Powered by Deep Web Technologies
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.


1

Maintaining plant safety margins  

SciTech Connect (OSTI)

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

B PLANT DOCUMENTED SAFETY ANALYSIS  

SciTech Connect (OSTI)

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

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

2003-08-01T23:59:59.000Z

3

Safety First Safety Last Safety Always Aerial lifts include the following types of vehicle-mounted  

E-Print Network [OSTI]

Safety First Safety Last Safety Always Aerial lifts include the following types of vehicle, if they can be installed safely. Aerial Lifts Safety Tip #11 A spill, a slip, a hospital trip #12;Additional Information for Presenters Review the information provided on the reverse side of this safety tip sheet

Minnesota, University of

4

Safety First Safety Last Safety Always Personal fall-protection systems include a body harness (safe-  

E-Print Network [OSTI]

Safety First Safety Last Safety Always Personal fall-protection systems include a body harness so they will not be damaged. Personal Fall-Protection Systems Safety Tip #8 Just because you always;Additional Information for Presenters Review the information provided on the reverse side of this safety tip

Minnesota, University of

5

Plutonium Finishing Plant safety evaluation report  

SciTech Connect (OSTI)

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

Not Available

1995-01-01T23:59:59.000Z

6

Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches  

SciTech Connect (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

7

Improving the safety of LWR power plants. Final report  

SciTech Connect (OSTI)

This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs (improving or maintaining level of safety with simpler systems or in a more cost-effective manner).

Not Available

1980-04-01T23:59:59.000Z

8

Hanford Plant Closed Over Safety Violation  

Science Journals Connector (OSTI)

...421-a ELIOT MARSHALL Hanford plant closed over...conducting a highly public campaign for his...curriculum fell short of meeting his standards. 24...m JOHN WALSH Hanford Plant Closed Over...Violation Concern for public safety prompted the...least until the year 2000. Since there is...

ELIOT MARSHALL

1986-10-24T23:59:59.000Z

9

Waste Isolation Pilot Plant Safety Analysis Report  

SciTech Connect (OSTI)

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

NONE

1995-11-01T23:59:59.000Z

10

Plutonium finishing plant safety systems and equipment list  

SciTech Connect (OSTI)

The Safety Equipment List (SEL) supports Analysis Report (FSAR), WHC-SD-CP-SAR-021 and the Plutonium Finishing Plant Operational Safety Requirements (OSRs), WHC-SD-CP-OSR-010. The SEL is a breakdown and classification of all Safety Class 1, 2, and 3 equipment, components, or system at the Plutonium Finishing Plant complex.

Bergquist, G.G.

1995-01-06T23:59:59.000Z

11

Safety system augmentation at Russian nuclear power plants  

SciTech Connect (OSTI)

This paper describes the design and procurement of a Class IE DC power supply system to upgrade plant safety at the Kola Nuclear Power Plant (NPP). Kola NPP is located above the Arctic circle at Polyarnie Zorie, Murmansk, Russia. Kola NPP consists of four units. Units 1 and 2 have VVER-440/230 type reactors: Units 3 and 4 have VVER-440/213 type reactors. The VVER-440 reactor design is similar to the pressurized water reactor design used in the US. This project provided redundant, Class 1E DC station batteries and DC switchboards for Kola NPP, Units 1 and 2. The new DC power supply system was designed and procured in compliance with current nuclear design practices and requirements. Technical issues that needed to be addressed included reconciling the requirements in both US and Russian codes and satisfying the requirements of the Russian nuclear regulatory authority. Close interface with ATOMENERGOPROEKT (AEP), the Russian design organization, KOLA NPP plant personnel, and GOSATOMNADZOR (GAN), the Russian version of US Nuclear Regulatory Commission, was necessary to develop a design that would assure compliance with current Russian design requirements. Hence, this project was expected to serve as an example for plant upgrades at other similar VVER-440 nuclear plants. In addition to technical issues, the project needed to address language barriers and the logistics of shipping equipment to a remote section of the Former Soviet Union (FSU). This project was executed by Burns and Roe under the sponsorship of the US DOE as part of the International Safety Program (INSP). The INSP is a comprehensive effort, in cooperation with partners in other countries, to improve nuclear safety worldwide. A major element within the INSP is the improvement of the safety of Soviet-designed nuclear reactors.

Scerbo, J.A.; Satpute, S.N.; Donkin, J.Y.; Reister, R.A. [Burns and Roe, Oradell, NJ (United States); [Department of Energy, Germantown, MD (United States)

1996-12-31T23:59:59.000Z

12

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

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

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

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

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

14

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

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

15

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

SciTech Connect (OSTI)

This Safety Evaluation Report (SER) documents the Department of 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

16

Rockwell International's Nuclear Criticality Safety Program at the Rocky Flats Plant  

SciTech Connect (OSTI)

This paper describes the criticality safety program at the Rocky Flats Plant. The groups responsible for safety are named and their functions outlined. (JDH)

McCarthy, J.D.

1987-01-01T23:59:59.000Z

17

Entomology Department safety training for new employees Anyone who works in a laboratory (including the Bohart Museum)  

E-Print Network [OSTI]

Entomology Department safety training for new employees Anyone who works in a laboratory (including safety manager of the space in which the employee is working. This includes required PPE. 3. Employees the Bohart Museum) 1. General training a. Employee completes the online UC Laboratory Safety Fundamentals

Ishida, Yuko

18

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

SciTech Connect (OSTI)

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

19

Safety Evaluation for Packaging (onsite) T Plant Canyon Items  

SciTech Connect (OSTI)

This safety evaluation for packaging (SEP) evaluates and documents the ability to safely ship mostly unique inventories of miscellaneous T Plant canyon waste items (T-P Items) encountered during the canyon deck clean off campaign. In addition, this SEP addresses contaminated items and material that may be shipped in a strong tight package (STP). The shipments meet the criteria for onsite shipments as specified by Fluor Hanford in HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments.

OBRIEN, J.H.

2000-07-14T23:59:59.000Z

20

Dynamical safety assessment of hydrogen production nuclear power plants using system dynamics method  

Science Journals Connector (OSTI)

Nuclear power plants for hydrogen production are investigated in the aspect of nuclear safety. The non-linear dynamical safety assessment is introduced for the analysis of the high temperature gas cooled reactor (HTGR) which is used for hydrogen production as well as electricity generation. The dynamical algorithm is adjusted for the safety assessment with an easier and reliable output. A feedback of power increase affects to the temperature decrease. The top event of the event is power and temperature stable. It is affected by the human factor, poison, and some other physical variables. There are several factors including the economic and safety factors which are considered for the reliability of the modelling simulations. Using the system dynamics (SD) method, the event quantification is performed for the event flows, stocks, and feedback by the single and double arrow lines.

Taeho Woo; Soonho Lee

2013-01-01T23:59:59.000Z

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.


21

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  

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

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  

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

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

A HIRARC model for safety and risk evaluation at a hydroelectric power generation plant  

Science Journals Connector (OSTI)

Abstract There are many formal techniques for the systematic analysis of occupational safety and health in general, and risk analysis in particular, for power generation plants at hydroelectric power stations. This study was initiated in order to create a HIRARC model for the evaluation of environmental safety and health at a hydroelectric power generation plant at Cameron Highlands in Pahang, Malaysia. The HIRARC model was used to identify the primary and secondary hazards which may be inherent in the system which were determined as a serious threat for plant operation and maintenance. The primary tools of the model consisted of, generic check-lists, work place inspection schemes which included task observation and interview, safety analysis as well as accident and incident investigation. For risk assessment, the Likert scale was complemented by the severity matrix analysis in order to determine the probability and extent of safety and health at the study power generation plant. These were used to identify and recommend control measures which included engineering and administrative aspects as well as the use of personal protective equipment (PPE). A total of forty-one important hazard items were identified in the system at target power generation plant. These hazards were mainly identified by means of checklists which were sourced from literature and subsequently customized for the current purpose. Risk assessment was conducted by initially classifying the hazards into three levels such as Low, Medium and High. Generally 66% of the hazards identified were at low risk, 32% at medium and 2% at high risk. This indicated that there was sufficient awareness and commitment to safety and health at the study power station. Meanwhile the Power Station was also certified by MS 1722:2005, OHSAS 18001, MS ISO 14001:2004, MS ISO 9001:2000 and scheduled waste regulation 2005 which give credibility to the current study in creating a working model which may find widespread application in the future.

A.M. Saedi; J.J. Thambirajah; Agamuthu Pariatamby

2014-01-01T23:59:59.000Z

24

Floating LNG plant will stress reliability and safety  

SciTech Connect (OSTI)

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

25

Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues. Supplement 3  

SciTech Connect (OSTI)

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ``A Prioritization of Generic Safety Issues,`` which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees.

Not Available

1993-12-01T23:59:59.000Z

26

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 +

27

Alternative off-site power supply improves nuclear power plant safety  

Science Journals Connector (OSTI)

Abstract A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source.

Blaže Gjorgiev; Andrija Volkanovski; Duško Kan?ev; Marko ?epin

2014-01-01T23:59:59.000Z

28

A model for the preventive maintenance scheduling of power plants including wind farms  

Science Journals Connector (OSTI)

Abstract This paper considers the problem of Power Plant Preventive Maintenance Scheduling (PPPMS). The goal is to evaluate which generators must stop production to be checked periodically for safety reasons. Preventive maintenance is crucial because a failure in a power plant may cause a general breakdown in an electric grid. This situation might result in a disruption of electric service to customers. The objective is to perform the problem of PPPMS from a reliability perspective, so the reliability of the system is maximized. The model presented considers the integration of wind power plants or wind farms into a traditional electric generating system comprising thermal, hydroelectric, and nuclear power units. The resulting model is categorized as an optimization problem. A case study based on a real power system is presented. Its main objective is to validate the efficiency of the proposed analysis.

Salvador Perez-Canto; Juan Carlos Rubio-Romero

2013-01-01T23:59:59.000Z

29

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

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

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

30

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  

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

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

31

Enhancing fire safety at Hydro plants with dry transformers  

SciTech Connect (OSTI)

Hydroelectric plant owners and engineers can use dry-type transformers to reduce fire hazards in auxiliary power systems. The decision to replace a liquid-immersed transformer with a dry-type product has a price: higher unit cost and a need to be more vigilant in detailing transformer specifications. But, whether the change affects only one failed transformer or is part of a plant rehabilitation project, the benefits in safety can be worth it. Voltages on hydroelectric plant auxiliary power systems can range from a 20 kV medium-voltage system to the normal 480-208/120 V low-voltage system. Dry transformers typically are used in such systems to reduce the fire hazard present with liquid-filled transformers. For a hydro plant owner or engineer seeking alternatives to liquid-filled transformers, there are two main kinds of dry-type transformers to consider: vacuum pressure impregnated (VPI) and cast coil epoxy resin. VPI transformers normally are manufactured in sizes up to 6,000 kVA with primary voltage ratings up to 20 kV. Cast coil transformers can be made in sizes from 75 to 10,000 kVA, with primary voltage ratings up to 34,500 V. Although the same transformer theory applies to dry transformers as to liquid-filled units, the cooling medium, air, required different temperature rise ratings, dielectric tests, and construction techniques to ensure reliability. Consequently, the factory and field tests for dry units are established by a separate set of American National Standards Institute (ANSI)/Institute of Electrical and Electronics Engineers (IEEE) standards. Cast coil transformers have several important advantages over VPI units.

Clemen, D.M. (Harza Engineering Company, Chicago, IL (United States))

1993-06-01T23:59:59.000Z

32

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

33

An approach for solvent selection in extractive distillation systems including safety considerations  

E-Print Network [OSTI]

Chemical Engineering Department, Instituto Tecnológico de Celaya, Celaya, GTO 38060 México 2 Chemical Engineering, Texas A&M University, College Station, TX 77843 and The Mary Kay O'Connor Process Safety Center implications that a given solvent generates for the process, are generally left for their consideration after

Grossmann, Ignacio E.

34

Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant  

SciTech Connect (OSTI)

This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested.

Sheaffer, M.K.; Keeton, S.C.

1993-09-20T23:59:59.000Z

35

ANNUAL SAFETY REFRESHER TRAINING FOR LABORATORY EMPLOYEES IN THE DEPT OF PLANT PATHOLOGY & NEMATOLOGY  

E-Print Network [OSTI]

practices. Chemical storage & handling [including transport]. (SafetyNet #42) Flammables Corrosives, and emergency measures for your workplace. 3. Follow all rules, safety guidelines and established safe work(s) noted. SafetyNet #66 General Earthquake Safety, Bomb Threat, and Disaster Procedures Chemical spill kits

Ferrara, Katherine W.

36

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010  

Broader source: Energy.gov [DOE]

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010

37

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

SciTech Connect (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

38

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

Science Journals Connector (OSTI)

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

Julwan Hendry Purba; Jie Lu; Guangquan Zhang

2012-01-01T23:59:59.000Z

39

PLC-Based Safety Critical Software Development for Nuclear Power Plants  

E-Print Network [OSTI]

PLC-Based Safety Critical Software Development for Nuclear Power Plants Junbeom Yoo1 , Sungdeok Cha}@kaeri.re.kr Abstract. This paper proposes a PLC(Programmable Logic Controller)-based safety critical software(FBD), a widely used PLC programming language. Finally, we manually refine the FBD programs so that redundant

40

Including radiative heat transfer and reaction quenching in modeling a Claus plant waste heat boiler  

SciTech Connect (OSTI)

Due to increasingly stringent sulfur emission regulations, improvements are necessary in the modified Claus process. A recently proposed model by Nasato et al. for the Claus plant waste heat boiler (WHB) is improved by including radiative heat transfer, which yields significant changes in the predicted heat flux and the temperature profile along the WHB tube, leading to a faster quenching of chemical reactions. For the WHB considered, radiation accounts for approximately 20% of the heat transferred by convection alone. More importantly, operating the WHB at a higher gas mass flux is shown to enhance reaction quenching, resulting in a doubling of the predicted hydrogen flow rate. This increase in hydrogen flow rate is sufficient to completely meet the hydrogen requirement of the H[sub 2]S recovery process considered, which would eliminate the need for a hydrogen plant.

Karan, K.; Mehrotra, A.K.; Behie, L.A. (Univ. of Calgary, Alberta (Canada). Dept. of Chemical and Petroleum Engineering)

1994-11-01T23:59:59.000Z

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.


41

Technical safety appraisal: Buildings 776/777 Rocky Flats Plant  

SciTech Connect (OSTI)

Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted.

Field, H C

1988-03-01T23:59:59.000Z

42

Safety provisions for UF{sub 6} handling in the design of a new UF{sub 6} conversion plant  

SciTech Connect (OSTI)

British Nuclear Fuels plc (BNFL) Fuel Division is currently undertaking the final design and construction of a new UF{sub 6} conversion plant at its production site at Springfields near Preston in the north of England. The Company has gained much experience in the handling of UF{sub 6} during operation of plants on site since 1961. The major hazard occurs during the liquefication cycle and the basis of the maximum credible incident scenario adopted for safety assessment and design purposes is discussed. This paper considers the design features which have been incorporated in the new plant to counter the hazards presented by the presence of UF{sub 6} in gaseous and liquid form and explains current thinking on operational procedures in areas of potential risk such as cylinder filling. The plant emergency response philosophy and systems are described and specific design provisions which have been included to satisfy the UK regulatory bodies are outlined in some detail.

Bannister, S.P. [British Nuclear Fuels plc, Preston (United Kingdom)

1991-12-31T23:59:59.000Z

43

Worker Involvement Improves Safety at Hanford Site's Plutonium Finishing Plant  

Broader source: Energy.gov [DOE]

Employees at the Hanford site are working together to find new and innovative ways to stay safe at the Plutonium Finishing Plant, one of the site’s most complex decommissioning projects.

44

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

45

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

SciTech Connect (OSTI)

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

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

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

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

47

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

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

48

An assessment of criticality safety at the Department of Energy Rocky Flats Plant, Golden, Colorado, July--September 1989  

SciTech Connect (OSTI)

This is a report on the 1989 independent Criticality Safety Assessment of the Rocky Flats Plant, primarily in response to public concerns that nuclear criticality accidents involving plutonium may have occurred at this nuclear weapon component fabrication and processing plant. The report evaluates environmental issues, fissile material storage practices, ventilation system problem areas, and criticality safety practices. While no evidence of a criticality accident was found, several recommendations are made for criticality safety improvements. 9 tabs.

Not Available

1989-09-01T23:59:59.000Z

49

Economical load distribution in power networks that include hybrid solar power plants  

Science Journals Connector (OSTI)

With respect to the growing share of renewable resources in secure provision of electrical energy, proper utilization of hybrid power plants is of great importance. Therefore, an optimal production planning for operation of these power plants is evidently necessary. Generally, economical load distribution refers to determination of an optimal point in production that fully provides for the total network load. In other words, the economical load distribution refers to cost minimization of the produced electrical power for satisfying the total network demand, with consideration of the actual constraints in the power system. To serve this purpose, several methods have been in use, but with the entry of power plants that use renewable energy resources, necessary steps should be taken to ensure their optimal use. However, economical optimization and sufficient reliability in serving concurrent demands are the two-fold objectives of the electrical power system and need to be considered simultaneously. Therefore, in analyzing the share of renewable energy resources in the total electrical power network, both their economical advantages and their reliable level of production should be considered. Presently, many countries show interest in using hybrid solar power plants and fossil fuel power plants. In this research, the problem of augmenting power networks with solar power plants and finding their optimal production point is dealt with. Some models for the production cost functions of these power plants are presented and discussed.

