training  

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

    Safety Training Before performing work at the CNM, you must take certain safety training courses. We encourage you to take these courses remotely before you arrive at Argonne. Go...

    382

    Dam Safety Program (Maryland)  

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

    The Dam Safety Division within the Department of the Environment is responsible for administering a dam safety program to regulate the construction, operation, and maintenance of dams to prevent...

    383

    Nuclear criticality safety department training implementation  

    SciTech Connect

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. The NCSD Qualification Program is described in Y/DD-694, Qualification Program, Nuclear Criticality Safety Department This document provides a listing of the roles and responsibilities of NCSD personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This document supersedes Y/DD-696, Revision 2, dated 3/27/96, Training Implementation, Nuclear Criticality Safety Department. There are no backfit requirements associated with revisions to this document.

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-09-06T23:59:59.000Z

    384

    Nuclear safety as applied to space power reactor systems  

    SciTech Connect

    Current space nuclear power reactor safety issues are discussed with respect to the unique characteristics of these reactors. An approach to achieving adequate safety and a perception of safety is outlined. This approach calls for a carefully conceived safety program which makes uses of lessons learned from previous terrestrial power reactor development programs. This approach includes use of risk analyses, passive safety design features, and analyses/experiments to understand and control off-design conditions. The point is made that some recent accidents concerning terrestrial power reactors do not imply that space power reactors cannot be operated safety.

    Cummings, G.E.

    1987-01-01T23:59:59.000Z

    385

    Environmental testing of an experimental digital safety channel  

    SciTech Connect

    This document presents the results of environmental stress tests performed on an experimental digital safety channel (EDSC) assembled at the Oak Ridge National Laboratory (ORNL) as part of the NRC-sponsored Qualification of Advanced Instrumentation and Controls (W) System program. The objective of this study is to investigate failure modes and vulnerabilities of microprocessor-based technologies when subjected to environmental stressors. The study contributes to the technical basis for environmental qualification of safety-related digital I&C systems. The EDSC employs technologies and digital subsystems representative of those proposed for use in advanced light-water reactors (ALWRs) or for retrofits in existing plants. Subsystems include computers, electrical and optical serial communication links, fiber-optic network links, analog-to-digital and digital-to-analog converters, and multiplexers. The EDSC was subjected to selected stressors that are a potential risk to digital equipment in a mild environment. The selected stressors were electromagnetic and radio-frequency interference (EMYRFI), temperature, humidity, and smoke exposure. The stressors were applied over ranges that were considerably higher than what the channel is likely to experience in a normal nuclear power plant environment. Ranges of stress were selected at a sufficiently high level to induce errors so that failure modes that are characteristic of the technologies employed could be identified.

    Korsah, K.; Tanaka, T.J.; Wilson, T.L. Jr.; Wood, R.T.

    1996-09-01T23:59:59.000Z

    386

    HTGR Dust Safety Issues and Needs for Research and Development  

    Science Conference Proceedings (OSTI)

    This report presents a summary of high temperature gas-cooled reactor dust safety issues. It draws upon a literature review and the proceedings of the Very High Temperature Reactor Dust Assessment Meeting held in Rockville, MD in March 2011 to identify and prioritize the phenomena and issues that characterize the effect of carbonaceous dust on high temperature reactor safety. It reflects the work and input of approximately 40 participants from the U.S. Department of Energy and its National Labs, the U.S. Nuclear Regulatory Commission, industry, academia, and international nuclear research organizations on the topics of dust generation and characterization, transport, fission product interactions, and chemical reactions. The meeting was organized by the Idaho National Laboratory under the auspices of the Next Generation Nuclear Plant Project, with support from the U.S. Nuclear Regulatory Commission. Information gleaned from the report and related meetings will be used to enhance the fuel, graphite, and methods technical program plans that guide research and development under the Next Generation Nuclear Plant Project. Based on meeting discussions and presentations, major research and development needs include: generating adsorption isotherms for fission products that display an affinity for dust, investigating the formation and properties of carbonaceous crust on the inside of high temperature reactor coolant pipes, and confirming the predominant source of dust as abrasion between fuel spheres and the fuel handling system.

    Paul W. Humrickhouse

    2011-06-01T23:59:59.000Z

    387

    Lisheng Safety Laboratory  

    Science Conference Proceedings (OSTI)

    Lisheng Safety Laboratory. NVLAP Lab Code: 200882-0. Address and Contact Information: Electronic & Lighting (Xiamen) Co. Ltd. No. ...

    2013-09-27T23:59:59.000Z

    388

    Safety and Security  

    Science Conference Proceedings (OSTI)

    *. Bookmark and Share. Safety and Security. ... National and International Standards for X-ray Security Screening Applications. ...

    2013-07-29T23:59:59.000Z

    389

    Electrical safety guidelines  

    SciTech Connect

    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

    390

    DOE handbook electrical safety  

    SciTech Connect

    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

    391

    Generic safety documentation model  

    SciTech Connect

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

    Mahn, J.A.

    1994-04-01T23:59:59.000Z

    392

    Safety Basis Information System  

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

    Analysis (SESA) SESA Home Mission & Functions Office of Sustainability, Environment, Safety and Anaylsis (SESA) Sustainability Support Environmental Policy & Assistance ...

    393

    Plant maintenance and advanced reactors, 2005  

    SciTech Connect

    The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: First U.S. EPRs in 2015, by Ray Ganthner, Framatome ANP; Pursuing several opportunities, by William E. (Ed) Cummins, Westinghouse Electric Company; Vigorous plans to develop advanced reactors, by Yuliang Sun, Tsinghua University, China; Multiple designs, small and large, by Kumiaki Moriya, Hitachi Ltd., Japan; Sealed and embedded for safety and security, by Handa Norihiko, Toshiba Corporation, Japan; Scheduled online in 2010, by Johan Slabber, PMBR (Pty) Ltd., South Africa; Multi-application reactors, by Nikolay G. Kodochigov, OKBM, Russia; Six projects under budget and on schedule, by David F. Togerson, AECL, Canada; Creating a positive image, by Scott Peterson, Nuclear Energy Institute (NEI); Advanced plans for nuclear power's renaissance, by John Cleveland, International Atomic Energy Agency, Austria; and, Plant profile: last five outages in less than 20 days, by Beth Rapczynski, Exelon Nuclear.

    Agnihotri, Newal (ed.)

    2005-09-15T23:59:59.000Z

    394

    FCT Safety, Codes and Standards: DOE Safety, Codes, and Standards...  

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

    Safety, Codes, and Standards Activities to someone by E-mail Share FCT Safety, Codes and Standards: DOE Safety, Codes, and Standards Activities on Facebook Tweet about FCT Safety,...

    395

    Universal software safety standard  

    Science Conference Proceedings (OSTI)

    This paper identifies the minimum subset required for a truly universal safety-critical software standard. This universal software standard could be used in but is not limited to the following application domains: commercial, military and space ... Keywords: software safety, system safety, validation, verification

    P. V. Bhansali

    2005-09-01T23:59:59.000Z

    396

    HTGR safety research program  

    SciTech Connect

    An HTGR safety research program is being performed supporting and guided in priorities by the AIPA Probabilistic Risk Study. Analytical and experimental studies have been conducted in four general areas where modeling or data assumptions contribute to large uncertainties in the consequence assessments and thus, in the risk assessment for key core heat-up accident scenarios. Experimental data have been obtained on time-dependent release of fission products from the fuel particles, and plateout characteristics of condensible fission products in the primary circuit. Potential failure modes of primarily top head PCRV components as well as concrete degradation processes have been analyzed using a series of newly developed models and interlinked computer programs. Containment phenomena, including fission product deposition and potential flammability of liberated combustible gases have been studied analytically.

    Barsell, A.W.; Olsen, B.E.; Silady, F.A.

    1980-08-01T23:59:59.000Z

    397

    New baseload power plants  

    Science Conference Proceedings (OSTI)

    This is a tabulation of the results of this magazines survey of current plans for new baseload power plants. The table lists the unit name, capacity, fuel, engineering firm, constructor, suppliers for steam generator, turbine generator and flue gas desulfurization equipment, date due on-line, and any non-utility participants. The table includes fossil-fuel plants, nuclear plants, geothermal, biomass and hydroelectric plants.

    Not Available

    1993-04-01T23:59:59.000Z

    398

    Pantex Plant | Department of Energy  

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

    Pantex Plant Pantex Plant Pantex Plant Pantex Plant | September 2010 Aerial View Pantex Plant | September 2010 Aerial View The primary mission of the Pantex Plant is the assembly, disassembly, testing, and evaluation of nuclear weapons in support of the NNSA stockpile stewardship program. Pantex also performs research and development in conventional high explosives and serves as an interim storage site for plutonium pits removed from dismantled weapons. Enforcement January 7, 2013 Enforcement Letter, NEL-2013-01 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant November 21, 2006 Preliminary Notice of Violation, BWXT Pantex, LLC - EA-2006-04 Issued to BWXT Pantex, LLC, related to Quality Assurance and Safety Basis Requirements Violations at the Pantex Plant

    399

    CRITICALITY SAFETY (CS)  

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

    Objective CS.1 - A criticality safety program is established, sufficient numbers of qualified personnel are provided, and adequate facilities and equipment are available to ensure criticality safety support services are adequate for safe operations. (Core Requirements 1, 2, and 6) Criteria * Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented. * Operations support personnel for the criticality safety area are adequately staffed and trained. Approach Record Review: Review the documentation that establishes the Criticality Safety Requirements (CSRs) for appropriateness and completeness. Review for adequacy and completion the criticality safety personnel training records that indicate training on facility procedures and systems under

    400

    MTDC Safety Sensor Technology  

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

    MTDC Safety Sensor Technology MTDC Safety Sensor Technology Background Beyond the standard duty cycle data collection system used in the Department of Energy's Medium Truck Duty Cycle program, additional sensors were installed on three test vehicles to collect several safety-related signals of interest to the Federal Motor Carrier Safety Administration. The real-time brake stroke, tire pressure, and weight information obtained from these sensors is expected to make possible a number of safety-related analyses such as determining the frequency and severity of braking events and tracking tire pressure changes over time. Because these signals are posted to the vehicle's databus, they also have the potential to be

    Note: This page contains sample records for the topic "include plant safety" 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

    CRITICALITY SAFETY (CS)  