Mohammad Taghi Ameli; Saeid Moslehpour; Mehdi Shamlo

2008-01-01T23:59:59.000Z

50

Overview of imporved criticality safety limits at the Rocky Flats plant  

SciTech Connect (OSTI)

This paper provides an overview of improved criticality safety limits developed for nuclear operations at the Rocky Flats plant. A concern that some limits were ambiguous and too complex has been resolved by involving the process operators (addressing human factors) in the limit development process. In the summer of 1989, there was a public concern that a criticality accident may have occurred and gone undetected at the Rocky Flats plant near Golden, Colorado. To resolve this concern, the US Department of Energy (DOE) asked Scientech, Inc., to assemble an independent review team and assess the concern. The Scientech team concluded that there was no indication that a criticality accident had ever occurred at the Rocky Flats plant. However, the team did identify inadequate safety conditions and practices and recommended corrective actions.

Grethel, T.E.; Moon, N.A. (Department of Energy, Golden, CO (United States)); Brown, C.L. (M.H. Chew Associates, Inc., Golden, CO (United States))

1993-01-01T23:59:59.000Z

51

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

SciTech Connect (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

52

Assessment of enriched uranium storage safety issues at the Oak Ridge Y-12 Plant  

SciTech Connect (OSTI)

This document is an assessment of the technical safety issues pertaining to the storage of EU at the Oak Ridge Y-12 Plant. The purpose of the assessment is to serve as the basis for defining the technical standards for storage of EU at Y-12. A formal assessment of the Y-12 materials acceptance criteria for EU is currently being conducted by a task force cochaired by B. G. Eddy of DOE Oak Ridge Operations and S. 0. Cox of Y-12 Defense Programs. The mission of this technical assessment for storage is obviously dependent on results of the acceptance assessment. Clearly, the two efforts require coordination to avoid inconsistencies. In addition, both these Assessments must be consistent with the Environmental Assessment for EU storage at Y-12.1 Both the Storage Assessment and the Criteria for Acceptance must take cognizance of the fact that a portion of the EU to be submitted for storage in the future is expected to be derived from foreign sources and to include previously irradiated uranium containing significant levels of transuranics, radioactive daughter products, and unstable uranium isotopes that do not occur in the EU stream of the DOE weapons complex. National security considerations may dictate that these materials be accepted despite the fact that they fail to conform to the Acceptance Criteria. This document will attempt to address the complexities inherent in this situation.

NONE

1996-08-01T23:59:59.000Z

53

Plants as Sources of Airborne Bacteria, Including Ice Nucleation-Active Bacteria  

Science Journals Connector (OSTI)

...allowed much greater exposure of the soil to wind than the dense, 0.9- m-high wheat canopy. Since wind speeds de- crease rapidly with depth in a dense plant cano- py, very little wind energy, if any, would have been available to...

Julianne Lindemann; Helen A. Constantinidou; William R. Barchet; Christen D. Upper

1982-11-01T23:59:59.000Z

54

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

SciTech Connect (OSTI)

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

55

Summary and bibliography of safety-related events at pressurized-water nuclear power plants as reported in 1979  

SciTech Connect (OSTI)

This report summarizes the data contained in reports submitted by licensees to the US Nuclear Regulatory Commission concerning safety-related operational events that occurred at pressurized-water-reactor nuclear power plants in 1979. A bibliography containing 100-word abstracts of the event reports is included. The 2064 abstracts included in the bibliography describe incidents, failures, and design or construction deficiencies experienced at the facilities. They are arranged alphabetically by reactor name and then chronologically for each reactor. Keyword and permuted-title indexes are provided to facilitate location of the abstracts of interest. Tables summarizing the information contained in the bibliography are also presented and discussed. Information listed in the tables includes instrument failures, equipment failures, system failures, causes of failures, deficiencies noted, and time of occurrence (i.e., during refueling, operation, testing, or construction). Some of the more interesting events that occurred during the year are reviewed in detail. 33 refs.

Scott, R.L.; Gallaher, R.B.

1981-07-01T23:59:59.000Z

56

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

SciTech Connect (OSTI)

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

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

1991-12-31T23:59:59.000Z

57

The EOP Visualization Module Integrated into the Plasma On-Line Nuclear Power Plant Safety Monitoring and Assessment System  

SciTech Connect (OSTI)

An ambitious project to replace the unit information systems (UISs) at the Hungarian Paks nuclear power plant was started in 1998-99. The basic aim of the reconstruction project is to install a modern, distributed UIS architecture on all four Paks VVER-440 units. The new UIS includes an on-line plant safety monitoring and assessment system (PLASMA), which contains a critical safety functions monitoring module and provides extensive operator support during the execution of the new, symptom-oriented emergency operating procedures (EOPs). PLASMA includes a comprehensive EOP visualization module, based on the COPMA-III procedure-handling software developed by the Organization for Economic Cooperation and Development, Halden Reactor Project. Intranet technology is applied for the presentation of the EOPs with the use of a standard hypertext markup language (HTML) browser as a visualization tool. The basic design characteristics of the system, with a detailed description of its user interface and functions of the new EOP display module, are presented.

Hornaes, Arne [Organization for Economic Cooperation and Development (France); Hulsund, John Einar [Organization for Economic Cooperation and Development (France); Vegh, Janos [KFKI Atomic Energy Research Institute (Hungary); Major, Csaba [KFKI Atomic Energy Research Institute (Hungary); Horvath, Csaba [KFKI Atomic Energy Research Institute (Hungary); Lipcsei, Sandor [KFKI Atomic Energy Research Institute (Hungary); Kapocs, Gyoergy [Paks Nuclear Power Plant Ltd. (Hungary)

2001-08-15T23:59:59.000Z

58

Cognitive decision errors and organization vulnerabilities in nuclear power plant safety management: Modeling using the TOGA meta-theory framework  

SciTech Connect (OSTI)

In the field of nuclear power plant (NPP) safety modeling, the perception of the role of socio-cognitive engineering (SCE) is continuously increasing. Today, the focus is especially on the identification of human and organization decisional errors caused by operators and managers under high-risk conditions, as evident by analyzing reports on nuclear incidents occurred in the past. At present, the engineering and social safety requirements need to enlarge their domain of interest in such a way to include all possible losses generating events that could be the consequences of an abnormal state of a NPP. Socio-cognitive modeling of Integrated Nuclear Safety Management (INSM) using the TOGA meta-theory has been discussed during the ICCAP 2011 Conference. In this paper, more detailed aspects of the cognitive decision-making and its possible human errors and organizational vulnerability are presented. The formal TOGA-based network model for cognitive decision-making enables to indicate and analyze nodes and arcs in which plant operators and managers errors may appear. The TOGA's multi-level IPK (Information, Preferences, Knowledge) model of abstract intelligent agents (AIAs) is applied. In the NPP context, super-safety approach is also discussed, by taking under consideration unexpected events and managing them from a systemic perspective. As the nature of human errors depends on the specific properties of the decision-maker and the decisional context of operation, a classification of decision-making using IPK is suggested. Several types of initial situations of decision-making useful for the diagnosis of NPP operators and managers errors are considered. The developed models can be used as a basis for applications to NPP educational or engineering simulators to be used for training the NPP executive staff. (authors)

Cappelli, M. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Gadomski, A. M. [ECONA, Centro Interuniversitario Elaborazione Cognitiva Sistemi Naturali e Artificiali, via dei Marsi 47, Rome (Italy); Sepiellis, M. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Wronikowska, M. W. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Poznan School of Social Sciences (Poland)

2012-07-01T23:59:59.000Z

59

Criticality safety evaluation of Rocky Flats Plant one-gallon shipping containers  

SciTech Connect (OSTI)

Criticality safety calculations have been performed to provide an analytical basis for handling, storage and transport of Rocky Flats Plant (RFP) one-gallon shipping containers. A mass limit was establish for metal (solid uranium or plutonium) and slurries (undissolved U or Pu solids in a ``mud,`` ``sludge,`` or ``slurry``). A separate volume limit was developed for plutonium solutions (liquids, either aqueous or organic, containing no visible undissolved solids).

Shaw, M.E.

1991-12-01T23:59:59.000Z

60

Criticality safety evaluation of Rocky Flats Plant one-gallon shipping containers  

SciTech Connect (OSTI)

Criticality safety calculations have been performed to provide an analytical basis for handling, storage and transport of Rocky Flats Plant (RFP) one-gallon shipping containers. A mass limit was establish for metal (solid uranium or plutonium) and slurries (undissolved U or Pu solids in a mud,'' sludge,'' or slurry''). A separate volume limit was developed for plutonium solutions (liquids, either aqueous or organic, containing no visible undissolved solids).

Shaw, M.E.

1991-12-01T23:59:59.000Z

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.


61

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

62

Worker Safety and Health Program for DOE (Including the National Nuclear Security Administration) Federal and Contractor Employees  

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

This document was developed to assist the Department of Energy (DOE or the Department) Federal and contractor employees in effectively developing, managing, and implementing a worker safety and health program. Cancels DOE G 440.1-1A and DOE G 440.1-8. Adm Chg 1, dated 3-22-13.

2011-10-20T23:59:59.000Z

63

Worker Safety and Health Program for DOE (Including the National Nuclear Security Administration) Federal and Contractor Employees  

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

This document was developed to assist the Department of Energy (DOE or the Department) Federal and contractor employees in effectively developing, managing, and implementing a worker safety and health program. Cancels DOE G 440.1-1A and DOE G 440.1-8. Adm Chg 1, dated 3-22-13, cancels DOE G 440.1-1B.

2011-10-20T23:59:59.000Z

64

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

SciTech Connect (OSTI)

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

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  

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

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  

SciTech Connect (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

Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant- Volume I, August 2002  

Broader source: Energy.gov [DOE]

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 discussed in Volume II of this report, and the combined results are discussed in a summary report. As discussed throughout this report, the ISM program at WIPP is generally effective. Although improvements are warranted in some areas, the current programs have contributed to overall effective ES&H performance and a good safety record at WIPP. Section 2 of this volume provides an overall discussion of the results of the review of the WIPP ES&H programs, including positive aspects and weaknesses. Section 3 provides OA’s conclusions regarding the overall effectiveness of CBFO and WTS management of the ES&H programs. Section 4 presents the ratings assigned as a result of this review. Appendix A provides supplemental information, including team composition. Appendix B identifies the specific finding that requires corrective action and follow-up. Appendix C presents the results of the review of selected guiding principles of ISM. Appendix D presents the results of the review of the CBFO and WTS feedback and continuous improvement processes. The results of the review of the application of the core functions of ISM for the selected WIPP activities are discussed in Appendix E.

68

Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA for re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)

Van Luik, Abraham; Patterson, Russell; Nelson, Roger [US Department of Energy, Carlsbad Field Office, 4021 S. National parks Highway, Carlsbad, NM 88220 (United States)] [US Department of Energy, Carlsbad Field Office, 4021 S. National parks Highway, Carlsbad, NM 88220 (United States); Leigh, Christi [Sandia National Laboratories Carlsbad Operations, 4100 S. National parks Highway, Carlsbad, NM 88220 (United States)] [Sandia National Laboratories Carlsbad Operations, 4100 S. National parks Highway, Carlsbad, NM 88220 (United States)

2013-07-01T23:59:59.000Z

69

Safety evaluation report related to Babcock and Wilcox Owners Group Plant Reassessment Program: (Final report)  

SciTech Connect (OSTI)

After the accident of Three Mile Island, Unit 2, nuclear power plant owners made a number of improvements to their nuclear facilities. Despite these improvements, the US Nuclear Regulatory Commission (NRC) staff is concerned that the number and complexity of events at Babcock and Wilcox (B and W) nuclear plants have not decreased as expected. This concern was reinforced by the June 9, 1985 total-loss-of-feedwater event at Davis-Besse Nuclear Power Station and the December 26, 1985 overcooling transient at Rancho Seco Nuclear Generating Station. By letter dated January 24, 1986, the Executive Director for Operations (EDO) informed the Chairman of the B and W Owners Group (BWOG) that a number of recent events at B and W-designed reactors have led the NRC staff to conclude that the basic requirements for B and W reactors need to be reexamined. In its February 13, 1986 response to the EDO's letter, the BWOG committed to lead an effort to define concerns relative to reducing the frequency of reactor trips and the complexity of post-trip response in B and W plants. The BWOG submitted a description of the B and W program entitled ''Safety and Performance Improvement Program'' (BAW-1919) on May 15, 1986. Five revisions to BAW-1919 have also been submitted. The NRC staff has reviewed BAW-1919 and its revisions and presents its evaluation in this report. 2 figs., 34 tabs.

Not Available

1987-11-01T23:59:59.000Z

70

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

SciTech Connect (OSTI)

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

71

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

SciTech Connect (OSTI)

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

72

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

SciTech Connect (OSTI)

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

Herborn, D.I.

1993-11-01T23:59:59.000Z

73

Regulatory analysis for the resolution of Generic Safety Issue 29: Bolting degradation or failure in nuclear power plants  

SciTech Connect (OSTI)

Generic Safety Issue (GSI)-29 deals with staff concerns about public risk due to degradation or failure of safety-related bolting in nuclear power plants. The issue was initiated in November 1982. Value-impact studies of a mandatory program on safety-related bolting for operating plants were inconclusive: therefore, additional regulatory requirements for operating plants could not be justified in accordance with provisions of 10 CFR 50.109. In addition, based on operating experience with bolting in both nuclear and conventional power plants, the actions already taken through bulletins, generic letters, and information notices, and the industry-proposed actions, the staff concluded that a sufficient technical basis exists for the resolution of GSI-29. The staff further concluded that leakage of bolted pressure joints is possible but catastrophic failure of a reactor coolant pressure boundary joint that will lead to significant accident sequences is highly unlikely. For future plants, it was concluded that a new Standard Review Plant section should be developed to codify existing bolting requirements and industry-developed initiatives. 9 refs., 1 tab.

Chang, T.Y.

1991-09-01T23:59:59.000Z

74

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

E-Print Network [OSTI]

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

75

Independent Oversight Inspection of Environment, Safety, and Health Programs at the Pantex Plant, Technical Appendices, Volume II, February 2005  

Broader source: Energy.gov [DOE]

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) containing detailed results of the OA review. Appendix C provides the results of the review of the application of the core functions of ISM for Pantex Plant work activities. Appendix D presents the results of the review of NNSA, PXSO, and BWXT feedback and continuous improvement processes and management systems. Appendix E presents the results of the review of essential safety system functionality, and Appendix F presents the results of the review of safety management of the selected focus areas.

76

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

SciTech Connect (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

77

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

SciTech Connect (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

78

Site plan safety submission for sampling, monitoring, decontamination of GB agent - north plant Rocky Mountain Arsenal. Volume 1  

SciTech Connect (OSTI)

The scope of this site plan safety submission (SPSS), includes: sampling plan to determine if GB is a contaminant in equipment and piping used in the production and demil processes; monitoring plan for personnel involved in the sampling effort; decon plan for personnel, equipment, and piping should contamination be identified. Additional sections and appendices include: historical use of bldg 1501, 1503, 1504, 1506, 1601, 1602, 1603, 1606; chemical information on GB; safety requirements; medical requirements and first aid procedures; piping drawings; rma sop's for sampling, monitoring, and decon.

Not Available

1988-10-01T23:59:59.000Z

79

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

Broader source: Energy.gov [DOE]

Presenter: Dr. Suzanne Helfinstine, Staff Engineer High Reliability Operations B&W Pantex Pantex Plant

80

The Application of Risk-Based Cost-Benefit Analysis in the Assessment of Acceptable Public Safety for Nuclear Power Plants  

Science Journals Connector (OSTI)

In 1982, the U.S. Nuclear Regulatory Commission issued, for public comment, proposed safety goals for commercial nuclear power plants. In an effort to quantitatively evaluate these proposed goals, a methodolog...

Thomas A. Morgan; Alfred J. Unione; George Sauter

1985-01-01T23:59:59.000Z

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.


81

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  

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

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

82

Safety Criticality Standards Using the French CRISTAL Code Package: Application to the AREVA NP UO{sub 2} Fuel Fabrication Plant  

SciTech Connect (OSTI)

Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical margins for all processes involving plutonium or enriched uranium. There are several criticality international standards, e.g., ARH-600, which is one the US nuclear industry relies on. The French Nuclear Safety Authority (DGSNR and its advising body IRSN) has requested AREVA NP to review the criticality standards used for the evaluation of its Low Enriched Uranium fuel fabrication plants with CRISTAL V0, the recently updated French criticality evaluation package. Criticality safety is a concern for every phase of the fabrication process including UF{sub 6} cylinder storage, UF{sub 6}-UO{sub 2} conversion, powder storage, pelletizing, rod loading, assembly fabrication, and assembly transportation. Until 2003, the accepted criticality standards were based on the French CEA work performed in the late seventies with the APOLLO1 cell/assembly computer code. APOLLO1 is a spectral code, used for evaluating the basic characteristics of fuel assemblies for reactor physics applications, which has been enhanced to perform criticality safety calculations. Throughout the years, CRISTAL, starting with APOLLO1 and MORET 3 (a 3D Monte Carlo code), has been improved to account for the growth of its qualification database and for increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating a modern basic microscopic cross section set based on JEF2.2 and the comprehensive APOLLO2 and MORET 4 codes. APOLLO2 is well suited for criticality standards calculations as it includes a sophisticated self shielding approach, a P{sub ij} flux determination, and a 1D transport (S{sub n}) process. CRISTAL V0 is the result of more than five years of development work focusing on theoretical approaches and the implementation of user-friendly graphical interfaces. Due to its comprehensive physical simulation and thanks to its broad qualification database with more than a thousand benchmark/calculation comparisons, CRISTAL V0 provides outstanding and reliable accuracy for criticality evaluations for configurations covering the entire fuel cycle (i.e. from enrichment, pellet/assembly fabrication, transportation, to fuel reprocessing). After a brief description of the calculation scheme and the physics algorithms used in this code package, results for the various fissile media encountered in a UO{sub 2} fuel fabrication plant will be detailed and discussed. (authors)

Doucet, M.; Durant Terrasson, L.; Mouton, J. [AREVA-NP (France)

2006-07-01T23:59:59.000Z

83

Nuclear power plants: structure and function  

SciTech Connect (OSTI)

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

84

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

SciTech Connect (OSTI)

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

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

1981-06-30T23:59:59.000Z

85

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

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

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

86

Structural Aging Program to evaluate continued performance of safety-related concrete structures in nuclear power plants  

SciTech Connect (OSTI)

This report discusses the Structural Aging (SAG) Program which is being conducted at the Oak Ridge National Laboratory (ORNL) for the United States Nuclear Regulatory commission (USNRC). The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. The program is organized into three technical tasks: Materials Property Data Base, Structural Component Assessment/Repair Technologies, and Quantitative Methodology for continued Service Determinations. Objectives and a summary of recent accomplishments under each of these tasks are presented.

Naus, D.J.; Oland, C.B. [Oak Ridge National Lab., TN (United States); Ellingwood, B.R. [Johns Hopkins Univ., Baltimore, MD (United States)

1994-03-01T23:59:59.000Z

87

Pilot plant investigation of N{sub 2}O emissions including the effect of long term operation in circulating FBC  

SciTech Connect (OSTI)

A pilot plant test program was conducted at CANMET to study the emissions of nitrous oxide (N{sub 2}O) from circulating fluidized bed combustors using the same coal and similar limestones as those to be used with the 165 MWe CFBC boiler owned and operated by Nova Scotia Power Incorporated (NSPI). The feedstocks examined during this trial were Devco Prince coal and the Windsor Group and Calpo limestones, the fuel and potential sorbents for NSPI`s 165 MWe CFBC plant. Twelve tests were first carried out with the first test series (TS1) using CANMET`s 0.8 MWt pilot-scale CFBC. Later, three additional tests were conducted (test series TS2), to study the effect of long term operation on the emissions of N{sub 2}O from CFBC and generate ash for an ash utilization study under a separate program. The key parameters studied were: temperature, secondary air to primary air ratio and elevation of the secondary air injection level on N{sub 2}O emissions as well as sulfur capture, combustion efficiency and NO{sub x} and CO levels. The N{sub 2}O emissions ranged from 51 to 117 ppm (or 32 to 72 mg/MJ). As expected, temperature was the dominant influence on N{sub 2}O emissions. In addition, longer term operation (80 to 100 h) had no significant effect on N{sub 2}O emissions. Despite a change in limestones and a significant change in limestone utilization, the N{sub 2}O emissions were equivalent in the two test series. Neither was any significant correlation established by way of multilinear regression between N{sub 2}O and other emissions for the two test series (i.e., SO{sub 2}, NO{sub x}, CO or O{sub 2}).

Desai, D.L.; Anthony, E.J.; Lau, I. [CANMET, Ottawa, Ontario (Canada); Andrews, N. [Nova Scotia Power Inc., Halifax, Nova Scotia (Canada)

1995-12-31T23:59:59.000Z

88

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

89

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

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

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

90

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

SciTech Connect (OSTI)

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

91

An adaptive load dispatching and forecasting strategy for a virtual power plant including renewable energy conversion units  

Science Journals Connector (OSTI)

Abstract The increasing awareness on the risky state of conventional energy sources in terms of future energy supply security and health of environment has promoted the research activities on alternative energy systems. However, due to the fact that the power production of main alternative sources such as wind and solar is directly related with meteorological conditions, these sources should be combined with dispatchable energy sources in a hybrid combination in order to ensure security of demand supply. In this study, the evaluation of such a hybrid system consisting of wind, solar, hydrogen and thermal power systems in the concept of virtual power plant strategy is realized. An economic operation-based load dispatching strategy that can interactively adapt to the real measured wind and solar power production values is proposed. The adaptation of the load dispatching algorithm is provided by the update mechanism employed in the meteorological condition forecasting algorithms provided by the combination of Empirical Mode Decomposition, Cascade-Forward Neural Network and Linear Model through a fusion strategy. Thus, the effects of the stochastic nature of solar and wind energy systems are better overcome in order to participate in the electricity market with higher benefits.

A. Tascikaraoglu; O. Erdinc; M. Uzunoglu; A. Karakas

2014-01-01T23:59:59.000Z

92

LBNL/ PUB 3000 Chapter 8 Questions on Electrical Cords 2010 Questions have been asked about electrical safety that includes extension cords,  

E-Print Network [OSTI]

LBNL/ PUB 3000 Chapter 8 ­ Questions on Electrical Cords 2010 Questions have been asked about at the lab out of Pub 3000 chapter 8 & 10 Chapter 8 ELECTRICAL SAFETY Contents Approved by Keith Gershon construction sites, in damp areas, or in an area where a person may be in direct contact with a solidly

Knowles, David William

93

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

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

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

94

The term "Heat Stress" refers to a group of heat related illnesses that include heat cramps, heat exhaustion and heat stroke. This safety meeting will review the hazards and symptoms of  

E-Print Network [OSTI]

It's Hot The term "Heat Stress" refers to a group of heat related illnesses that include heat cramps, heat exhaustion and heat stroke. This safety meeting will review the hazards and symptoms of working in the heat. Also, how to reduce risks of working in hot temperatures and respond to danger

Li, X. Rong

95

Facility Safety  

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

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

2005-12-22T23:59:59.000Z

96

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

SciTech Connect (OSTI)

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

97

Safety at a glance; Upgrading the displays in a nuclear plant control room  

SciTech Connect (OSTI)

As part of an effort to upgrade aging plants, computer-integrated data-acquisition systems are beginning to penetrate the nation's nuclear power control rooms. The impetus is also partly due to the legacy of Three Mile Island, where control room operators, confused about which stream pressure line reading was correct, unfortunately believed the wrong one. This paper reports on the Vermont Yankee nuclear generating facility near Brattleboro, Vt., where the new SPDS requirement provided the opportunity to reassess the existing automated data-acquisition system, an installation that came as original equipment when the plant opened in 1972. The system, a Honeywell industrial computer repackaged by General Electric (which built the reactor), has become obsolete.

Baer, T.

1992-01-01T23:59:59.000Z

98

Power plant including an exhaust gas recirculation system for injecting recirculated exhaust gases in the fuel and compressed air of a gas turbine engine  

DOE Patents [OSTI]

A power plant is provided and includes a gas turbine engine having a combustor in which compressed gas and fuel are mixed and combusted, first and second supply lines respectively coupled to the combustor and respectively configured to supply the compressed gas and the fuel to the combustor and an exhaust gas recirculation (EGR) system to re-circulate exhaust gas produced by the gas turbine engine toward the combustor. The EGR system is coupled to the first and second supply lines and configured to combine first and second portions of the re-circulated exhaust gas with the compressed gas and the fuel at the first and second supply lines, respectively.

Anand, Ashok Kumar; Nagarjuna Reddy, Thirumala Reddy; Shaffer, Jason Brian; York, William David

2014-05-13T23:59:59.000Z

99

Reliability analysis of safety-related digital instrumentation and control in a nuclear power plant.  

E-Print Network [OSTI]

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

Gustafsson, Johan

2012-01-01T23:59:59.000Z

100

Safety Standards  

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

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

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

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

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

102

ENVIRONMENTAL, HEALTH AND SAFETY  

E-Print Network [OSTI]

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

California at Davis, University of

103

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

SciTech Connect (OSTI)

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

104

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

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

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.

105

Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 1  

SciTech Connect (OSTI)

Separate abstracts are included for each of the papers presented concerning current issues in nuclear power plant safety; national programs in nuclear power plant safety; radiological source terms; probabilistic risk assessment methods and techniques; non LOCA and small-break-LOCA transients; safety goals; pressurized thermal shocks; applications of reliability and risk methods to probabilistic risk assessment; human factors and man-machine interface; and data bases and special applications.

none,

1983-02-01T23:59:59.000Z

106

Facility Safety  

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

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

2002-05-20T23:59:59.000Z

107

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  

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

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

108

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

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

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

2012-06-01T23:59:59.000Z

109

Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1979  

SciTech Connect (OSTI)

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 1979. The 1345 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. Keyword and permuted-title indexes to facilitate location of individual abstracts are provided in full size 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 the failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). Some of the more interesting events that occurred during the year are reviewed in detail. 32 refs.

Scott, R.L.; Gallaher, R.B.

1981-06-01T23:59:59.000Z

110

Health Safety & Environmental Protection Committee Meeting Summaries...  

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

Flip Chart Notes Attachment 2: DOE-ORP's response to HAB Advice 258 (Safety at the Waste Treatment and Immobilization Plant) Attachment 3: Nuclear Safety Management Presentation...

111

Independent Oversight Inspection of Environment, Safety, and...  

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

Inspection of Environment, Safety, and Health Programs at the Pantex Plant, Technical Appendices, Volume II, February 2005 Independent Oversight Inspection of Environment, Safety,...

112

Materials Safety Data Sheets  

E-Print Network [OSTI]

Materials Safety Data Sheets (MSDS) MSDS contain chemical hazard information about substances compounds and solvents. MSDS data can be accessed from the following URLs http://www.ehs.umass.edu/ http://www.chem.umass.edu/Safety the "Important Safety Sites for the University" link to reach a variety of safety related information, including

Schweik, Charles M.

113

Aerosol Formation from High-Pressure Sprays for Supporting the Safety Analysis for the Hanford Waste Treatment and Immobilization Plant  

SciTech Connect (OSTI)

The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pretreat and vitrify waste currently stored in underground tanks at Hanford. One of the postulated events in the hazard analysis for the WTP is a breach in process piping that produces a pressurized spray with small droplets that can be transported into ventilation systems. Literature correlations are currently used for estimating the generation rate and size distribution of aerosol droplets in postulated spray releases. These correlations, however, are based on results obtained from small engineered nozzles using Newtonian liquids that do not contain slurry particles and thus do not accurately represent the fluids and breaches in the WTP. A test program was developed to measure the generation rate of droplets suspended in a test chamber and droplet size distribution from a range of prototypic sprays. A novel test method was developed to allow measurement of sprays from small to very large breaches and also includes the effect of aerosol generation from splatter when the spray impacts on walls. Results show that the aerosol generation rate increases with increasing the orifice area, though with a weaker dependence on orifice area than the currently-used correlation. A comparison of water sprays to slurry sprays with 8 to 20 wt% gibbsite or boehmite particles shows that the presence of slurry particles depresses the release fraction compared to water for droplets above 10 ?m and increases the release fraction below this droplet size.

Gauglitz, Phillip A.; Mahoney, Lenna A.; Schonewill, Philip P.; Bontha, Jagannadha R.; Blanchard, Jeremy; Kurath, Dean E.; Daniel, Richard C.; Song, Chen

2013-03-05T23:59:59.000Z

114

Facility Safety  

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

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

1996-10-24T23:59:59.000Z

115

Facility Safety  

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

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

1995-11-16T23:59:59.000Z

116

A fuzzy-based reliability approach to evaluate basic events of fault tree analysis for nuclear power plant probabilistic safety assessment  

Science Journals Connector (OSTI)

Abstract Fault tree analysis has been widely utilized as a tool for nuclear power plant probabilistic safety assessment. This analysis can be completed only if all basic events of the system fault tree have their quantitative failure rates or failure probabilities. However, it is difficult to obtain those failure data due to insufficient data, environment changing or new components. This study proposes a fuzzy-based reliability approach to evaluate basic events of system fault trees whose failure precise probability distributions of their lifetime to failures are not available. It applies the concept of failure possibilities to qualitatively evaluate basic events and the concept of fuzzy sets to quantitatively represent the corresponding failure possibilities. To demonstrate the feasibility and the effectiveness of the proposed approach, the actual basic event failure probabilities collected from the operational experiences of the David–Besse design of the Babcock and Wilcox reactor protection system fault tree are used to benchmark the failure probabilities generated by the proposed approach. The results confirm that the proposed fuzzy-based reliability approach arises as a suitable alternative for the conventional probabilistic reliability approach when basic events do not have the corresponding quantitative historical failure data for determining their reliability characteristics. Hence, it overcomes the limitation of the conventional fault tree analysis for nuclear power plant probabilistic safety assessment.

Julwan Hendry Purba

2014-01-01T23:59:59.000Z

117

Safety First Safety Last Safety Always Safety Shoes  

E-Print Network [OSTI]

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

Minnesota, University of

118

RESEARCH SAFETY RADIATION SAFETY  

E-Print Network [OSTI]

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

119

Safety Overview Committee (SOC)  

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

120

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

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

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.

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

Petri Net Modeling for Probabilistic Safety Assessment and its Application in the Air Lock System of a CANDU Nuclear Power Plant  

Science Journals Connector (OSTI)

Historically, fault trees are extensively used in Probabilistic Safety Assessment (PSA) to model and evaluate the probability and consequence of failures of complex engineering systems, such as nuclear power plants. Scenarios of hypothetical accidents resulting in severe core damage can be developed. Petri net is another modeling technique that offers many advantages when comparing with fault trees, such as is ability to represent the time sequence of the events along with their duration. In this research, Petri net theory is extended to model system failures. The transformations required to model logic gates by Petri nets are explored and examples provided. Methods for qualitative analysis for Petri nets are presented. The application of Petri net in the airlock system of a Canada Deuterium Uranium (CANDU) reactor is explored. It is further demonstrated that Petri net can be used in both coherent and non-coherent systems.

Andrew Lee; Lixuan Lu

2012-01-01T23:59:59.000Z

122

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]

Health and Safety Aspects of Pro- posed Nuclear, Geothermal, and Fossil-FuelHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Nero, A.V.

2010-01-01T23:59:59.000Z

123

Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997  

SciTech Connect (OSTI)

This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy`s efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees` requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees` post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant`s requests, a fourth information exchange will be held later in 1997.

NONE

1997-04-01T23:59:59.000Z

124

Safety First Safety Last Safety Always General site safety  

E-Print Network [OSTI]

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

Minnesota, University of

125

Safety First Safety Last Safety Always Safety Tip #22  

E-Print Network [OSTI]

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

Minnesota, University of

126

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  

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

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

127

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  

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

128

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  

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

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

129

Traffic Safety Facts 2004  

National Nuclear Security Administration (NNSA)

information on highway traffic safety, which can be accessed by Internet users at web site www.nhtsa.dot.govpeoplencsa, includes the following annual NCSA fact sheets:...

130

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]

for Fossil-Fu.e l and Geothermal Power Plants", Lawrencefrom fossil-fuel and geothermal power plants Control offrom fossil-fuel and geothermal power plants Radionuclide

Nero, A.V.

2010-01-01T23:59:59.000Z

131

Safety Culture at the WTP White Paper: Potential Attachment for...  

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

292011 Page 1 of 6 Safety Culture at the WTP White Paper: Potential Attachment for Advice on Waste Treatment Plant Safety Culture Introduction This white paper provides context...

132

Independent Oversight Follow-up Assessment of Safety Culture...  

Energy Savers [EERE]

Follow-up Assessment of Safety Culture at the Waste Treatment and Immobilization Plant - June 2014 Independent Oversight Follow-up Assessment of Safety Culture at the Waste...

133

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

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

Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002 Inspection of Environment, Safety, and Health Management at the...

134

Plant maintenance and plant life extension issue, 2007  

SciTech Connect (OSTI)

The focus of the March-April issue is on plant maintenance and plant life extension. Major articles/reports in this issue include: Three proposed COLs expected in 2007, by Dale E. Klein, U.S. Nuclear Regulatory Commission; Delivering behaviors that our customers value, by Jack Allen, Westinghouse Electric Company; Facilitating high-level and fuel waste disposal technologies, by Malcolm Gray, IAEA, Austria; Plant life management and long-term operation, by Pal Kovacs, OECD-NEA, France; Measuring control rod position, by R. Taymanov, K. Sapozhnikova, I. Druzhinin, D.I. Mendeleyev, Institue for Metrology, Russia; and, 'Modernization' means higher safety, by Svetlana Genova, Kozluduy NPP plc, Bulgaria.

Agnihotri, Newal (ed.)

2007-03-15T23:59:59.000Z

135

Management of National Nuclear Power Programs for assured safety  

SciTech Connect (OSTI)

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

136

Innovative safety features of the modular HTGR  

SciTech Connect (OSTI)

The Modular High Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept under development through a cooperative program involving the US Government, the nuclear industry, and the utilities. Near-term development is focused on electricity generation. The top-level safety requirement is that the plant`s operation not disturb the normal day-to-day activities of the public. Quantitatively, this requires that the design meet the US Environmental Protection Agency`s Protective Action Guides at the site boundary and hence preclude the need for sheltering or evacuation of the public. To meet these stringent safety requirements and at the same time provide a cost competitive design requires the innovative use of the basic high temperature gas-cooled reactor features of ceramic fuel, helium coolant, and a graphite moderator. The specific fuel composition and core size and configuration have been selected to the use the natural characteristics of these materials to develop significantly higher margins of safety. In this document the innovative safety features of the MHTGR are reviewed by examining the safety response to events challenging the functions relied on to retain radionuclides within the coated fuel particles. A broad range of challenges to core heat removal are examined, including a loss of helium pressure of a simultaneous loss of forced cooling of the core. The challenges to control of heat generation consider not only the failure to insert the reactivity control systems but also the withdrawal of control rods. Finally, challenges to control of chemical attack of the ceramic-coated fuel are considered, including catastrophic failure of the steam generator, which allows water ingress, or failure of the pressure vessels, which allows air ingress. The plant`s response to these extreme challenges is not dependent on operator action, and the events considered encompass conceivable operator errors.

Silady, F.A.; Simon, W.A.

1992-01-01T23:59:59.000Z

137

UNBC SAFETY CHECKLIST SAFETY CHECKLIST  

E-Print Network [OSTI]

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

Northern British Columbia, University of

138

Toolbox Safety Talk Ladder Safety  

E-Print Network [OSTI]

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

Pawlowski, Wojtek

139

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

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

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

140

Food Safety and Meat Microbiology  

E-Print Network [OSTI]

Food Safety and Meat Microbiology School July 17-19, 2012 Master Meat Crafter Program Department) and the University of Wisconsin-Madison Meat Science Laboratory are again hosting the Food Safety and Meat your food safety systems and the safety of your products. Topics will include microbiology, sanitation

Sheridan, Jennifer

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

Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Numbers 50-390 and 50-391). Supplement Number 13  

SciTech Connect (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), and Supplement No. 12 (October 1993), 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. These issues relate to: Design criteria -- structures, components, equipment, and systems; Reactor; Instrumentation and controls; Electrical power systems; Auxiliary systems; Conduct of operations; Accident analysis; and Quality assurance.