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

    OBJECTIVE CS.1 The LANL criticality safety program provides the required technical guidance and oversight capabilities to ensure a comprehensive criticality safety program for the storage of nuclear materials in SSTs. (Core Requirements 3, 4, 8) Criteria * The Criticality Safety Program is an administrative TSR and meets the General and * Specific Requirements of DOE O 420.1A, Section 4.3 Nuclear Criticality Safety. * All processes and operations involving significant quantities of fissile materials are * described in current procedures approved by line management. * Procedures contain approved criticality controls and limits, based on HSR-6 evaluations and recommendations. * Supervisors, operations personnel, and criticality safety officers have received

    402

    Center for Intermodal Transportation Safety  

    E-Print Network (OSTI)

    Center for Intermodal Transportation Safety and Security Panagiotis Scarlatos, Ph.D., Director Transportation Safety and Security #12;Center for Intermodal Transportation Safety and Security Partners #12 evacuations · Tracking systems for hazardous materials Center for Intermodal Transportation Safety

    Fernandez, Eduardo

    403

    Risk-informed incident management for nuclear power plants  

    E-Print Network (OSTI)

    Decision making as a part of nuclear power plant operations is a critical, but common, task. Plant management is forced to make decisions that may have safety and economic consequences. Formal decision theory offers the ...

    Smith, Curtis Lee, 1966-

    2002-01-01T23:59:59.000Z

    404

    SIGNAL GROUPING FOR CONDITION MONITORING OF NUCLEAR POWER PLANT COMPONENTS  

    E-Print Network (OSTI)

    SIGNAL GROUPING FOR CONDITION MONITORING OF NUCLEAR POWER PLANT COMPONENTS Piero Baraldi between those used to monitor the reactor coolant pump of a Pressurized Water Reactor (PWR) is considered Monitoring, Empirical Modeling, Power Plants, Safety Critical Nuclear Instrumentation, Autoassociative models

    405

    Safety audit of refrigerated liquefied gas facilities  

    SciTech Connect

    An Exxon Research and Engineering Co. comprehensive review of engineering practices and application of safety requirements at Exxon's world-wide refrigerated liquefied hydrocarbon gas storage and handling installations, which included a field audit of about 90 tanks at 30 locations, showed that catastrophic tank failure was not a credible event with properly operated and maintained tanks designed, constructed, and tested in accordance with API Standard 620, Design and Construction of Large Welded Low-Pressure Storage Tanks, although supplemental requirements were suggested to further enhance safety. The review also showed that any meaningful safety audit should be comprehensive and must include all facilities with careful attention to detail. The review embraces products of -1 to -167C and included LNG, ethylene, LPG, and LPG olefins. Recent and proposed LNG safety legislation; some field audit results; and recommendations as to design, construction, and operation of LNG and LPG storage facilities, marine terminals, and tankers, are also discussed.

    Feely, F.J.; Sommer, E.C.; Marshall, B.T.; Palmer, A.J.

    1980-01-01T23:59:59.000Z

    406

    FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter  

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

    H2 Safety Snapshot H2 Safety Snapshot Newsletter to someone by E-mail Share FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Facebook Tweet about FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Twitter Bookmark FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Google Bookmark FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Delicious Rank FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Digg Find More places to share FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on AddThis.com... Home Basics Current Approaches to Safety, Codes & Standards DOE Activities Quick Links Hydrogen Production Hydrogen Delivery Hydrogen Storage Fuel Cells Technology Validation Manufacturing Education Systems Analysis

    407

    Nuclear Facility Safety Basis  

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

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

    408

    Chemical Safety Program  

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

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

    409

    Safety System Oversight  

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

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

    410

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

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

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

    411

    DOE O 460.1C, Packaging and Transportation Safety  

    Directives, Delegations, and Requirements

    The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of ...

    2010-05-14T23:59:59.000Z

    412

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

    Science Conference Proceedings (OSTI)

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

    Alan Bond

    2001-04-01T23:59:59.000Z

    413

    Plant Support Engineering: Aging Management Program Development Guidance for AC and DC Low-Voltage Power Cable Systems for Nuclear P ower Plants  

    Science Conference Proceedings (OSTI)

    Regulatory and management concern regarding the reliability of low-voltage power cable systems at nuclear plants has been increasing for the past 5–10 years. The staff of the United States Nuclear Regulatory Commission are concerned that wetted (up to and including submergence) low-voltage power cable circuits may be degrading to the point at which multiple cable circuits may fail when called on to perform functions affecting safety. Utility managers are concerned that cables may fail, causing adverse sa...

    2010-06-02T23:59:59.000Z

    414

    POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

    E-Print Network (OSTI)

    which steam is raised. nuclear fuel generates heat that isattention to nuclear and fossil-fuel plants, and these areFor all the fossil-fuel and nuclear (However, categories,

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    415

    Safety/safeguards interactions during safety-related emergencies at Nuclear Power Reactor Facilities  

    Science Conference Proceedings (OSTI)

    This report contains an analysis of the safety/safeguards interactions that could occur during safety-related emergencies at licensed nuclear power reactors, and the extent to which these interactions are addressed in existing or proposed NRC guidance. The safety/safeguards interaction during a series of postulated emergencies was systematically examined to identify any potential performance deficiencies or conflicts between the Operations (safety) and Security (safeguards) organizations. This examination included the impacts of coordination with off-site emergency response personnel. Duties, responsibilities, optimal methods, and procedural actions inherent in these interactions were explored.

    Moul, D.A.; Pilgrim, M.K.; Schweizer, R.L.; McEwen, J.E. Jr.