Not Available

1994-04-01T23:59:59.000Z

142

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP  

SciTech Connect (OSTI)

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

Kessler, S

2009-04-21T23:59:59.000Z

143

Status of IFE safety and environmental activities in the US  

Science Journals Connector (OSTI)

This paper presents an overview of recent progress in the area of inertial fusion energy (IFE) safety and environment (S&E) in the US. Over the past several years, a significant effort has been devoted towards the development of S&E analyses for future IFE power plants. We have completed the safety assessment of various baseline IFE power plant concepts, including simulation of accident scenarios and accident consequences analyses, S&E studies of candidate target materials and discussions on waste management issues. The results from this work have allowed for a better understanding of the behaviour of radioactive sources and hazardous materials within the IFE power plant, identification of the energy sources that could mobilize those materials in case of an accident and assessment of waste management options for IFE. Currently, ongoing S&E studies for IFE are focusing on emerging design concepts, which include support to the high average power laser (HAPL) program for development of a dry-wall, laser-driven IFE power plant and collaboration with the Z-pinch IFE program for the production of an economically attractive power plant using high-yield Z-pinch-driven targets. In this paper, the main safety issues related to the HAPL and Z-IFE programs are reviewed, some recent safety highlights are presented and future directions in the IFE S&E area are proposed.

S. Reyes; J. F. Latkowski; W. R. Meier; M. Sawan

2007-01-01T23:59:59.000Z

144

Safety Notices  

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

145

Safety First Safety Last Safety Always Requirements for employers  

E-Print Network [OSTI]

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

Minnesota, University of

146

Independent Oversight Inspection, Portsmouth Gaseous Diffusion Plant -  

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

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

147

Safety Management System Policy  

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

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

148

Safety and Technical Services  

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

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

149

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 U. S. Conunercial Nuclear Power Plants", Report WASH-Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"

Nero, A.V.

2010-01-01T23:59:59.000Z

150

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

Nero, A.V.

2010-01-01T23:59:59.000Z

151

UNBC SAFETY CHECKLIST SAFETY CHECKLIST  

E-Print Network [OSTI]

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

Northern British Columbia, University of

152

Integrated Safety Management Safety Culture Resources | Department...  

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

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

153

RISMC ADVANCED SAFETY ANALYSIS WORKING PLAN – FY 2015 – FY 2019  

SciTech Connect (OSTI)

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

Ronaldo H. Szilard; Curtis L. Smith

2014-09-01T23:59:59.000Z

154

Toolbox Safety Talk Safety Data Sheets (SDS)  

E-Print Network [OSTI]

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

Pawlowski, Wojtek

155

Public Safety Public Safety Center  

E-Print Network [OSTI]

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

156

Postgraduate Certificate in Safety and Risk Management  

E-Print Network [OSTI]

in safety and risk management, including health and safety legislation, safety policy and culture, risk be fully integrated into the organisation and the safety culture of the organisation developed accordinglyPostgraduate Certificate in Safety and Risk Management #12;Programme Structure The Postgraduate

Mottram, Nigel

157

Integrated Safety Management (ISM) | Department of Energy  

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

this content. NEWS 2010 Independent Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project Deputy Secretary Memo regarding...

158

Cryogenic safety  

Science Journals Connector (OSTI)

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

Eric W. Spencer

1964-01-01T23:59:59.000Z

159

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

SciTech Connect (OSTI)

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

160

Facility Safety  

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

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

2000-11-20T23:59:59.000Z

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

Safety Science & Solutions Integrating Human Factors in Healthcare  

E-Print Network [OSTI]

Safety Science & Solutions Integrating Human Factors in Healthcare Tuesday 2nd December 2014 safety, quality and productivity in healthcare. Showcasing enduring solutions to patient safety recognised speakers in patient safety including: Martin Bromiley, Founder, Clinical Human Factors Group Dr

Levi, Ran

162

ANNUAL FIRE SAFETY REPORT 2011 Ithaca, NY Campus  

E-Print Network [OSTI]

Plan ____________________________________________________ 14 Cornell University Fire Safety Plan including programs in: Fire Protection, Emergency Services, Emergency Management o Fire Protection Services o Research and Laboratory Safety o Chemical Safety o Radiation Safety o Biological Safe

Chen, Tsuhan

163

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

SciTech Connect (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

164

Independent Oversight Assessment, Pantex Plant - November 2012...  

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

Oversight Assessment, Pantex Plant - November 2012 November 2012 Assessment of Nuclear Safety Culture at the Pantex Plant This report provides the results of an independent...

165

Oversight Reports - Pantex Plant | Department of Energy  

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

2012 Independent Oversight Assessment, Pantex Plant - November 2012 Assessment of Nuclear Safety Culture at the Pantex Plant August 8, 2012 Independent Activity Report, Pantex...

166

Independent Activity Report, Hanford Plutonium Finishing Plant...  

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

Plutonium Finishing Plant - May 2012 Independent Activity Report, Hanford Plutonium Finishing Plant - May 2012 May 2012 Criticality Safety Information Meeting for the Hanford...

167

Independent Oversight Inspection, Waste Isolation Pilot Plant...  

Office of Environmental Management (EM)

Plant, Summary Report - August 2002 Independent Oversight Inspection, Waste Isolation Pilot Plant, Summary Report - August 2002 August 2002 Inspection of Environment, Safety, and...

168

Independent Oversight Inspection, Pantex Plant - June 2009 |...  

Energy Savers [EERE]

Inspection, Pantex Plant - June 2009 June 2009 Inspection of Environment, Safety, and Health Programs at the Pantex Plant This report documents the results of an inspection of the...

169

Independent Oversight Inspection, Pantex Plant, Summary Report...  

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

Inspection, Pantex Plant, Summary Report - November 2002 November 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Pantex Plant This report...

170

Independent Oversight Inspection, Pantex Plant, February 2005...  

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

Oversight Inspection, Pantex Plant, February 2005 February 2005 Inspection of Environment, Safety, and Health Programs at the Pantex Plant This report provides the results...

171

Safety, Security  

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

172

An Overview of the Safety Case for Small Modular Reactors  

SciTech Connect (OSTI)

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] [ORNL

2011-01-01T23:59:59.000Z

173

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

174

Radioisotope thermoelectric generator reliability and safety  

SciTech Connect (OSTI)

There are numerous occasions when a planetary mission requires energy in remote areas of the solar system. Anytime power is required much beyond Mars or the Asteroid Belts, solar power is not an option. The radioisotope thermoelectric generator (RTG) was developed for such a mission requirement. It is a relatively small and lightweight power source that can produce power under adverse conditions. Just this type of source has become the backbone of the power system for far outer plant exploration. Voyagers I and II are utilizing RTGs, which will soon power the Galileo spacecraft to Jupiter and the Ulysses spacecraft to study the solar poles. The paper discusses RTG operation including thermoelectric design, converter design, general-purpose heat source; RTG reliability including design, testing, experience, and launch approval; and RTG safety issues and methods of ensuring safety.

Campbell, R.; Klein, J.

1989-01-01T23:59:59.000Z

175

Innovative safety features of the modular HTGR  

SciTech Connect (OSTI)

The Modular High Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept under development through a cooperative program involving the US Government, the nuclear industry, and the utilities. Near-term development is focused on electricity generation. The top-level safety requirement is that the plant's operation not disturb the normal day-to-day activities of the public. Quantitatively, this requires that the design meet the US Environmental Protection Agency's Protective Action Guides at the site boundary and hence preclude the need for sheltering or evacuation of the public. To meet these stringent safety requirements and at the same time provide a cost competitive design requires the innovative use of the basic high temperature gas-cooled reactor features of ceramic fuel, helium coolant, and a graphite moderator. The specific fuel composition and core size and configuration have been selected to the use the natural characteristics of these materials to develop significantly higher margins of safety. In this document the innovative safety features of the MHTGR are reviewed by examining the safety response to events challenging the functions relied on to retain radionuclides within the coated fuel particles. A broad range of challenges to core heat removal are examined, including a loss of helium pressure of a simultaneous loss of forced cooling of the core. The challenges to control of heat generation consider not only the failure to insert the reactivity control systems but also the withdrawal of control rods. Finally, challenges to control of chemical attack of the ceramic-coated fuel are considered, including catastrophic failure of the steam generator, which allows water ingress, or failure of the pressure vessels, which allows air ingress. The plant's response to these extreme challenges is not dependent on operator action, and the events considered encompass conceivable operator errors.

Silady, F.A.; Simon, W.A.

1992-01-01T23:59:59.000Z

176

Facility Safety  

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

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

2005-12-22T23:59:59.000Z

177

Biological Safety  

Broader source: Energy.gov [DOE]

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

178

Safety Information for Families  

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

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

179

Facility Safety  

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

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

1995-10-13T23:59:59.000Z

180

Facility Safety  

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

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

2012-12-04T23:59:59.000Z

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

Nuclear Safety (Pennsylvania) | Department of Energy  

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

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

182

Aerosol Formation from High-Pressure Sprays for Supporting the Safety Analysis for the Hanford Waste Treatment and Immobilization Plant - 13183  

SciTech Connect (OSTI)

The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pretreat and vitrify waste currently stored in underground tanks at Hanford. One of the postulated events in the hazard analysis for the WTP is a breach in process piping that produces a pressurized spray with small droplets that can be transported into ventilation systems. Literature correlations are currently used for estimating the generation rate and size distribution of aerosol droplets in postulated releases. These correlations, however, are based on results obtained from small engineered nozzles using Newtonian liquids that do not contain slurry particles and thus do not represent the fluids and breaches in the WTP. A test program was developed to measure the generation rate, and the release fraction which is the ratio of generation rate to spray flow rate, of droplets suspended in a test chamber and droplet size distribution from prototypic sprays. A novel test method was developed to allow measurement of sprays from small to large breaches and also includes the effect of aerosol generation from splatter when the spray impacts on walls. Results show that the release fraction decreases with increasing orifice area, though with a weaker dependence on orifice area than the currently-used correlation. A comparison of water sprays to slurry sprays with 8 to 20 wt% gibbsite or boehmite particles shows that the presence of slurry particles depresses the release fraction compared to water for droplets above 10 ?m and increases the release fraction below this droplet size. (authors)

Gauglitz, P.A.; Mahoney, L.A.; Schonewill, P.P.; Bontha, J.R.; Blanchard, J.; Kurath, D.E.; Daniel, R.C.; Song, C. [Pacific Northwest National Laboratory, PO Box 999, Richland WA 99352 (United States)] [Pacific Northwest National Laboratory, PO Box 999, Richland WA 99352 (United States)

2013-07-01T23:59:59.000Z

183

Safety Communications  

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

184

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

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

185

DOE - Safety of Radioactive Material Transportation  

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

186

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment...  

Energy Savers [EERE]

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste...

187

Safety Cinema: Safety Videos: Los Alamos National Laboratory  

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

Safety CinemaTM VideosINDUSTRIAL HYGIENE AND SAFETY Safety Videos Safety Cinema Safety Videos Home Safety Cinema Human Beings Beryllium Integrated Safety CONTACTS Occupational...

188

Technical evaluation report TMI action -- NUREG-0737 (II.D.1). Relief and safety valve testing, Watts Bar Nuclear Plant, Units 1 and 2 (Dockets 50-390 and 50-391)  

SciTech Connect (OSTI)

In the past, safety and relief valves installed in the primary coolant system of light water reactors have performed improperly. As a result, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) and, subsequently, NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended development and completion of programs to do two things. First, they should reevaluate the functional performance capabilities of pressurized water reactor safety, relief, and block valves. Second, they should verify the integrity of the pressurizer safety and relief valve piping systems for normal, transient, and accident conditions. This report documents the review of those programs by Lockheed Idaho Technologies Company. Specifically, this report documents the review of the Watts Bar Nuclear Plant, Units 1 and 2, Applicant response to the requirements of NUREG-0578 and NUREG-0737. This review found the Applicant provided an acceptable response reconfirming they met General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 for the subject equipment. It should also be noted Lockheed Idaho performed this review for both Units 1 and 2. However, the applicability of this review to Unit 2 depends on verifying that the Unit 2 as-built system conforms to the Unit 1 design reviewed in this report.

Fineman, C.P.

1995-02-01T23:59:59.000Z

189

ORISE: Integrated Safety Management (ISM)  

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

190

Pantex Plant Emergency Response Exercise  

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

Joint Information Center Emergency Manager Offsite Interface Coordinator DOE Technical Advisor Emergency Press Center Radiation Safety Figure 1. Pantex Plant Emergency Response...

191

Independent Oversight Assessment, Waste Treatment and Immobilization Plant- January 2012  

Broader source: Energy.gov [DOE]

Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant

192

NUCLEAR PLANT AND CONTROL  

E-Print Network [OSTI]

for the digital protection systems of a nuclear power plant. When spec- ifying requirements for software and CRSA processes are described using shutdown system 2 of the Wolsong nuclear power plants as the digital, the missiles, and the digital protection systems embed- ded in nuclear power plants. Obviously, safety

193

Safety Advisories  

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

194

Safety Values  

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

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

195

Safety Engineer  

Broader source: Energy.gov [DOE]

This position is located within the Savannah River Operations Office, Office of Safety and Quality Assurance, Technical Support Division. Department of Energy (DOE) Savannah River (SR) Operations...

196

Bhopal Disaster and Risk Analysis: The Significance of the Bhopal Disaster to Risk Analysis At Any Other Chemical Plant (Safety Expenditure with Capital Rationing)  

Science Journals Connector (OSTI)

Current frequency of chemical plant incidents involving the public my average one every ten years for a fifty man department (one every million man hours.) Prior to Bhopal these resulted in from 1 to 400 compl...

Ernest V. Anderson

1987-01-01T23:59:59.000Z

197

Multicriteria selection aiding related to photovoltaic plants1 on farming fields on Corsica island: a real case study using2  

E-Print Network [OSTI]

greenhouse gas emissions, including energy savings, increased efficiency, supply safety and increasing31 Multicriteria selection aiding related to photovoltaic plants1 on farming fields on Corsica has been subjected to an unprecedented abundance of photovoltaic plant projects since8 its energy

Boyer, Edmond

198

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

Broader source: Energy.gov [DOE]

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

199

Independent Oversight Review, Waste Treatment and Immobilization Plant Project- October 2010  

Broader source: Energy.gov [DOE]

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project

200

A recommended safety program for the Mabry Foundry and Machine Company and Iron Castings Incorporated of Beaumont, Texas  

E-Print Network [OSTI]

rates of the two companies, The problem has been approached as one including past accident analysis, plant and safety organ1aation, and rec- ommendations and. procedures dealing with safety in the two fcundriesh I. THE PROBLER ht te oht... for premium payments' It, is determined by comparing the compensa- tion andjor medical costs reported to the Texas Industrial Accident Board, for a particulax' foundry, with the costs ze- portsd by other foundries in ths stats ~ An average of 37, 5 psr...

Begnaud, Edward Marshall

2012-06-07T23:59:59.000Z

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.


201

Enhancing nuclear power safety  

Science Journals Connector (OSTI)

Through its ClydeUnion Pumps brand, SPX has a long history of providing pumps to the nuclear power industry and is working to help provide solutions that enhance vital safety systems on these plants. Compared with traditional alternatives, its TWL steam turbine driven pump is designed to increase the reliability of systems that provide heat removal from pressurised water reactors and boiling water reactors during extended emergency periods.

2014-01-01T23:59:59.000Z

202

ORISE: Safety is our top priority  

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

203

Safety Bulletin  

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

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

204

(bifenazate, OHP). Water-sprayed plants were included as a control. This trial was conducted from October 3 to November 4, 2013 on field-grown 12 15' `Yoshino' cryptomeria in a  

E-Print Network [OSTI]

Island Horticultural Research and Extension Center A greenhouse study was conducted to evaluate with plants showing symptoms of injury � speckled and lightly bronzed foliage. Five single-tree replicates in a greenhouse that was lit by sodium vapor lamps from 8 AM to 5 PM. Separate two-quart containers of tall fescue

Danforth, Bryan Nicholas

205

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]

EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSINGEmergency Planning for Nuclear Power Plants Determination ofproposed nuclear power plants . . . . . . . . . • . . . .

Yen, W.W.S.

2010-01-01T23:59:59.000Z

206

Pump apparatus including deconsolidator  

DOE Patents [OSTI]

A pump apparatus includes a particulate pump that defines a passage that extends from an inlet to an outlet. A duct is in flow communication with the outlet. The duct includes a deconsolidator configured to fragment particle agglomerates received from the passage.

Sonwane, Chandrashekhar; Saunders, Timothy; Fitzsimmons, Mark Andrew

2014-10-07T23:59:59.000Z

207

Basic TRUEX process for Rocky Flats Plant  

SciTech Connect (OSTI)

The Generic TRUEX Model was used to develop a TRUEX process flowsheet for recovering the transuranics (Pu, Am) from a nitrate waste stream at Rocky Flats Plant. The process was designed so that it is relatively insensitive to changes in process feed concentrations and flow rates. Related issues are considered, including solvent losses, feed analysis requirements, safety, and interaction with an evaporator system for nitric acid recycle.

Leonard, R.A.; Chamberlain, D.B.; Dow, J.A.; Farley, S.E.; Nunez, L.; Regalbuto, M.C.; Vandegrift, G.F.

1994-08-01T23:59:59.000Z

208

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]

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- FuelHealth and Safety Aspects of Pro- posed Nuclear, Geothermal, and Fossil-Fuel

Nero, A.V.

2010-01-01T23:59:59.000Z

209

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]

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Nero, jA.V.

2010-01-01T23:59:59.000Z

210

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]

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- FuelHealth and Safety Aspects of Pro- posed Nuclear, Geothermal, and Fossil-Fuel

Yen, W.W.S.

2010-01-01T23:59:59.000Z

211

Department Safety Representatives Department Safety Representative  

E-Print Network [OSTI]

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

Pawlowski, Wojtek

212

Fire Safety Committee Meeting Minutes- May 2014  

Broader source: Energy.gov [DOE]

DOE Fire Safety Committee Meeting Minutes, May, 2014 Topics included discussions on Fire modeling, revisions to DOE regulations and other important items relating to DOE and Fire Safety Community.

213

Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting: Volume 1, Plenary session, Severe accident sequence analysis, Risk analysis/PRA applications, Reference plant risk analysis - NUREG-1150, Innovative concepts for increased safety of advanced power reactors  

SciTech Connect (OSTI)

This six-volume report contains 156 papers out of the 175 that were presented at the Fourteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 27-31, 1986. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-four different papers presented by researchers from Canada, Czechoslovakia, Finland, Germany, Italy, Japan, Mexico, Spain, Sweden, Switzerland and the United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting.

Weiss, A.J. (comp.)

1987-02-01T23:59:59.000Z

214

UNIVERSITY HEALTH, SAFETY and WELLBEING POLICY STATEMENT Strategic Health and Safety Goal  

E-Print Network [OSTI]

. The University aims to establish a positive health and safety culture that includes awareness and understanding and visitors. 2. This positive health and safety culture will be people-focussed and evidenced by: a maintaining focus on health, safety, and well-being. 3. This positive health and safety culture will have

Davies, Christopher

215

HSS Safety Shares  

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

216

ENVIRONMENT, SAFETY & HEALTH DIVISION Chapter 12: Fire and Life Safety  

E-Print Network [OSTI]

ENVIRONMENT, SAFETY & HEALTH DIVISION Chapter 12: Fire and Life Safety Fire Protection Equipment The purpose of these requirements is to ensure the adequate provision and operability of fire protection Requirements Fire protection equipment includes Automatic fire suppression systems (such as sprinkler, clean

Wechsler, Risa H.

217

NRC - regulator of nuclear safety  

SciTech Connect (OSTI)

The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

NONE

1997-05-01T23:59:59.000Z

218

LASER SAFETY POLICY MANUAL ENVIRONMENTAL HEALTH & SAFETY  

E-Print Network [OSTI]

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

Houston, Paul L.

219

Toolbox Safety Talk Machine Shop Safety  

E-Print Network [OSTI]

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

Pawlowski, Wojtek

220

Test plan: Sealing of the Disturbed Rock Zone (DRZ), including Marker Bed 139 (MB139) and the overlying halite, below the repository horizon, at the Waste Isolation Pilot Plant. Small-scale seal performance test-series F  

SciTech Connect (OSTI)

This test plan describes activities intended to demonstrate equipment and techniques for producing, injecting, and evaluating microfine cementitious grout. The grout will be injected in fractured rock located below the repository horizon at the Waste Isolation Pilot Plant (WIPP). These data are intended to support the development of the Alcove Gas Barrier System (AGBS), the design of upcoming, large-scale seal tests, and ongoing laboratory evaluations of grouting efficacy. Degradation of the grout will be studied in experiments conducted in parallel with the underground grouting experiment.

Ahrens, E.H.

1992-05-01T23:59:59.000Z

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.


221

Test plan: Sealing of the Disturbed Rock Zone (DRZ), including Marker Bed 139 (MB139) and the overlying halite, below the repository horizon, at the Waste Isolation Pilot Plant. [Cementitious grout into fractured WIPP rock  

SciTech Connect (OSTI)

This test plan describes activities intended to demonstrate equipment and techniques for producing, injecting, and evaluating microfine cementitious grout. The grout will be injected in fractured rock located below the repository horizon at the Waste Isolation Pilot Plant (WIPP). These data are intended to support the development of the Alcove Gas Barrier System (AGBS), the design of upcoming, large-scale seal tests, and ongoing laboratory evaluations of grouting efficacy. Degradation of the grout will be studied in experiments conducted in parallel with the underground grouting experiment.

Ahrens, E.H.

1992-05-01T23:59:59.000Z

222

Independent Oversight Review, Plutonium Finishing Plant- July 2014  

Broader source: Energy.gov [DOE]

Targeted Review of the Safety Significant Confinement Ventilation System and Review of Federal Assurance Capability at the Plutonium Finishing Plant

223

Independent Oversight Review, Portsmouth Gaseous Diffusion Plant- April 2013  

Broader source: Energy.gov [DOE]

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

224

Independent Activity Report, Hanford Plutonium Finishing Plant- May 2012  

Broader source: Energy.gov [DOE]

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

225

Health, Safety and Environmental Protection Committee Page 1  

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

team. She will be working closely with the Hanford Advisory Board (Board or HAB). Waste Treatment Plant Safety Culture Advice (joint topic with the Tank Waste Committee) Health,...

226

CRAD, Documented Safety Analysis Development- April 23, 2013  

Broader source: Energy.gov [DOE]

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

227

Safety, Security & Fire Report  

E-Print Network [OSTI]

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

Straight, Aaron

228

FAQS Qualification Card – Occupational Safety  

Broader source: Energy.gov [DOE]

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

229

Chapter 3 - Safety Offshore  

Science Journals Connector (OSTI)

This chapter focuses on specific issues to do with managing safety in offshore oil and gas facilities. The distinctions between drilling, pipelines and production are described. Offshore special issues include congestion, the number of people onboard, hurricanes/cyclones and dropped objects.

Ian Sutton

2014-01-01T23:59:59.000Z

230

Packaging and Transportation Safety  

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

The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of radioactive and other hazardous materials and for modal transportation. Cancels DOE O 460.1B, 5-14-10

2010-05-14T23:59:59.000Z

231

Committee on Microbiological Safety  

E-Print Network [OSTI]

standards and best practices for the oversight and administration of research with recombinant or synthetic of the research are conducted in a safe manner using established biosafety standards, principles and practices, or environmental risks, including, for example, requirements for education and training and for laboratory safety

Goodrich, Lisa V.

232

CANDU safety-status and direction  

SciTech Connect (OSTI)

This paper reviews the status and direction of Canada deuterium uranium (CANDU) safety design for the current CANDU product line, with emphasis on the single-unit containment plants.

Snell, V.G.; Allen, P.J. (Atomic Energy of Canada Limited, Sheridan Park (Canada))

1993-01-01T23:59:59.000Z

233

Flibe Use in Fusion Reactors - An Initial Safety Assessment  

SciTech Connect (OSTI)

This report is an initial effort to identify and evaluate safety issues associated with the use of Flibe (LiF-BeF2) as a molten salt coolant for nuclear fusion power plant applications. Flibe experience in the Molten Salt Reactor Experiment is briefly reviewed. Safety issues identified include chemical toxicity, radiological issues resulting from neutron activation, and the operational concerns of handling a high temperature coolant. Beryllium compounds and fluorine pose be toxicological concerns. Some controls to protect workers are discussed. Since Flibe has been handled safely in other applications, its hazards appear to be manageable. Some safety issues that require further study are pointed out. Flibe salt interaction with strong magnetic fields should be investigated. Evolution of Flibe constituents and activation products at high temperature (i.e., will Fluorine release as a gas or remain in the molten salt) is an issue. Aerosol and tritium release from a Flibe spill requires study, as does neutronics analysis to characterize radiological doses. Tritium migration from Flibe into the cooling system is also a safety concern. Investigation of these issues will help determine the extent to which Flibe shows promise as a fusion power plant coolant or plasma-facing material.

Cadwallader, Lee Charles; Longhurst, Glen Reed

1999-04-01T23:59:59.000Z

234

State-of-the-art of non-destructive testing methods and technologies for application to nuclear power plant safety-related concrete structures  

SciTech Connect (OSTI)

The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: •locating steel reinforcement and identification of its cover depth •locating tendon ducts and identification of the condition of the grout materials •detection of cracking, voids, delamination, and honeycombing in concrete structures •detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner •methods capable of identification of corrosion occurrence on the concrete side of the containment liner.

Wiggenhauser, Herbert [BAM - Federal Institute for Materials Research and Testing, Berlin, D (Germany); Naus, Dan J. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

2014-02-18T23:59:59.000Z

235

State-of-the-Art of Non-Destructive Testing Methods and Technologies for Application to Nuclear Power Plant Safety-Related Concrete Structures  

SciTech Connect (OSTI)

The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: locating steel reinforcement and identification of its cover depth locating tendon ducts and identification of the condition of the grout materials detection of cracking, voids, delamination, and honeycombing in concrete structures detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner methods capable of identification of corrosion occurrence on the concrete side of the containment liner

Wiggenhauser, Dr. Herbert [Federal Institute for Materials Research and Testing (BAM)] [Federal Institute for Materials Research and Testing (BAM); Naus, Dan J [ORNL] [ORNL

2014-01-01T23:59:59.000Z

236

Strategic Safety Goals  

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

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

237

Radiation Safety  

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

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

238

Nuclear Safety Research and Development Annual Report, December 2014  

Broader source: Energy.gov [DOE]

This document is the first annual report of DOE’s Nuclear Safety Research and Development (NSR&D) Program, managed by the Office of Nuclear Safety in the Office of Environment, Health, Safety and Security. The report includes a description of the program and summaries of R&D projects related to DOE (including NNSA) nuclear facility and operational safety.

239

ARAMIS: An integrated risk assessment methodology for SEVESO Plants  

E-Print Network [OSTI]

, SEVESO, land use planning, risk reduction, safety barriers, safety culture, safety management the needs of various stakeholders concerned by the safety of industrial plants. ARAMIS is divided into six, published in "2. International Conference on safety and environment in process industry (CISAP-2), Naples

Paris-Sud XI, Université de

240

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]

Response Planning for Nuclear Power Plants in California",and Related Standards for Nuclear Power Plants", Lawrencejected lifetime for a nuclear power plant is 40 years, a

Nero, jA.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.


241

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]

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

Nero, A.V.

2010-01-01T23:59:59.000Z

242

Laser Safety Inspection Criteria  

SciTech Connect (OSTI)

A responsibility of the Laser Safety Officer (LSO) is to perform laser safety audits. The American National Standard Z136.1 Safe use of Lasers references this requirement in several sections: (1) Section 1.3.2 LSO Specific Responsibilities states under Hazard Evaluation, ''The LSO shall be responsible for hazards evaluation of laser work areas''; (2) Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''; and (3) Appendix D, under Survey and Inspections, it states, ''the LSO will survey by inspection, as considered necessary, all areas where laser equipment is used''. Therefore, for facilities using Class 3B and or Class 4 lasers, audits for laser safety compliance are expected to be conducted. The composition, frequency and rigueur of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms. In many institutions, a sole Laser Safety Officer (LSO) or a number of Deputy LSO's perform these audits. For that matter, there are institutions that request users to perform a self-assessment audit. Many items on the common audit list and the associated findings are subjective because they are based on the experience and interest of the LSO or auditor in particular items on the checklist. Beam block usage is an example; to one set of eyes a particular arrangement might be completely adequate, while to another the installation may be inadequate. In order to provide more consistency, the National Ignition Facility Directorate at Lawrence Livermore National Laboratory (NIF-LLNL) has established criteria for a number of items found on the typical laser safety audit form. These criteria are distributed to laser users, and they serve two broad purposes: first, it gives the user an expectation of what will be reviewed by an auditor, and second, it is an opportunity to explain audit items to the laser user and thus the reasons for some of these items. Some examples are given from the audit criteria handout. As an explanatory key to the reader, an Operational Safety Procedure (OSP) as a formally reviewed safety procedure required for all Class 3B and Class 4 laser installations. An ''OSP Binder'' contains all safety documentation related to a given laser operation and serves as a central repository for documents, such as the OSP, interlock logs, lessons learned, contact information etc. ''Unattended Operation'' refers to approved procedures for unattended operation of the laser installation and may include operation beyond normal working hours. ''L-train'' is the LLNL training tracking system.

Barat, K

2005-02-11T23:59:59.000Z

243

SSRL Safety Office Memo  

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

244

ENVIRONMENTAL HEALTH & SAFETY  

E-Print Network [OSTI]

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

Brownstone, Rob

245

THE IMPACT OF THE GLOBAL NUCLEAR SAFETY REGIME IN BRAZIL  

SciTech Connect (OSTI)

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

246

Reactor operation safety information document  

SciTech Connect (OSTI)

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

Not Available

1990-01-01T23:59:59.000Z

247

Asymptotic Safety  

E-Print Network [OSTI]

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

R. Percacci

2008-11-18T23:59:59.000Z

248

Gas Pipeline Safety (Indiana)  

Broader source: Energy.gov [DOE]

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

249

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

nuclear tors. for of of These studies can examine safety systems or safety research programsnuclear power plants, and at risk. to reduce population The Light-water Reactor Safety Research Program

Nero, A.V.

2010-01-01T23:59:59.000Z

250

Next Generation Nuclear Plant Defense-in-Depth Approach  

SciTech Connect (OSTI)

The purpose of this paper is to (1) document the definition of defense-in-depth and the pproach that will be used to assure that its principles are satisfied for the NGNP project and (2) identify the specific questions proposed for preapplication discussions with the NRC. Defense-in-depth is a safety philosophy in which multiple lines of defense and conservative design and evaluation methods are applied to assure the safety of the public. The philosophy is also intended to deliver a design that is tolerant to uncertainties in knowledge of plant behavior, component reliability or operator performance that might compromise safety. This paper includes a review of the regulatory foundation for defense-in-depth, a definition of defense-in-depth that is appropriate for advanced reactor designs based on High Temperature Gas-cooled Reactor (HTGR) technology, and an explanation of how this safety philosophy is achieved in the NGNP.

Edward G. Wallace; Karl N. Fleming; Edward M. Burns

2009-12-01T23:59:59.000Z

251

Plutonium Finishing Plant (PFP) HVAC System Component Index  

SciTech Connect (OSTI)

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

252

Independent Oversight Review, Pantex Plant, December 2013  

Broader source: Energy.gov [DOE]

Targeted Review of the Safety Significant Blast Door and Personnel Door Interlock Systems and Review of Federal Assurance Capability at the Pantex Plant

253

Enterprise Assessments Review, Waste Isolation Pilot Plant -...  

Energy Savers [EERE]

December 2014 Review of the Waste Isolation Pilot Plant Recovery Plan for Operating Diesel Equipment with Available Underground Airflows. The Office of Nuclear Safety and...

254

Enterprise Assessments Review, Waste Isolation Pilot Plant -...  

Energy Savers [EERE]

December, 2014 Review of the Waste Isolation Pilot Plant Conduct of Maintenance Recovery Plan The Office of Nuclear Safety and Environmental Assessments, within the U.S. Department...

255

ENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION  

E-Print Network [OSTI]

ENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION SIMON FRASER UNIVERSITY ENVIRONMENTAL HEALTH & SAFETY DEPARTMENT Discovery Park - MTF 8888 University Drive Burnaby, British Columbia Canada V5 FOOTWEAR 23867 TRADES & CONSTRUCTION 23867 TRANSPORT OF DANGEROUS GOODS 27265 WORKPLACE ENVIRONMENT 23867

256

THE QUEEN'S COLLEGE, OXFORD STATEMENT OF SAFETY POLICY  

E-Print Network [OSTI]

and Safety at Work etc. Act 1974 which came into force on 1 April 1975 lay a duty on all employers to ensure, as far as is reasonably practicable, the safety of their employees at work by maintaining safe plant statement of his general policy with respect to the health and safety at work of his employees

Capdeboscq, Yves

257

SAFETY ASSESSMENT OF THE ARIES COMPACT STELLARATOR DESIGN  

E-Print Network [OSTI]

SAFETY ASSESSMENT OF THE ARIES COMPACT STELLARATOR DESIGN B. J. MERRILL,*a L. A. EL-GUEBALY,b C. This power plant design contains many innovative features to im- prove the physics, engineering, and safety-cooled by flowing lead lithium. In this paper we examine the safety and environmental performance of ARIES

California at San Diego, University of

258

Machine Shop Safety Tips & Safety Guidelines GENERAL SAFETY TIPS  

E-Print Network [OSTI]

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

Veiga, Pedro Manuel Barbosa

259

CRAD, Facility Safety - Unreviewed Safety Question Requirements...  

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

a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Unreviewed Safety Question Requirements...

260

SELFMONITORING DISTRIBUTED MONITORING SYSTEM FOR NUCLEAR POWER PLANTS (PRELIMINARY VERSION)  

E-Print Network [OSTI]

SELF­MONITORING DISTRIBUTED MONITORING SYSTEM FOR NUCLEAR POWER PLANTS (PRELIMINARY VERSION) Aldo and identification are extremely important activities for the safety of a nuclear power plant. In particular inside huge and complex production plants. 1 INTRODUCTION Safety in nuclear power plants requires

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

Safety Shoe Mobile  

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

Safety and Training Safety Notices Safety Shoe Mobile The Safety Shoe Mobile comes to Argonne every Monday on the following schedule: 200 Area: 0800 - 1200 360 Area: 1300 - 1630...

262

OCCUPATIONAL SAFETY and HEALTH  

E-Print Network [OSTI]

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

Weaver, Harold A. "Hal"

263

OCCUPATIONAL HEALTH AND SAFETY  

E-Print Network [OSTI]

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

264

The Office of Health, Safety and Security  

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

265

Electrical Safety  

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

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

266

Stair Safety  

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

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

267

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

268

Explosives Safety  

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

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

269

Safety valve  

DOE Patents [OSTI]

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

Bergman, Ulf C. (Malmoe, SE)

1984-01-01T23:59:59.000Z

270

Facility Safety  

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

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

2013-06-21T23:59:59.000Z

271

Office of Nuclear Safety - Directives  

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

272

Russell Furr Laboratory Safety &  

E-Print Network [OSTI]

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

273

NREL: News - NREL Recommended for Prestigious Safety and Environmental...  