    1985-03-01T23:59:59.000Z

    416

    Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program  

    DOE Green Energy (OSTI)

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

    Not Available

    1987-05-01T23:59:59.000Z

    417

    Generic Qualification of the ABB Common Qualified PLC Based Platform for Safety-Related Applications  

    Science Conference Proceedings (OSTI)

    As its nuclear plants age, the electric power industry is focusing on the development of cost-effective replacement systems for obsolete instrumentation, control, and safety systems. This report describes the generic qualification a platform for safety-related applications that incorporates programmable logic controllers (PLCs), a technology with an excellent track record in non-nuclear applications for critical control and safety functions.

    1999-08-18T23:59:59.000Z

    418

    Modular HTGR Safety Basis and Approach  

    SciTech Connect

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) capable of producing electricity and/or high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) process, as recommended in the NGNP Licensing Strategy - A Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy [DOE/NRC 2008]. Nuclear Regulatory Commission (NRC) licensing of the NGNP plant utilizing this process will demonstrate the efficacy for licensing future HTGRs for commercial industrial applications. This information paper is one in a series of submittals that address key generic issues of the priority licensing topics as part of the process for establishing HTGR regulatory requirements. This information paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach with the NRC staff and public stakeholders. The NGNP project does not expect to receive comments on this information paper because other white papers are addressing key generic issues of the priority licensing topics in greater detail.

    Thomas Hicks

    2011-08-01T23:59:59.000Z

    419

    Recommended guidelines for solid fuel use in cement plants  

    Science Conference Proceedings (OSTI)

    Pulverized solid fuel use at cement plants in North America is universal and includes bituminous and sub-bituminous coal, petroleum coke, and any combination of these materials. Provided are guidelines for the safe use of pulverized solid fuel systems in cement plants, including discussion of the National Fire Protection Association and FM Global fire and explosion prevention standards. Addressed are fire and explosion hazards related to solid fuel use in the cement industry, fuel handling and fuel system descriptions, engineering design theory, kiln system operations, electrical equipment, instrumentation and safety interlock issues, maintenance and training, and a brief review of code issues. New technology on fire and explosion prevention including deflagration venting is also presented.

    Young, G.L.; Jayaraman, H.; Tseng, H. (and others)

    2007-07-01T23:59:59.000Z

    420

    Seabrook Station probabilistic safety assessment. Main report, volumes 1-6 and summary report  

    SciTech Connect

    This report documents an independent probabilistic safety assessment of the twin nuclear power plants under construction near Seabrook, New Hampshire. This assessment quantified the risk to public health and safety associated with potential accidents during the period of operation of the station. The main report contains the technical analyses of the Seabrook plant and site, the risk modeling and data analysis.

    Not Available

    1983-12-01T23:59:59.000Z

    Note: This page contains sample records for the topic "include plant safety" 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

    Automatic safety rod for reactors  

    DOE Patents (OSTI)

    An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-core flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.

    Germer, John H. (San Jose, CA)

    1988-01-01T23:59:59.000Z

    422

    Hanford Waste Vitrification Plant technical manual  

    SciTech Connect

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

    Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

    1996-03-01T23:59:59.000Z

    423

    Environment, Safety and Health Evaluations - Reports  

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

    Environment, Safety and Health Evaluations Reports Review Reports 2010 Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010 Site Visit Report - Facility Centered Assessment of the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility, June 2010 Independent Oversight Inspection of the Hanford Site Chronic Beryllium Disease Prevention Program, June 2010 Site Visit Report - Review of the Lawrence Livermore National Laboratory Fire Protection Design Review Process, May 2010 Independent Oversight Assessment of Environmental Monitoring at the Idaho National Laboratory Site, May 2010 Independent Oversight Focus Area Review of Specific Administrative Controls at DOE Nuclear Facilities, April 2010

    424

    Functional Conceptual Design Criteria - 5-MW/sub e/ salt-gradient solar pond power plant at Great Salt Lake  

    DOE Green Energy (OSTI)

    The purpose of this solar pond plant facility would be to provide valid data on the cost, operation, and reliability of salt-gradient solar ponds as a means of producing power. A general facility description is given which includes design code requirements, site selection, site characteristics, and site-specific design requirements. Functional requirements discussed include: civil-structural; mechanical; electrical; and control, instrumentation and alarms. Occupational and environmental safety, security, and quality assurance are also discussed.

    Brown, L.M.; Barnhart, J.S.; Cavola, R.G.; Drost, M.K.; Hauser, S.G.; Johnson, B.M.

    1983-08-01T23:59:59.000Z

    425

    Plants & Animals  

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

    Plants & Animals Plants & Animals Plants & Animals Plant and animal monitoring is performed to determine whether Laboratory operations are impacting human health via the food chain. April 12, 2012 A rabbit on LANL land. A rabbit on LANL land. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email We sample many plants and animals, including wild and domestic crops, game animals, fish, and food products from animals, as well as other plants and animals not considered food sources. What plants and animals do we monitor? LANL monitors both edible and non-edible plants and animals to determine whether Laboratory operations are impacting human health via the food chain, or to find contaminants that indicate they are being moved in the