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

and will include Management of Metrology Laboratory, Construction Quality Assurance, Records Management, Environment, Safety, Occupational Health, Physical Security and...

274

Electrical Safety - Monthly Analyses of Electrical Safety Occurrences  

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

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

275

Independent Oversight Inspection, Pantex Plant - August 2005 | Department  

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

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

276

Safety | Data.gov  

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

277

FAQS Qualification Card - Nuclear Safety Specialist | Department of  

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

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

278

Lawrence Berkeley National Lab/ Site Specific Safety Plan  

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

279

FAQS Qualification Card - Criticality Safety | Department of Energy  

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

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

280

Environmental Health & Safety Office of Radiological Safety  

E-Print Network [OSTI]

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

Houston, Paul L.

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

Environmental Health and Instructional Safety Employee Safety  

E-Print Network [OSTI]

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

de Lijser, Peter

282

Safety Share from National Safety Council  

Broader source: Energy.gov [DOE]

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

283

ROYAL HOLLOWAY, UNIVERSITY OF LONDON DEPARTMENTAL HEALTH AND SAFETY  

E-Print Network [OSTI]

staff are made aware of the health and safety issues (including fire safety) applicable to their work and working environment in order that their own health and safety, and that of their colleagues, is not placedROYAL HOLLOWAY, UNIVERSITY OF LONDON DEPARTMENTAL HEALTH AND SAFETY STAFF INDUCTION POLICY

Sheldon, Nathan D.

284

Safety Peer Exchange for Tribal Governments Save the Date!  

E-Print Network [OSTI]

Safety Peer Exchange for Tribal Governments Save the Date! December 9 and 10, 2014 Please mark your calendars for the Tribal Road Safety Peer Exchange sponsored by the FHWA Office of Safety in cooperation safety. The draft agenda includes: DAY 1 ­ Tuesday December 9, 2014 (8am to 5pm) Presentations o Tribal

Hartman, Chris

285

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

Science Journals Connector (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

286

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

287

Oversight Reports - Pantex Plant | Department of Energy  

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

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

288

Safety Guidelines for Fieldwork Industrial Hygiene and Occupational Safety Department  

E-Print Network [OSTI]

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

Arnold, Jonathan

289

Autoclave nuclear criticality safety analysis  

SciTech Connect (OSTI)

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

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

1991-12-31T23:59:59.000Z

290

Safety Engineer | Princeton Plasma Physics Lab  

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

291

Human factors issues in qualitative and quantitative safety analyses  

SciTech Connect (OSTI)

Humans are a critical and integral part of any operational system, be it a nuclear reactor, a facility for assembly or disassembling hazardous components, or a transportation network. In our concern over the safety of these systems, we often focus our attention on the hardware engineering components of such systems. However, experience has repeatedly demonstrated that it is often the human component that is the primary determinant of overall system safety. Both the nuclear reactor accidents at Chernobyl and Three Mile Island and shipping disasters such as the Exxon Valdez and the Herald of Free Enterprise accidents are attributable to human error. Concern over human contributions to system safety prompts us to include reviews of human factors issues in our safety analyses. In the conduct of Probabilistic Risk Assessments (PRAs), human factors issues are addressed using a quantitative method called Human Reliability Analysis (HRA). HRAs typically begin with the identification of potential sources of human error in accident sequences of interest. Human error analysis often employs plant and/or procedures walk-downs in which the analyst considers the ``goodness`` of procedures, training, and human-machine interfaces concerning their potential contribution to human error. Interviews with expert task performers may also be conducted. In the application of HRA, once candidate sources of human error have been identified, error probabilities are developed.

Hahn, H.A.

1993-10-01T23:59:59.000Z

292

SCHOOL OF EDUCATION SAFETY STATEMENT  

E-Print Network [OSTI]

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

O'Mahony, Donal E.

293

Independent Oversight Inspection of Environment, Safety, and Health  

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

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)

294

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

Office of Environmental Management (EM)

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

295

Campus Public Safety Office Michael Soto, Director of Public Safety  

E-Print Network [OSTI]

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

Bertini, Robert L.

296

National Safety Council Safety Share | Department of Energy  

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

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

297

Hydrogen Use and Safety  

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

298

EMPLOYEE SAFETY ORIENTATION  

E-Print Network [OSTI]

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

Bolch, Tobias

299

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 Risk and Safety Manager 5535 Security 7058 #12;- 3 - FOREWORD This reference manual outlines the safe

Bolch, Tobias

300

Tag: Safety  

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

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

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

    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

    302

    Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor  

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

    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)

    303

    Evaluation of residue drum storage safety risks  

    SciTech Connect (OSTI)

    A study was conducted to determine if any potential safety problems exist in the residue drum backlog at the Rocky Flats Plant. Plutonium residues stored in 55-gallon drums were packaged for short-term storage until the residues could be processed for plutonium recovery. These residues have now been determined by the Department of Energy to be waste materials, and the residues will remain in storage until plans for disposal of the material can be developed. The packaging configurations which were safe for short-term storage may not be safe for long-term storage. Interviews with Rocky Flats personnel involved with packaging the residues reveal that more than one packaging configuration was used for some of the residues. A tabulation of packaging configurations was developed based on the information obtained from the interviews. A number of potential safety problems were identified during this study, including hydrogen generation from some residues and residue packaging materials, contamination containment loss, metal residue packaging container corrosion, and pyrophoric plutonium compound formation. Risk factors were developed for evaluating the risk potential of the various residue categories, and the residues in storage at Rocky Flats were ranked by risk potential. Preliminary drum head space gas sampling studies have demonstrated the potential for formation of flammable hydrogen-oxygen mixtures in some residue drums.

    Conner, W.V.

    1994-06-17T23:59:59.000Z

    304

    Waste Isolation Pilot Plant - Reports  

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

    305

    Power Plant Power Plant  

    E-Print Network [OSTI]

    Basin Center for Geothermal Energy at University of Nevada, Reno (UNR) 2 Nevada Geodetic LaboratoryStillwater Power Plant Wabuska Power Plant Casa Diablo Power Plant Glass Mountain Geothermal Area Lassen Geothermal Area Coso Hot Springs Power Plants Lake City Geothermal Area Thermo Geothermal Area

    Tingley, Joseph V.

    306

    DOE Order Self Study Modules - DOE G 450.4-1B Integrated Safety...  

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

    and implemented. Controls may include site or facility commitments, such as conduct of operations and maintenance programs; worker safety programs; specified safety systems; or...

    307

    Safety and Security Directives Reform  

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

    308

    2007 Integrated Safety Management Workshop  

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

    309

    Hydrogen peroxide safety issues  

    SciTech Connect (OSTI)

    A literature survey was conducted to review the safety issues involved in handling hydrogen peroxide solutions. Most of the information found in the literature is not directly applicable to conditions at the Rocky Flats Plant, but one report describes experimental work conducted previously at Rocky Flats to determine decomposition reaction-rate constants for hydrogen peroxide solutions. Data from this report were used to calculate decomposition half-life times for hydrogen peroxide in solutions containing several decomposition catalysts. The information developed from this survey indicates that hydrogen peroxide will undergo both homogeneous and heterogeneous decomposition. The rate of decomposition is affected by temperature and the presence of catalytic agents. Decomposition of hydrogen peroxide is catalyzed by alkalies, strong acids, platinum group and transition metals, and dissolved salts of transition metals. Depending upon conditions, the consequence of a hydrogen peroxide decomposition can range from slow evolution of oxygen gas to a vapor, phase detonation of hydrogen peroxide vapors.

    Conner, W.V.

    1993-04-14T23:59:59.000Z

    310

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

    SciTech Connect (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

    311

    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

    312

    Office of Nuclear Safety  

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

    313

    Safety & Environmental Protection Services  

    E-Print Network [OSTI]

    Safety & Environmental Protection Services Guidance Note --------------------------------------------------------------------------------------------------------------------------------------------- UNIVERSITY OF GLASGOW Safety & Environmental Protection Services 1 Telephone: 0141-330-5532 Email: safety of others who live near you. It is about fire and the tragic consequences of getting some simple things

    Guo, Zaoyang

    314

    Safety & Environmental Protection Services  

    E-Print Network [OSTI]

    Safety & Environmental Protection Services Guidance Note --------------------------------------------------------------------------------------------------------------------------------------------- UNIVERSITY OF GLASGOW Safety & Environmental Protection Services 1 Telephone: 0141-330-5532 Email: safety FOR THE CURRENT REVISION. Emergency Fire Action Plan Revision 03/10 Listed below are the procedures and other

    Guo, Zaoyang

    315

    System Design and the Safety Basis  

    SciTech Connect (OSTI)

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

    Ellingson, Darrel

    2008-05-06T23:59:59.000Z

    316

    FAQS Qualification Card - Senior Technical Safety Manager | Department of  

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

    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

    317

    FAQS Qualification Card - Occupational Safety | Department of Energy  

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

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

    318

    FAQS Qualification Card - Safety Software Quality Assurance | Department  

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

    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

    319

    FAQS Qualification Card - Aviation Safety Officer | Department of Energy  

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

    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

    320

    FAQS Qualification Card - Nuclear Explosive Safety Study | Department of  

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

    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

    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

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

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

    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,

    322

    GT-MHR design, performance, and safety  

    SciTech Connect (OSTI)

    The Gas Turbine-Modular Helium Reactor (GT-MHR) is the result of coupling the evolution of a low power density passively safe modular reactor with key technology developments in the U.S. during the last decade: large industrial gas turbines; large active magnetic bearings; and compact, highly effective plate-fin heat exchangers. This is accomplished through the unique use of the Brayton cycle to produce electricity with the helium as primary coolant from the reactor directly driving the gas turbine electrical generator. This cycle can achieve a high net efficiency in the range of 45% to 48%. In the design of the GT-MHR the desirable inherent characteristics of the inert helium coolant, graphite core, and the coated fuel particles are supplemented with specific design features such as passive heat removal to achieve the safety objective of not disturbing the normal day-to-day activities of the public even for beyond design basis rare accidents. Each GT-MHR plant consists of four modules. The GT-MHR module components are contained within steel pressure vessels: a reactor vessel, a power conversion vessel, and a connecting cross vessel. All vessels are sited underground in a concrete silo, which serves as an independent vented low pressure containment structure. By capitalizing on industrial and aerospace gas turbine development, highly effective heat exchanger designs, and inherent gas cooled reactor temperature characteristics, the passively safe GT-MHR provides a sound technical, monetary, and environmental basis for new nuclear power generating capacity. This paper provides an update on the status of the design, which has been under development on the US-DOE program since February 1993. An assessment of plant performance and safety is also included.

    Neylan, A.J.; Shenoy, A.; Silady, F.A.; Dunn, T.D.

    1994-11-01T23:59:59.000Z

    323

    Integrated Safety Management  

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

    Safety Management BEHAVIOR (SAFETY CULTURE) - principles of behavior (values) - align motivations PLAN WORK define project scope define facility functional requirements define and...

    324

    Nuclear criticality safety guide  

    SciTech Connect (OSTI)

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

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

    1996-09-01T23:59:59.000Z

    325

    Magnetic Field Safety Training  

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

    Safety Training Magnetic Field Safety Strong Magnetic Fields exist around energized magnets. High magnetic fields alone are a recognized hazard only for personnel with certain...

    326

    Nuclear Safety Regulatory Framework  

    Energy Savers [EERE]

    Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946...

    327

    Westinghouse Small Modular Reactor balance of plant and supporting systems design  

    SciTech Connect (OSTI)

    The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (>225 MWe) integral pressurized water reactor (iPWR), in which all of the components typically associated with the nuclear steam supply system (NSSS) of a nuclear power plant are incorporated within a single reactor pressure vessel. This paper is the second in a series of four papers which describe the design and functionality of the Westinghouse SMR. It focuses, in particular, upon the supporting systems and the balance of plant (BOP) designs of the Westinghouse SMR. Several Westinghouse SMR systems are classified as safety, and are critical to the safe operation of the Westinghouse SMR. These include the protection and monitoring system (PMS), the passive core cooling system (PXS), and the spent fuel cooling system (SFS) including pools, valves, and piping. The Westinghouse SMR safety related systems include the instrumentation and controls (I and C) as well as redundant and physically separated safety trains with batteries, electrical systems, and switch gears. Several other incorporated systems are non-safety related, but provide functions for plant operations including defense-in-depth functions. These include the chemical volume control system (CVS), heating, ventilation and cooling (HVAC) systems, component cooling water system (CCS), normal residual heat removal system (RNS) and service water system (SWS). The integrated performance of the safety-related and non-safety related systems ensures the safe and efficient operation of the Westinghouse SMR through various conditions and transients. The turbine island consists of the turbine, electric generator, feedwater and steam systems, moisture separation systems, and the condensers. The BOP is designed to minimize assembly time, shipping challenges, and on-site testing requirements for all structures, systems, and components. (authors)

    Memmott, M. J.; Stansbury, C.; Taylor, C. [Westinghouse Electric Company LLC, 600 Cranberry Woods Drive, Cranberry Twp. PA 16066 (United States)

    2012-07-01T23:59:59.000Z

    328

    Software Quality Assurance for Nuclear Safety Systems  

    SciTech Connect (OSTI)

    The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: {sm_bullet} Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe {sm_bullet} Considers the larger system that uses the software and its impacts {sm_bullet} Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety-critical software and applies the highest level of rigor for those systems. DOE has further defined a risk approach to nuclear safety system software consistent with the analyses required for operation of nuclear facilities. This requires the grading of software in terms of safety class and safety significant structures, systems and components (SSCs). Safety-class SSCs are related to public safety where as safety-significant SSCs are identified for specific aspects of defense-in-depth and worker safety. Industry standards do not directly categorize nuclear safety software and DOE sites are not consistent in their approach to nuclear safety software quality assurance. DOE is establishing a more detailed graded approach for software associated with safety class and safety significant systems. This paper presents the process and results that DOE utilized to develop a detailed classification scheme for nuclear safety software.

    Sparkman, D R; Lagdon, R

    2004-05-16T23:59:59.000Z

    329

    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  

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

    330

    Introduction to LNG vehicle safety. Topical report  

    SciTech Connect (OSTI)

    Basic information on the characteristics of liquefied natural gas (LNG) is assembled in this report to provide an overview of safety issues and practices for the use of LNG vehicles. This document is intended for those planning or considering the use of LNG vehicles, including vehicle fleet owners and operators, public transit officials and boards, local fire and safety officials, manufacturers and distributors, and gas industry officials. Safety issues and mitigation measures that should be considered for candidate LNG vehicle projects are addressed.

    Bratvold, D.; Friedman, D.; Chernoff, H.; Farkhondehpay, D.; Comay, C.

    1994-03-01T23:59:59.000Z

    331

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

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

    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.

    332

    DOE Seeks Proposals for Portsmouth Plant Technical Services | Department of  

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

    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

    333

    20 - Licensing for nuclear power plant siting, construction and operation  

    Science Journals Connector (OSTI)

    Abstract: This chapter addresses the need for licensing of nuclear power plants, and how such licenses can be requested by an applicant and granted by a regulatory authority. The licensing process is country dependent, although based on the common principle that the applicant must demonstrate that the proposed nuclear power plant will comply with the established regulations, and that it will operate safely without undue risks to the health and safety of plant personnel, the population and the environment. During the construction and operational phases the regulatory authority ensures compliance with the the license conditions through evaluation, monitoring and inspection. The license may be a single document covering all the phases in the life of the plant, or a set of consecutive documents requested and issued for different phases, which may include design certification, site approval, design and construction, commissioning and operation, design changes during operation, life extension and, finally, decommissioning.

    A. Alonso; S.K. Sharma; D.F. Torgerson

    2012-01-01T23:59:59.000Z

    334

    Nuclear plant-aging research on reactor protection systems  

    SciTech Connect (OSTI)

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed.

    Meyer, L.C.

    1988-01-01T23:59:59.000Z

    335

    Integrating Safety Assessment Methods using the Risk Informed Safety Margins Characterization (RISMC) Approach  

    SciTech Connect (OSTI)

    Safety is central to the design, licensing, operation, and economics of nuclear power plants (NPPs). As the current light water reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of systems, structures, and components (SSC) degradations or failures that initiate safety significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated primarily based on engineering judgment backed by a set of conservative engineering calculations. The ability to better characterize and quantify safety margin is important to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development (R&D) in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the RISMC Pathway provides methods and tools that enable mitigation options known as margins management strategies. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. As the lead Department of Energy (DOE) Laboratory for this Pathway, the Idaho National Laboratory (INL) is tasked with developing and deploying methods and tools that support the quantification and management of safety margin and uncertainty.

    Curtis Smith; Diego Mandelli

    2013-03-01T23:59:59.000Z

    336

    Bog Plants  

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

    337

    Complete Safety Training  

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

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

    338

    Complete Safety Training  

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

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

    339

    Complete Safety Training  

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

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

    340

    Waste Isolation Pilot Plant  

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

    revised to analyze and address all nuclear safety issues. A formal operational readiness review is included in the Recovery Plan that will be conducted prior to returning to full...

    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

    2012 Nuclear Safety Workshop Presentations | Department of Energy  

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

    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

    342

    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]

    nuclear, geothermal, and fossil-fuel power plants. However,power plants, which are reviewed and licensed by the Nuclear Regulatory Commission (NRC), and relatively few areas of geothermal and

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    343

    Independent Oversight Assessment, Pantex Plant - November 2012 | Department  

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

    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

    344

    SAFETY AND THE Office of Environmental Health and Instructional Safety  

    E-Print Network [OSTI]

    SAFETY AND THE SUPERVISOR Office of Environmental Health and Instructional Safety #12;Safety to University safety, health, and environmental compliance strategies. Every employee is entitled to a safe standard practices, and administering your overall safety, health, and environmental responsibilities

    de Lijser, Peter

    345

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

    E-Print Network [OSTI]

    of the health and safety impact of fossil fuel emissions.to public health and safety, of any fossil fuel plant areHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    346

    Workers Deliver Award-Winning Respiratory Safety | Department of Energy  

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

    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.