    426

    Plant immune systems  

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

    Plant immune systems Plant immune systems Name: stephanie Status: N/A Age: N/A Location: N/A Country: N/A Date: Around 1993 Question: Do plants have an immune system? How does it work? Are plants able to "fight off" infections such as Dutch Elm disease? Replies: In the broadest sense, an immune system is any method an organism has protect itself from succeeding to another organism's efforts to undermine its health and integrity. In this sense, yes, plants have immune systems. Plants do NOT have "active" immune systems, like humans, including macrophages, lymls, antibodies, complements, interferon, etc., which help us ward off infection. Rather, plants have "passive" mechanisms of protection. For instance, the waxy secretion of some plants (cuticle) functions to help hold in moisture and keep out microorganisms. Plants can also secrete irritating juices that prevent insects and animals from eating it. The thick bark of woody plants is another example of a defensive adaptation, that protects the more delicate tissues inside. The chemical secretions of some plants are downright poisonous to many organisms, which greatly enhance the chances of survival for the plant. Fruits of plants contain large amounts of vitamin C and bioflavonoids, compounds which have been shown in the lab to be anti-bacterial and antiviral. So in these ways, plants can improve their chances of survival. Hundreds of viruses and bacteria attack plants each year, and the cost to agriculture is enormous. I would venture to guess that once an organism establishes an infection in a plant, the plant will not be able to "fight" it. However, exposure to the sun's UV light may help control an infection, possibly even defeat it, but the plant does not have any inherent "active" way to fight the infection

    427

    Plan for addressing issues relating to oil shale plant siting  

    SciTech Connect

    The Western Research Institute plan for addressing oil shale plant siting methodology calls for identifying the available resources such as oil shale, water, topography and transportation, and human resources. Restrictions on development are addressed: land ownership, land use, water rights, environment, socioeconomics, culture, health and safety, and other institutional restrictions. Descriptions of the technologies for development of oil shale resources are included. The impacts of oil shale development on the environment, socioeconomic structure, water availability, and other conditions are discussed. Finally, the Western Research Institute plan proposes to integrate these topics to develop a flow chart for oil shale plant siting. Western Research Institute has (1) identified relative topics for shale oil plant siting, (2) surveyed both published and unpublished information, and (3) identified data gaps and research needs. 910 refs., 3 figs., 30 tabs.

    Noridin, J.S.; Donovan, R.; Trudell, L.; Dean, J.; Blevins, A.; Harrington, L.W.; James, R.; Berdan, G.

    1987-09-01T23:59:59.000Z

    428

    Safety for Users  

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

    Safety for Users Safety for Users Safety for Users Print Safety at the ALS The mission of the ALS is "Support users in doing outstanding science in a safe environment." All users and staff participate in creating a culture and environment where performing research using the proper safeguards and fulfilling all safety requirements result in the success of the facility and its scientific program. The documents and guidance below will assist users and staff to achieve these goals. How Do I...? A series of fact sheets that explain what users need to know and do when preparing to conduct experiments at the ALS. Complete Experiment Safety Documentation? Work with Biological Materials? Work with Chemicals? Work with Regulated Soil? Bring and Use Electrical Equipment at the ALS?

    429

    Combustion Safety Overview  

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

    March 1-2, 2012 March 1-2, 2012 Building America Stakeholders Meeting Austin, Texas Combustion Safety in the Codes Larry Brand Gas Technology Institute Acknowledgement to Paul Cabot - American Gas Association 2 | Building America Program www.buildingamerica.gov Combustion Safety in the Codes Widely adopted fuel gas codes: * National Fuel Gas Code - ANSI Z223.1/NFPA 54, published by AGA and NFPA (NFGC) * International Fuel Gas Code - published by the International Code Council (IFGC) * Uniform Plumbing Code published by IAPMO (UPC) Safety codes become requirements when adopted by the Authority Having Jurisdiction (governments or fire safety authorities) 3 | Building America Program www.buildingamerica.gov Combustion Safety in the Codes Formal Relationships Between these codes: - The IFGC extracts many safety

    430

    Safety at CERN  

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

    U.S. CMS Program U.S. CMS Program Last Updated: March 19, 2012 Safety at CERN Information for U. S. Personnel This information was developed by the U.S. Department of Energy, Office of Science. It is provided to assist you in preparing for your visit to CERN and to help you work safely. As at any U.S. laboratory, you are also responsible for your own safety at CERN. If you are in doubt as to whether your working conditions meet safety standards, you must ask for clarification from your supervisor, the CMS GLIMOS, the PH Department Safety Officer or, if necessary, the CERN Safety Commission. If you regard yourself or others as clearly at risk, you must interrupt the work to take corrective action. Your primary points of contact for safety related questions or

    431

    Safety | Argonne National Laboratory  

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

    Safety Safety Biosafety Safety Safety is integral to Argonne's scientific research and engineering technology mission. As a leading U.S. Department of Energy multi-program research laboratory, our obligation to the American people demands that we conduct our research and operations safely and responsibly. As a recognized leader in safety, we are committed to making ethical decisions that provide a safe and healthful workplace and a positive presence within the larger Chicagoland community. Argonne's Integrated Safety Management program is the foundation of the laboratory's ongoing effort to provide a safe and productive environment for employees, users, other site personnel, visitors and the public. Related Sites U.S. Department of Energy Lessons Learned Featured Media

    432

    Risk Informed Safety Margin Characterization Case Study: Selection of  

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

    Case Study: Selection Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification Risk Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification Reference 1 discussed key elements of the process for developing a margins-based "safety case" to support safe and efficient operation for an extended period. The present report documents (in Appendix A) a case study, carrying out key steps of the Reference 1 process, using an actual plant Probabilistic Risk Assessment (PRA) model. In general, the margins-based safety case helps the decision-maker manage plant margins most effectively. It tells the plant decision-maker such things as what margin is present (at the plant level, at the functional

    433

    Interactive Trouble Condition Sign Discovery for Hydroelectric Power Plants  

    Science Conference Proceedings (OSTI)

    Kyushu Electric Power Co.,Inc. collects different sensor data and weather information (hereafter, operation data) to maintain the safety of hydroelectric power plants while the plants are running. It is very rare to occur trouble condition in the plants. ... Keywords: Data Mining, Hydroelectric Power Plant, Support Vector Machine, Trouble Condition Detection

    Takashi Onoda; Norihiko Ito; Hironobu Yamasaki

    2009-07-01T23:59:59.000Z

    434

    Beamline Safety Design Review Steering Committee Charter  

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

    Meeting Minutes internal link Meeting Minutes internal link Reviews internal link Beamline Safety Design Review Steering Committee (BSDRSC) 1. Purpose The Beamline Safety Design Review Steering Committee (BSDRSC) oversees the review of all safety aspects related to beamline and critical component design, regardless of who generated the design, and includes facility operational issues when reviewing non-APS generated designs. 2. Membership Members appointed by the APS Division Directors will be comprised of a pre-selected standing committee with membership chosen by function. The following functions will be included: AES User Technical Interface (Committee Chair) AES Technical Operations Specialist APS Electrical / Electronics Technical Representative AES QA Engineering Specialist APS Radiation Safety Shielding Committee Chair

    435

    Safety control circuit for a neutronic reactor  

    DOE Patents (OSTI)

    A neutronic reactor comprising an active portion containing material fissionable by neutrons of thermal energy, means to control a neutronic chain reaction within the reactor comprising a safety device and a regulating device, a safety device including means defining a vertical channel extending into the reactor from an aperture in the upper surface of the reactor, a rod containing neutron-absorbing materials slidably disposed within the channel, means for maintaining the safety rod in a withdrawn position relative to the active portion of the reactor including means for releasing said rod on actuation thereof, a hopper mounted above the active portion of the reactor having a door disposed at the bottom of the hopper opening into the vertical channel, a plurality of bodies of neutron-absorbing materials disposed within the hopper, and means responsive to the failure of the safety rod on actuation thereof to enter the active portion of the reactor for opening the door in the hopper.

    Ellsworth, Howard C. (Richland, WA)

    2004-04-27T23:59:59.000Z

    436

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

    SciTech Connect

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

    Borsheim, G.L.

    1993-09-01T23:59:59.000Z

    437

    Pipeline Safety (Maryland)  

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

    The Public Service Commission has the authority enact regulations pertaining to pipeline safety. These regulations address pipeline monitoring, inspections, enforcement, and penalties.

    438

    Lift truck safety review  

    SciTech Connect

    This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter`s Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given.

    Cadwallader, L.C.

    1997-03-01T23:59:59.000Z

    439

    Nuclear Safety Information Dashboard  

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

    provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into...

    440

    FACILITY SAFETY (FS)  

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

    - (Core Requirement 1) Line management has established a QA program to ensure safe accomplishment of work. Personnel exhibit an awareness of public and worker safety, health, and...

    Note: This page contains sample records for the topic "include plant safety" 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

    SSRL Safety Office Memo  

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

    Safety Office SSO 012406 Memo to SSRL staff concerning operation of Circuit Breakers and Disconnect Switches Recently SLAC has adopted new regulations (NFPA70E) which outline the...

    442

    Safety Training - Cyclotron  

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

    Safety Training GERT All experimenters at the 88-Inch Cyclotron are required to take the General Employee Radiation Training (GERT) course, which can be found here: GERT Building...

    443

    Dam Safety Program (Florida)  

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

    Dam safety in Florida is a shared responsibility among the Florida Department of Environmental Protection (FDEP), the regional water management districts, the United States Army Corps of Engineers ...

    444

    Coiled Tubing Safety Manual  

    SciTech Connect

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

    Crow, W.

    1999-04-06T23:59:59.000Z

    445

    Public Safety Network Requirements  

    Science Conference Proceedings (OSTI)

    ... Usage scenario. ... imposed by public safety applications and usage scenarios is key in ... requirements as shown in Figure 2. This analysis was used as ...

    2010-10-05T23:59:59.000Z

    446

    Pipeline Safety (South Dakota)  

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

    The South Dakota Pipeline Safety Program, administered by the Public Utilities Commission, is responsible for regulating hazardous gas intrastate pipelines. Relevant legislation and regulations...

    447

    2003 Kansas City Plant Annual Illness and Injury Surveillance Report, Revised September 2007  

    SciTech Connect

    Annual Illness and Injury Surveillance Program report for 2003 for the Kansas City Plant. The U.S. Department of Energy’s (DOE) commitment to assuring the health and safety of its workers includes the conduct of epidemiologic surveillance activities that provide an early warning system for health problems among workers. The IISP monitors illnesses and health conditions that result in an absence of workdays, occupational injuries and illnesses, and disabilities and deaths among current workers.