    347

    Workers Deliver Award-Winning Respiratory Safety | Department of Energy  

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

    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.

    348

    Performance Evaluation of Standby Safety Systems Due to Independent and Common Cause Failures  

    E-Print Network [OSTI]

    for the safety systems in Cana- dian Deuterium Uranium (CANDU) Nuclear Power Plants (NPPs) [2] to be 10-3 . When

    Lewis, Greg

    349

    Worker Safety and Health  

    Broader source: Energy.gov [DOE]

    Worker Safety and Health Policy establishes Departmental expectations for worker safety and health through the development of rules, directives and guidance. Worker safety and health policy will ensure that workers are adequately protected from hazards associated with DOE sites and operations and reflect national worker safety and health laws, regulations, and standards where applicable.

    350

    Environmental Health and Safety  

    E-Print Network [OSTI]

    Environmental Health and Safety EHS-FORM-022 v.1.1 Page 1 of 1 Laboratory safety self NA Radioactive materials [MNI Radiation Safety Manua ]l MNI: contact Christian Janicki christian.janicki@mcgill.ca 8888-43866 ANSI (American National Standards Institute) Class 3b or 4 lasers Biological safety

    Shoubridge, Eric

    351

    Local Safety Committee Engineering  

    E-Print Network [OSTI]

    Minutes Local Safety Committee Name of Committee Engineering Worksite Mailing Address & Postal Code J. Pannell ECE Support Engineer x Ken Jodrey E-Shops, for B. Wilson x * co-chairs Brad Hayes Safety, no report. Pending C. Safety Day Planning Committee Planning for Safety Days on Sept. 10 & 11 continues

    Saskatchewan, University of

    352

    Effectiveness Safety Committee  

    E-Print Network [OSTI]

    Increase the Effectiveness of Your Safety Committee Lisa Tobiason An equal opportunity educator 302 Acres. ­ East Campus 338 Acres. #12;UNL Safety Committees · Chancellors University Safety Committee (CUSC). · Unit Safety Committees. ­ Thirty-two active committees representing Lincoln campuses

    Farritor, Shane

    353

    SAFETY MANUAL ENVIRONMENTAL  

    E-Print Network [OSTI]

    HAZARDOUS MATERIALS SAFETY MANUAL ENVIRONMENTAL HEALTH & SAFETY #12;Emergency Phone Numbers Newark-800-722-7112 National .....................................1-800-222-1222 July 2007 Environmental Health and Safety://www.udel.edu/ehs #12;University Of Delaware Safety Policy Number 7-1 The policy of the University of Delaware

    Firestone, Jeremy

    354

    Fire Safety January 2011  

    E-Print Network [OSTI]

    1 Fire Safety PROCEDURES January 2011 firesafety@uwo.ca Campus Phones ­ EMERGENCY ­ Dial 911 Fire Safety Service is the focal point for the coordinated administration of the University Fire Safety Prevention and Fire Safety to minimize the risk of injury or loss of life or property due to fire

    Lennard, William N.

    355

    Local Safety Committee Engineering  

    E-Print Network [OSTI]

    Minutes Local Safety Committee Name of Committee Engineering Worksite Mailing Address & Postal Code-Shops Tech x R. Dahlgren Safety Resources x L. Wilson (support) Dean's Office x D. Hart Safety Resources x T involving chemicals. C. Safety Day Planning Committee L. Roth reported that the schedule of speakers

    Saskatchewan, University of

    356

    Facility Safety  

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

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

    2014-06-25T23:59:59.000Z

    357

    Safety posters | Argonne National Laboratory  

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

    Falls 10 of 34 Slips, Trips and Falls Road Safety 11 of 34 Road Safety Safety Counts - Lockout 12 of 34 Safety Counts - Lockout ISMposter1B 13 of 34 ISMposter1B Integrated Safety...

    358

    Construction Safety Advisory Committee- Membership Roster  

    Broader source: Energy.gov [DOE]

    CSAC members shall consist of DOE and DOE contractor employees whose normal job duties include program management or operational direction of construction safety. Members shall be nominated by their management based on their construction safety expertise and on the needs of the committee.

    359

    EHSO TRAINING CLASSES Fire Safety Program Training  

    E-Print Network [OSTI]

    EHSO TRAINING CLASSES Fire Safety Program Training 1. Fire Safety (60 minutes) Instruction includes an actual fire eperience. 2. Fire Extinguisher Training (30 minutes) A practical demonstration on actual burnable liquid fires. This practical extinguisher training is a critical portion of the fire

    360

    University Services University Health and Safety  

    E-Print Network [OSTI]

    Health and Safety includes the Building Code Division (BCD) and the Department of Environmental Health and Safety (DEHS). The Building Code Division is the institutional code enforcement department for all review, code interpretation and inspection according to state and national codes. Building Codes works

    Minnesota, University of

    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

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

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

    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

    362

    Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor  

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

    (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

    363

    ACTIVITY SPECIFIC FIREARMS SAFETY PLAN FOR  

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

    364

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

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

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

    365

    Integrated Safety Management Policy  

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

    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

    366

    Independent Oversight Review, Waste Isolation Pilot Plant - November...  

    Energy Savers [EERE]

    Safety and Security (HSS), conducted an independent review of the U.S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) preparedness for severe natural phenomena...

    367

    Nuclear power's threat to health, safety, and freedom  

    Science Journals Connector (OSTI)

    Nuclear power's threat to health, safety, and freedom ... In particular, they may differ on whether the nuclear power plants that are the result of the 1953 Atoms for Peace movement help or hinder the control of nuclear weapons. ...

    1980-10-13T23:59:59.000Z

    368

    Aspects of environmental and safety analysis of fusion reactors  

    E-Print Network [OSTI]

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

    Kazimi, Mujid S.

    1977-01-01T23:59:59.000Z

    369

    A risk-informed approach to safety margins analysis  

    SciTech Connect (OSTI)

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

    Curtis Smith; Diego Mandelli

    2013-07-01T23:59:59.000Z

    370

    Genetic Engineered Food and Safety  

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

    371

    SI Safety Information  

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

    372

    Integrated Safety Management (ISM)  

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

    373

    Meals included in Conference Registrations  

    E-Print Network [OSTI]

    Meals included in Conference Registrations Meals included as part of the cost of a conference the most reasonable rates are obtained. Deluxe hotels and motels should be avoided. GSA rates have been for Georgia high cost areas. 75% of these amounts would be $21 for non- high cost areas and $27 for high cost

    Arnold, Jonathan

    374

    Code of Federal Regulations NUCLEAR SAFETY MANAGEMENT  

    Broader source: Energy.gov [DOE]

    This part governs the conduct of DOE contractors, DOE personnel, and other persons conducting activities (including providing items and services) that affect, or may affect, the safety of DOE nuclear facilities.

    375

    Construction Safety Advisory Committee | Department of Energy  

    Office of Environmental Management (EM)

    meeting and included in the minutes of the meeting. Approved: Larry McCabe, P.E., MBA, CSP, DOEHQ Program Lead DOE Construction Safety Advisory Committee Jeffrey D. Feit,...

    376

    Pantex Plant | Department of Energy  

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

    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

    377

    Safety Assurance for ATR Irradiations  

    SciTech Connect (OSTI)

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

    S. Blaine Grover

    2006-10-01T23:59:59.000Z

    378

    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

    379

    Unusual Condition Mining for Risk Management of Hydroelectric Power Plants  

    Science Journals Connector (OSTI)

    Kyushu Electric Power Co.,Inc. collects different sensor data and weather information to maintain the safety of hydroelectric power plants while the plants are running. In this paper, we consider that the abnormal condition sign may be unusual condition. ...

    Takashi Onoda; Norihiko Ito; Hironobu Yamasaki

    2006-12-01T23:59:59.000Z

    380

    Nuclear Safety Regulatory Framework  

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

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

    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

    Texas Plants Poisonous to Livestock.  

    E-Print Network [OSTI]

    TEXAS PLANTS POISONOUS TO LIVESTOCK TEXAS A&M UNIVERSITY TEXAS AGRICULTURAL EXPERIMENT STATION TEXAS AGRICULTURAL EXTENSION SERVICE College Station, Texas THE PROBLEM POISONOUS PLANT RESEARCH IN TEXAS TOXIC PLANT CONSTITUENTS TEXAS PLANTS... list includes plants growing in Texas and reported to be poisonous in other areas. Some species described seldom cause trouble but are included since they have been proved toxic and may, under conditions, bring about livestock losses. Poisoning...

    Sperry, Omer Edison

    1964-01-01T23:59:59.000Z

    382

    Safety Responsibilities of Faculty & Lab Managers D. Heeley (14  

    E-Print Network [OSTI]

    Safety Responsibilities of Faculty & Lab Managers D. Heeley (14 th June 2010) 1 1) Primary responsibility for safety within their own laboratory or work space rests with the individual faculty member of their employment, on good safety practice. This will include: (i) Handling of hazardous materials (e.g. metabolic

    Oyet, Alwell

    383

    Recommended guidelines for solid fuel use in cement plants  

    SciTech Connect (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

    384

    Magnetic Field Safety Magnetic Field Safety  

    E-Print Network [OSTI]

    Magnetic Field Safety Training #12;Magnetic Field Safety Strong Magnetic Fields exist around energized magnets. High magnetic fields alone are a recognized hazard only for personnel with certain medical conditions such as pacemakers, magnetic implants, or embedded shrapnel. In addition, high magnetic

    McQuade, D. Tyler

    385

    Waste acceptance criteria for the Waste Isolation Pilot Plant. Revision 4  

    SciTech Connect (OSTI)

    This Revision 4 of the Waste Acceptance Criteria (WAC), WIPP-DOE-069, identifies and consolidates existing criteria and requirements which regulate the safe handling and preparation of Transuranic (TRU) waste packages for transportation to and emplacement in the Waste Isolation Pilot Plant (WIPP). This consolidation does not invalidate any existing certification of TRU waste to the WIPP Operations and Safety Criteria (Revision 3 of WIPP-DOE--069) and/or Transportation: Waste Package Requirements (TRUPACT-II Safety Analysis Report for Packaging [SARP]). Those documents being consolidated, including Revision 3 of the WAC, currently support the Test Phase.

    Not Available

    1991-12-01T23:59:59.000Z

    386

    Coal Mine Safety Act (Virginia)  

    Broader source: Energy.gov [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...

    387

    Health & Safety Plan Last Updated  

    E-Print Network [OSTI]

    Health & Safety Plan Last Updated March 2008 1 #12;A. SCOPE AND RESPONSIBILITY....................................................................................................................................... 3 2. Safety and Health Policy...................................................................................................................... 3 4. Safety Coordinator

    Anderson, Richard

    388

    Use of neural networks in the operation of nuclear power plants  

    SciTech Connect (OSTI)

    Application of neural networks to the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: (a) diagnosing specific abnormal conditions, (b) detection of the change of mode of operation, (c) signal validation, (d) monitoring of check valves, (e) modeling of the plant thermodynamics, (f) emulation of core reload calculations, (g) analysis of temporal sequences in NRC's licensee event report,'' (h) monitoring of plant parameters, and (i) analysis of plant vibrations. Each of these projects and its status are described briefly in this article. the objective of each of these projects is to enhance the safety and performance of nuclear plants through the use of neural networks. 6 refs.

    Uhrig, R.E. (Tennessee Univ., Knoxville, TN (USA) Oak Ridge National Lab., TN (USA))

    1990-01-01T23:59:59.000Z

    389

    Safety Case Depictions vs. Safety Cases Would the Real Safety Case Please Stand Up?  

    E-Print Network [OSTI]

    Safety Case Depictions vs. Safety Cases ­ Would the Real Safety Case Please Stand Up? Ibrahim Habli York, UK ibrahim.habli@cs.york.ac.uk, tim.kelly@cs.york.ac.uk Keywords: Safety Cases, Safety Arguments, GSN, Safety Assurance, Certification Abstract The integrity of the safety case depends primarily

    Kelly, Tim

    390

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

    E-Print Network [OSTI]

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

    Sze, Lawrence

    391

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

    E-Print Network [OSTI]

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

    Sze, Lawrence

    392

    National Ignition Facility Project Site Safety Program  

    SciTech Connect (OSTI)

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

    Dun, C

    2003-09-30T23:59:59.000Z

    393

    Technical Safety Requirements  

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

    Safety Requirements Safety Requirements FUNCTIONAL AREA GOAL: Contractor has developed, maintained, and received DOE Field Office Approval for the necessary operating conditions of a facility. The facility has also maintained an inventory of safety class and safety significant systems and components. REQUIREMENTS: 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

    394

    Documented Safety Analysis  

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

    Documented Safety Analysis Documented Safety Analysis FUNCTIONAL AREA GOAL: A document that provides an adequate description of the hazards of a facility during its design, construction, operation, and eventual cleanup and the basis to prescribe operating and engineering controls through Technical Safety Requirements (TSR) or Administrative Controls (AC). REQUIREMENTS: 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.

    395

    Safety for Users  

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

    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...

    396

    Safety for Users  

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

    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...

    397

    Nuclear Engineer (Criticality Safety)  

    Broader source: Energy.gov [DOE]

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

    398

    Pipeline Safety Rule (Tennessee)  

    Broader source: Energy.gov [DOE]

    The Pipeline Safety Rule simply states, "The Minimum Federal Safety Standards for the transportation of natural and other gas by pipeline (Title 49, Chapter 1, Part 192) as published in the Federal...

    399

    General Engineer (Nuclear Safety)  

    Broader source: Energy.gov [DOE]

    The Chief of Nuclear Safety (CNS) reports the US/M&P; in serving as the Central Technical Authority (CTA) for M&P; activities, ensuring the Departments nuclear safety policies and...

    400

    Annual Security and Fire Safety Report | 2010 public safety  

    E-Print Network [OSTI]

    Annual Security and Fire Safety Report | 2010 col u m bia univer sity public safety #12;Contents A Message from the Vice President for Public Safety.............................................1 The Clery .............................................................................................................2 The Department of Public Safety

    Kim, Philip

    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

    Overview of ITER safety  

    SciTech Connect (OSTI)

    This paper presents an overview of safety in the International Thermonuclear Experimental Reactor (ITER) project midway through the Engineering Design Activities (EDA). We describe the safety strategy and approach used by the project. Then, we present project radiological release limits with the methodology used to determine if these release limits are met. We review the major safety functions and their implementation for ITER, previous results, and plans for upcoming safety and environmental analyses. 16 refs., 2 figs., 3 tabs.

    Petti, D.A. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Piet, S.J. [ITER San Diego Joint Work Site, La Jolla, CA (United States)

    1996-12-31T23:59:59.000Z

    402

    Index of /safety  

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

    safety Icon Name Last modified Size Description DIR Parent Directory - DIR hazardousradioactive..> 17-Apr-2013 12:29 -...

    403

    Nuclear Explosive Safety Manual  

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

    This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

    2009-04-14T23:59:59.000Z

    404

    Electrical safety guidelines  

    SciTech Connect (OSTI)

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

    Not Available

    1993-09-01T23:59:59.000Z

    405

    Strategic Safety Goals | Department of Energy  

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

    Strategic Safety Goals Strategic Safety Goals July 19, 2012 Strategic Safety Goals, Safety Performance for 2nd Quarter 2012 - Events DOE Strives to Avoid Strategic Safety Goals...

    406

    Hanford Waste Vitrification Plant technical manual  

    SciTech Connect (OSTI)

    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

    407

    Annual Fire Safety Report  

    E-Print Network [OSTI]

    2010 Annual Fire Safety Report University of California, Irvine HIGHER EDUCATION OPPORTUNITY to the Fire Safety in Student Housing Buildings of current or perspective students and employees be reported publish an annual fire safety report, keep a fire log, and report fire statistics to the Secretary

    Loudon, Catherine

    408

    Universal software safety standard  

    Science Journals Connector (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

    409

    Radiation safety system  

    Science Journals Connector (OSTI)

    ......disable this safety function and...circuits and software. Other required...source in case of radiation monitors. Feedback...from other non-safety systems to prevent...write and check software. The expected...logic systems for safety functions can...levels of prompt radiation hazard. ACS......

    Vaclav Vylet; James C. Liu; Lawrence S. Walker

    2009-11-01T23:59:59.000Z

    410

    Environmental Health & Safety  

    E-Print Network [OSTI]

    Environmental Health & Safety Sub Department Name 480 Oak Rd, Stanford, CA 94305 T 650.723.0448 F 650.725.3468 DEPUTY DIRECTOR, ENVIRONMENTAL HEALTH AND SAFETY Exempt, Full-Time (100% FTE) Posted May 1, 2014 The Department of Environmental Health and Safety (EH&S) at Stanford University seeks

    411

    Environmental Health and Safety  

    E-Print Network [OSTI]

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

    Shoubridge, Eric

    412

    SYSTEM SAFETY PROGRESS REPORT,  

    E-Print Network [OSTI]

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

    Rathbun, Julie A.

    413

    Health, Safety & Wellbeing Policy  

    E-Print Network [OSTI]

    Health, Safety & Wellbeing Policy Statement The University of Glasgow is one of the four oldest our very best to minimise the risk to the health, safety and wellbeing of staff, students, researchers resource and our students as our valued customers and partners. We acknowledge health and safety as a core

    Mottram, Nigel

    414

    Plan for addressing issues relating to oil shale plant siting  

    SciTech Connect (OSTI)

    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

    415

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

    SciTech Connect (OSTI)

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

    Alan Bond

    2001-04-01T23:59:59.000Z

    416

    Plants & Animals  

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

    417

    Sponsorship includes: Agriculture in the  

    E-Print Network [OSTI]

    Sponsorship includes: · Agriculture in the Classroom · Douglas County Farm Bureau · Gifford Farm · University of Nebraska Agricultural Research and Development Center · University of Nebraska- Lincoln Awareness Coalition is to help youth, primarily from urban communities, become aware of agriculture

    Nebraska-Lincoln, University of

    418

    Plant immune systems  

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

    419

    Safety and Occupational Health Manager  

    Broader source: Energy.gov [DOE]

    This incumbent in this position will serve as a Safety and Occupational Health Manager representing the BPA Safety Office in the administration of safety and health programs. The Safety...