    U.S. Department of Energy, Office of Health, Safety and Security, Office of Illness and Injury Prevention Programs

    2007-10-04T23:59:59.000Z

    448

    2003 Pantex Plant Annual Illness and Injury Surveillance Report, Revised September 2007  

    Science Conference Proceedings (OSTI)

    Annual Illness and Injury Surveillance Program report for 2003 for the Pantex Plant. DOE is commited to assuring the health and safety of its workers. This includes the conduct of epidemiologic surveillance activities that provide an early warning system for health problems among workers. The IISP monitors illnesses and health conditions that result in an absence of workdays, occupational injuries and illnesses, and disabilities and deaths among current workers.

    U.S. Department of Energy, Office of Health, Safety and Security, Office of Illness and Injury Prevention Programs

    2007-10-05T23:59:59.000Z

    449

    AVESTAR Center for Operational Excellence of Electricity Generation Plants  

    Science Conference Proceedings (OSTI)

    To address industry challenges in attaining operational excellence for electricity generation plants, the U.S. Department of Energy’s (DOE) National Energy Technology Laboratory (NETL) has launched a world-class facility for Advanced Virtual Energy Simulation Training and Research (AVESTARTM). This presentation will highlight the AVESTARTM Center simulators, facilities, and comprehensive training, education, and research programs focused on the operation and control of high-efficiency, near-zero-emission electricity generation plants. The AVESTAR Center brings together state-of-the-art, real-time, high-fidelity dynamic simulators with full-scope operator training systems (OTSs) and 3D virtual immersive training systems (ITSs) into an integrated energy plant and control room environment. AVESTAR’s initial offering combines--for the first time--a “gasification with CO2 capture” process simulator with a “combined-cycle” power simulator together in a single OTS/ITS solution for an integrated gasification combined cycle (IGCC) power plant with carbon dioxide (CO2) capture. IGCC systems are an attractive technology option for power generation, especially when capturing and storing CO2 is necessary to satisfy emission targets. The AVESTAR training program offers a variety of courses that merge classroom learning, simulator-based OTS learning in a control-room operations environment, and immersive learning in the interactive 3D virtual plant environment or ITS. All of the courses introduce trainees to base-load plant operation, control, startups, and shutdowns. Advanced courses require participants to become familiar with coordinated control, fuel switching, power-demand load shedding, and load following, as well as to problem solve equipment and process malfunctions. Designed to ensure work force development, training is offered for control room and plant field operators, as well as engineers and managers. Such comprehensive simulator-based instruction allows for realistic training without compromising worker, equipment, and environmental safety. It also better prepares operators and engineers to manage the plant closer to economic constraints while minimizing or avoiding the impact of any potentially harmful, wasteful, or inefficient events. The AVESTAR Center is also used to augment graduate and undergraduate engineering education in the areas of process simulation, dynamics, control, and safety. Students and researchers gain hands-on simulator-based training experience and learn how the commercial-scale power plants respond dynamically to changes in manipulated inputs, such as coal feed flow rate and power demand. Students also analyze how the regulatory control system impacts power plant performance and stability. In addition, students practice start-up, shutdown, and malfunction scenarios. The 3D virtual ITSs are used for plant familiarization, walk-through, equipment animations, and safety scenarios. To further leverage the AVESTAR facilities and simulators, NETL and its university partners are pursuing an innovative and collaborative R&D program. In the area of process control, AVESTAR researchers are developing enhanced strategies for regulatory control and coordinated plant-wide control, including gasifier and gas turbine lead, as well as advanced process control using model predictive control (MPC) techniques. Other AVESTAR R&D focus areas include high-fidelity equipment modeling using partial differential equations, dynamic reduced order modeling, optimal sensor placement, 3D virtual plant simulation, and modern grid. NETL and its partners plan to continue building the AVESTAR portfolio of dynamic simulators, immersive training systems, and advanced research capabilities to satisfy industry’s growing need for training and experience with the operation and control of clean energy plants. Future dynamic simulators under development include natural gas combined cycle (NGCC) and supercritical pulverized coal (SCPC) plants with post-combustion CO2 capture. These dynamic simulators are targeted for us

    Zitney, Stephen

    2012-08-29T23:59:59.000Z

    450

    Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement  

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

    Facts and Lessons of the Fukushima Nuclear Accident and Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints September 19, 2012 Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company Topics Covered: How Tsunami Struck Fukushima Sites Tsunami Height Estimation How we responded in the Recovery Process Safety Improvement and Further Enhancement of Nuclear Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints More Documents & Publications January2005 NNSANews Meeting Materials: June 15, 2011

    451

    Safety of Decommissioning of Nuclear Facilities  

    Science Conference Proceedings (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

    452

    ALMR plant design and performance  

    SciTech Connect

    The advanced liquid-metal reactor (ALMR) plant, sponsored by the US Department of Energy and being developed by a General Electric Company lead industrial team, features simple and reliable safety systems, seismic isolation, passive decay heat removal, passive reactivity control, and substantial margins to structural and fuel damage limits during potential accident situations. These features will result in significant gains for public safety and protection of the owner's investment. Standardized modular construction and extensive factory fabrication will result in a plant design that is economically competitive. The reference commercial ALMR plant utilizes nine reactor modules arranged in three identical 480-MW(electric) power blocks for an overall plant net electrical rating of 1440 MW(electric). Each power block features three identical reactor modules, each with its own steam generator, that jointly supply power to a single turbine generator.

    Kwant, W.; Boardman, C.E.; Dayal, Y.; Magee, P.M. (GE Nuclear Energy, San Jose, CA (United States))

    1992-01-01T23:59:59.000Z

    453

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

    SciTech Connect

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

    Bari, R.A.

    1992-10-01T23:59:59.000Z

    454

    Tutorial on nuclear thermal propulsion safety for Mars  

    DOE Green Energy (OSTI)

    Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

    Buden, D.

    1992-01-01T23:59:59.000Z

    455

    Tutorial on nuclear thermal propulsion safety for Mars  

    DOE Green Energy (OSTI)

    Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

    Buden, D.

    1992-08-01T23:59:59.000Z

    456

    DOE/EM Criticality Safety Needs Assessment  

    SciTech Connect

    The issue of nuclear criticality safety (NCS) in Department of Energy Environmental Management (DOE/EM) fissionable material operations presents challenges because of the large quantities of material present in the facilities and equipment that are committed to storage and/or material conditioning and dispositioning processes. Given the uncertainty associated with the material and conditions for many DOE/EM fissionable material operations, ensuring safety while maintaining operational efficiency requires the application of the most-effective criticality safety practices. In turn, more-efficient implementation of these practices can be achieved if the best NCS technologies are utilized. In 2002, DOE/EM-1 commissioned a survey of criticality safety technical needs at the major EM sites. These needs were documented in the report Analysis of Nuclear Criticality Safety Technology Supporting the Environmental Management Program, issued May 2002. Subsequent to this study, EM safety management personnel made a commitment to applying the best and latest criticality safety technology, as described by the DOE Nuclear Criticality Safety Program (NCSP). Over the past 7 years, this commitment has enabled the transfer of several new technologies to EM operations. In 2008, it was decided to broaden the basis of the EM NCS needs assessment to include not only current needs for technologies but also NCS operational areas with potential for improvements in controls, analysis, and regulations. A series of NCS workshops has been conducted over the past years, and needs have been identified and addressed by EM staff and contractor personnel. These workshops were organized and conducted by the EM Criticality Safety Program Manager with administrative and technical support by staff at Oak Ridge National Laboratory (ORNL). This report records the progress made in identifying the needs, determining the approaches for addressing these needs, and assimilating new NCS technologies into EM fissionable material operations. In addition, the report includes projections of future EM needs and associted recommendations.

    Westfall, Robert Michael [ORNL; Hopper, Calvin Mitchell [ORNL

    2011-02-01T23:59:59.000Z

    457

    Independent Oversight Review, Portsmouth Gaseous Diffusion Plant -  

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

    Portsmouth Gaseous Diffusion Plant Portsmouth Gaseous Diffusion Plant - November 2013 Independent Oversight Review, Portsmouth Gaseous Diffusion Plant - November 2013 November 5, 2013 Review of Preparedness for Severe Natural Phenomena Events at the Portsmouth Gaseous Diffusion Plant This report documents the results of an independent oversight review of the preparedness of the DOE Portsmouth/Paducah Project Office, contractors at the DOE Portsmouth Gaseous Diffusion Plant, and selected non-leased facilities to respond to a severe natural phenomena event (NPE). The review was conducted in July and August 2013 by the U.S. Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security (HSS). The HSS Office of Safety and Emergency Management Evaluations performed this

    458

    Seismic Safety Margins Research Program (Phase I). Project IV. Structural building response; Structural Building Response Review  

    Science Conference Proceedings (OSTI)

    As part of the Phase I effort of the Seismic Safety Margins Research Program (SSMRP) being performed by the University of California Lawrence Livermore Laboratory for the US Nuclear Regulatory Commission, the basic objective of Subtask IV.1 (Structural Building Response Review) is to review and summarize current methods and data pertaining to seismic response calculations particularly as they relate to the objectives of the SSMRP. This material forms one component in the development of the overall computational methodology involving state of the art computations including explicit consideration of uncertainty and aimed at ultimately deriving estimates of the probability of radioactive releases due to seismic effects on nuclear power plant facilities.

    Healey, J.J.; Wu, S.T.; Murga, M.

    1980-02-01T23:59:59.000Z

    459

    The Office of Health, Safety and Security  

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

    8 8 2008 BY MONTH: JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC This list last updated Tuesday, April 02, 2013 DECEMBER December 22, 2008, Departmental letter regarding the completion of Commitments 5.2.1, 5.2.2, 5.2.3, and 5.5.2 in the Implementation Plan for Board Recommendation 2007-01. [HTML] [PDF] [DOC] December 22, 2008, Departmental letter forwarding the Safety Software Central Registry and Communications Portal Management Plan. [HTML] [PDF] [DOC] December 16, 2008, Board letter closing Recommendation 98-2, Accelerating Safety Management Improvements at the Pantex Plant, and establishing a 60-day reporting requirement for an evaluation of the disposition of findings from NES Studies, NES Change Evaluations, and Operational Safety Reviews from 2003 through 2008 [HTML] [PDF] [DOC]

    460

    Nuclear Safety Enforcement Documents | Department of Energy  

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

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

    Note: This page contains sample records for the topic "include plant safety" 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

    The color of safety  

    Science Conference Proceedings (OSTI)

    The industry's workforce is getting grayer as veteran miners approach retirement, and greener as new hires come onboard. Will the changing complexion of the industry affect future safety technology? The article discusses problems of noise, vibration, and communication faced by coal miners and reports some developments by manufacturers of mining equipment to improve health and safety. 1 fig., 4 photos.

    Carter, R.A.

    2006-06-15T23:59:59.000Z