    420

    Safety Manual Prepared by the  

    E-Print Network [OSTI]

    Radiation and Laser Safety 19 Laser Safety 21 Compressed Gas and Cryogenic Safety 22 Electrical Safety 24 911. Red Pull Station Pulling down the handle on a Red Pull Station will send a fire alarm to the Fire

    Alpay, S. Pamir

    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

    Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program  

    SciTech Connect (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

    422

    A Technique for Demonstrating Safety and Correctness of Program Translators  

    E-Print Network [OSTI]

    Plants · It produce the `Shutdown' signal to protect a NPP from unwanted situation. 2014-11-05 Scope An overview of Nuclear Power Plants. #12;5 1. Introduction · Software Development Process based on PLC #12;6 1-11-05 Safety Property Natural requirement "If PV_OUT (An input sensor value) is more than the TSP (Trip Set

    423

    CRITICALITY SAFETY (CS)  

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

    Objective CS.1 - A criticality safety program is established, sufficient numbers of qualified personnel are provided, and adequate facilities and equipment are available to ensure criticality safety support services are adequate for safe operations. (Core Requirements 1, 2, and 6) Criteria * Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented. * Operations support personnel for the criticality safety area are adequately staffed and trained. Approach Record Review: Review the documentation that establishes the Criticality Safety Requirements (CSRs) for appropriateness and completeness. Review for adequacy and completion the criticality safety personnel training records that indicate training on facility procedures and systems under

    424

    MTDC Safety Sensor Technology  

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

    425

    CRITICALITY SAFETY (CS)  

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

    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

    426

    FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter  

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

    H2 Safety Snapshot H2 Safety Snapshot Newsletter to someone by E-mail Share FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Facebook Tweet about FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Twitter Bookmark FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Google Bookmark FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Delicious Rank FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on Digg Find More places to share FCT Safety, Codes and Standards: H2 Safety Snapshot Newsletter on AddThis.com... Home Basics Current Approaches to Safety, Codes & Standards DOE Activities Quick Links Hydrogen Production Hydrogen Delivery Hydrogen Storage Fuel Cells Technology Validation Manufacturing Education Systems Analysis

    427

    Bonuses at nuclear arms plants condemned  

    Science Journals Connector (OSTI)

    The Department of Energy's management of its 17 nuclear weapons plants, already beset by massive environmental, safety, and health problems, drew further fire at a House hearing last week. ... Keith O. Fultz, director of energy issues at the General Accounting Office, presented a report detailing how DOE downplayed or ignored serious environmental, safety, and health problems at the Rocky Flats plant near Denver while awarding the operator, Rockwell International Corp., $26.8 million in performance bonuses in fiscal years 1986- 88. ...

    RICHARD SELTZER

    1989-10-30T23:59:59.000Z

    428

    Nuclear Facility Safety Basis  

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

    Safety Basis Safety Basis FUNCTIONAL AREA GOAL: A fully compliant Nuclear Facility Safety Basis. Program is implemented and maintained across the site. REQUIREMENTS: 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

    429

    Chemical Safety Program  

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

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

    430

    Safety System Oversight  

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

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

    431

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

    SciTech Connect (OSTI)

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

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

    1990-11-09T23:59:59.000Z

    432

    Traffic Safety Culture Center for Transportation Safety  

    E-Print Network [OSTI]

    generally opposed to raising the state's gasoline tax to pay for new roads or to make the roads safer. The Texas Traffic Safety Culture Survey was conducted at ten driver license stations operated by the Texas

    433

    Safety First Safety AlwaysSafety Last Using abrasive wheel equipment exposes you to many  

    E-Print Network [OSTI]

    Safety First Safety AlwaysSafety Last Using abrasive wheel equipment exposes you to many potential and strength and meet all manufacturer specifications. Abrasive Wheel Machinery and Tools Safety Tip #1

    Minnesota, University of

    434

    Pressure Safety Program Implementation at ORNL  

    SciTech Connect (OSTI)

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply with pressure safety requirements in 10 CFR 851. It also describes actions taken to develop and implement ORNL’s Pressure Safety Program.

    Lower, Mark [ORNL; Etheridge, Tom [ORNL; Oland, C. Barry [XCEL Engineering, Inc.

    2013-01-01T23:59:59.000Z

    435

    Environment, Safety and Health Evaluations - Reports  

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

    436

    Risk Informed Safety Margin Characterization Case Study: Selection of  

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

    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

    437

    Safety First Safety Last Safety Always Three soil types, plus rock, determine the slope or  

    E-Print Network [OSTI]

    Safety First Safety Last Safety Always · Three soil types, plus rock, determine the slope or safety to be at least 2 feet from the edge. Excavation Requirements Safety Tip #10 If you see a mistake and don't fix it on the reverse side of this safety tip sheet. Please refrain from reading the information verbatim

    Minnesota, University of

    438

    Safety First Safety Last Safety Always Over the years, many techniques and methods have been  

    E-Print Network [OSTI]

    Safety First Safety Last Safety Always Over the years, many techniques and methods have been, especially to the lower back. DON'T TWIST! Safe Lifting Techniques Safety Tip #6 Don't learn safety of this safety tip sheet. Please refrain from reading the information verbatim--paraphrase it instead

    Minnesota, University of

    439

    Safety First Safety Last Safety Always Roughly one out of every four accidents (25%) involves  

    E-Print Network [OSTI]

    Safety First Safety Last Safety Always Roughly one out of every four accidents (25%) involves at an unsafe speed · Failure to check mirrors often Fleet Safety: Backing Accidents Safety Tip #2 Accidents hurt-- safety doesn't. All backing accidents are preventable. The key is to plan ahead to avoid backing

    Minnesota, University of

    440

    Independent Oversight Review, Portsmouth Gaseous Diffusion Plant -  

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

    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

    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

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

    SciTech Connect (OSTI)

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

    Borsheim, G.L.

    1993-09-01T23:59:59.000Z

    442

    Beamline Safety Design Review Steering Committee Charter  

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

    443

    Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement  

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

    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

    444

    Appendix F Cultural Resources, Including  

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

    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

    445

    Reactor Safety Research Programs  

    SciTech Connect (OSTI)

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

    Edler, S. K.

    1981-07-01T23:59:59.000Z

    446

    Safety for Users  

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

    Safety for Users Safety for Users Safety for Users Print Safety at the ALS The mission of the ALS is "Support users in doing outstanding science in a safe environment." All users and staff participate in creating a culture and environment where performing research using the proper safeguards and fulfilling all safety requirements result in the success of the facility and its scientific program. The documents and guidance below will assist users and staff to achieve these goals. How Do I...? A series of fact sheets that explain what users need to know and do when preparing to conduct experiments at the ALS. Complete Experiment Safety Documentation? Work with Biological Materials? Work with Chemicals? Work with Regulated Soil? Bring and Use Electrical Equipment at the ALS?

    447

    Combustion Safety Overview  

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

    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

    448

    Safety at CERN  

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

    449

    Safety | Argonne National Laboratory  

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

    450

    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

    451

    The LBB methodology application results performed on the safety related piping of NPP V-1 in Jaslovske Bohunice  

    SciTech Connect (OSTI)

    A broad overview of the leak before break (LBB) application to the Slovakian V-1 nuclear power plant is presented in the paper. LBB was applied to the primary cooling circuit and surge lines of both WWER 440 type units, and also used to assess the integrity of safety related piping in the feed water and main steam systems. Experiments and calculations performed included analyses of stresses, material mechanical properties, corrosion, fatigue damage, stability of heavy component supports, water hammer, and leak rates. A list of analysis results and recommendations are included in the paper.

    Kupca, L.; Beno, P. [Nuclear Power Plants Research Institute, Trnava (Slovakia)

    1997-04-01T23:59:59.000Z

    452

    Tutorial on nuclear thermal propulsion safety for Mars  

    SciTech Connect (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

    453

    Tutorial on nuclear thermal propulsion safety for Mars  

    SciTech Connect (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

    454

    Hydrogen Technologies Safety Guide  

    SciTech Connect (OSTI)

    The purpose of this guide is to provide basic background information on hydrogen technologies. It is intended to provide project developers, code officials, and other interested parties the background information to be able to put hydrogen safety in context. For example, code officials reviewing permit applications for hydrogen projects will get an understanding of the industrial history of hydrogen, basic safety concerns, and safety requirements.

    Rivkin, C.; Burgess, R.; Buttner, W.

    2015-01-01T23:59:59.000Z

    455

    Safety of Decommissioning of Nuclear Facilities  

    SciTech Connect (OSTI)

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

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

    2008-01-15T23:59:59.000Z

    456

    Waste Isolation Pilot Plant Annual Site Environmental Report for 2012  

    SciTech Connect (OSTI)

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2012 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year; Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS).

    None

    2013-09-01T23:59:59.000Z

    457

    DOE Explosives Safety Manual  

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

    This Manual describes DOE's explosives safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives.

    1996-03-29T23:59:59.000Z

    458

    Gas Safety Law (Florida)  

    Broader source: Energy.gov [DOE]

    This law authorizes the establishment of rules and regulations covering the design, fabrication, installation, inspection, testing and safety standards for installation, operation and maintenance...

    459

    Pipeline Safety (South Dakota)  

    Broader source: Energy.gov [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...

    460

    Pipeline Safety (Maryland)  

    Broader source: Energy.gov [DOE]

    The Public Service Commission has the authority enact regulations pertaining to pipeline safety. These regulations address pipeline monitoring, inspections, enforcement, and penalties.

    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

    Dam Safety Program (Florida)  

    Broader source: Energy.gov [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 ...

    462

    Mine Safety & Health Specialist  

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as the Carlsbad Field Office (CBFO) Mine Safety & Health Specialist and is primarily responsible for inspecting and evaluating the performance...

    463

    Safety & Quality Assurance  

    Broader source: Energy.gov [DOE]

    Together, our Facility Operations Division and Engineering, Safety and Quality Division work to ensure EM conducts its operations and cleanup safely through sound practices. These divisions ensure...

    464

    FACILITY SAFETY (FS)  

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

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

    465

    Occupational Safety Performance  

    Office of Environmental Management (EM)

    this report (July 2012). All data has not yet been submitted to CAIRS. 1 Occupational Safety Performance Comparable Industry, Average TRC Rate Comparable Industry, Average DART...

    466

    Coiled Tubing Safety Manual  

    SciTech Connect (OSTI)

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

    Crow, W.

    1999-04-06T23:59:59.000Z

    467

    Aviation Management and Safety  

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

    To establish a policy framework that will ensure safety, efficiency and effectiveness of government or contractor aviation operations. Cancels DOE O 440.2B.

    2011-06-15T23:59:59.000Z

    468

    Laboratory Safety Manual Office of Environment, Health and Safety  

    E-Print Network [OSTI]

    Prevention Plan is a key step in strengthening the safety culture in laboratories. The UCLA Injury#12;Laboratory Safety Manual Office of Environment, Health and Safety December 201 #12;UCLA Laboratory Safety Manual Introduction Laboratory safety is an integral part of laboratory research

    Jalali. Bahram

    469

    Safety Criteria and Safety Lifecycle for Artificial Neural Networks  

    E-Print Network [OSTI]

    Safety Criteria and Safety Lifecycle for Artificial Neural Networks Zeshan Kurd, Tim Kelly and Jim performance based techniques that aim to improve the safety of neural networks for safety critical applications. However, many of these techniques provide inadequate forms of safety arguments required

    Kelly, Tim

    470

    Aviation Safety + Security Program GLOBAL EXPERTS IN SAFETY MANAGEMENT SYSTEMS  

    E-Print Network [OSTI]

    2011- 2012 Aviation Safety + Security Program GLOBAL EXPERTS IN SAFETY MANAGEMENT SYSTEMS of aviation safety. Endings signal new beginnings and new beginnings mean evolving challenges for safety. This was the world in which the USC Aviation Safety and Security Program was born in 1952 and this is the world

    Wang, Hai

    471

    Public Safety Team (PST) Organizational Structure for Public Safety Management  

    E-Print Network [OSTI]

    Public Safety Team (PST) President Organizational Structure for Public Safety Management for public safety· Coordinates public communications, legal,· and IT support for public safety Maintains· response to safety issues involving individual students and student behavior Ensures appropriate

    472

    Aviation Safety + Security Program GLOBAL EXPERTS IN SAFETY MANAGEMENT SYSTEMS  

    E-Print Network [OSTI]

    2010- 2011 Aviation Safety + Security Program GLOBAL EXPERTS IN SAFETY MANAGEMENT SYSTEMS Relevance and currency -- that is what drives the Aviation Safety and Security Program of the USC Viterbi that our core course, Aviation Safety Management Systems, is so necessary in ensuring the safety

    Wang, Hai

    473

    Food Safety and Technology Food Safety and Technology  

    E-Print Network [OSTI]

    Food Safety and Technology Food Safety and Technology Institute for Food Safety and Health IIT Program Manager: Renee McBrien The Institute for Food Safety and Health (IFSH), with IIT faculty, U ground for individuals seeking graduate edu- cation in food safety and technology and food process

    Heller, Barbara

    474

    SEAS Safety Program SEAS SAFETY PROGRAM 2013-2014  

    E-Print Network [OSTI]

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

    475

    SEAS Safety Program SEAS SAFETY PROGRAM 2012-2103  

    E-Print Network [OSTI]

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

    476

    The Office of Health, Safety and Security  

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

    477

    Nuclear Safety Enforcement Documents | Department of Energy  

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

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

    478

    Fire Safety Tests for Cesium-Loaded Spherical Resorcinol Formaldehyde Resin: Data Summary Report  

    SciTech Connect (OSTI)

    A draft safety evaluation of the scenario for spherical resorcinol formaldehyde (SRF) resin fire inside the ion exchange column was performed by the Hanford Tank Waste Treatment and Immobilization Plant (WTP) Fire Safety organization. The result of this draft evaluation suggested a potential change of the fire safety classification for the Cesium Ion Exchange Process System (CXP) emergency elution vessels, equipment, and piping. To resolve this question, the fire properties of the SRF resin were measured by Southwest Research Institute (SwRI) through a subcontract managed by Pacific Northwest National Laboratory (PNNL). The results of initial fire safety tests on the SRF resin were documented in a previous report (WTP-RPT-218). The present report summarizes the results of additional tests performed by SwRI on the cesium-loaded SRF resin. The efforts by PNNL were limited to summarizing the test results provided by SwRI into one consolidated data report. The as-received SwRI report is attached to this report in the Appendix A. Where applicable, the precision and bias of each test method, as given by each American Society for Testing and Materials (ASTM) standard procedure, are included and compared with the SwRI test results of the cesium-loaded SRF resin.

    Kim, Dong-Sang; Schweiger, Michael J.; Peterson, Reid A.

    2012-09-01T23:59:59.000Z

    479

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

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

    What Does Self-Assessment of Safety Culture Look Like? Discussion What 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 Plant Perspective September 20, 2013 Presenter: Dr. Suzanne Helfinstine, Staff Engineer High Reliability Operations B&W Pantex Pantex Plant Topic covered: Pantex on a journey to become a High Reliability Organization (HRO) Understanding our culture provides feedback on our progress in the HRO journey - Initial survey provides a baseline Pilot site for safety culture self assessment to support EFCOG (Safety Culture Task Group, 2009) and DOE initiative (Ref. Implementation Plan for DNFSB Recommendation 2011-1, Section 5.2.2) What Does Self-Assessment of Safety Culture Look Like? Discussion from the

    480

    NATIONAL WEATHER SERVICE - Lightning Safety  

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

    NATIONAL WEATHER SERVICE - Lightning Safety Lightning: What You Need to Know * NO PLACE outside is safe when thunderstorms are in the area!! * If you hear thunder, lightning is close enough to strike you. * When you hear thunder, immediately move to safe shelter: a substantial building with electricity or plumbing or an enclosed, metal-topped vehicle with windows up. * Stay in safe shelter at least 30 minutes after you hear the last sound of thunder. Indoor Lightning Safety * Stay off corded phones, computers and other electrical equipment that put you in direct contact with electricity. * Avoid plumbing, including sinks, baths and faucets. * Stay away from windows and doors, and stay off porches. * Do not lie on concrete floors, and do not lean against concrete walls.

    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.


    481

    Radiation Safety Work Control Form  

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

    Radiation Safety Work Control Form Radiation Safety Work Control Form (see instructions on pg-2) Rev July-2012 Area: Form #: Date: Preliminary Applicability Screen: (a) Will closing the beam line injection stoppers mitigate the radiological hazards introduced by the proposed work? Yes No (b) Can the closed state of the beam line injection stoppers be assured during the proposed work (ie., work does NOT involve injection stoppers or associated HPS)? Yes No If the answers to both questions are yes, the work can be performed safely under an SSRL RSWCF. If the answer to either question is no, then the work must be performed under a SPEAR3 RSWCF. Section 1: Description of work to be done, including date and time. (Person Responsible completes section)

    482

    The Politically Correct Nuclear Energy Plant  

    E-Print Network [OSTI]

    The Politically Correct Nuclear Energy Plant Andrew C. Kadak Massachusetts Institute of Technology - Small is Beautiful · Nuclear Energy - But Getting Better #12;Politically Correct ! · Natural Safety is a bad idea. · There is no new nuclear energy plant that is competitive at this time. · De-regulation did

    483

    VVER safety research: the COVERS project  

    Science Journals Connector (OSTI)

    In the VVER operating countries, as in a number of European Union (EU) countries, the share of nuclear power in the total energy generation is significant. The safety and reliability of VVER operation is therefore not only the key requirement imposed for the prevention of possible radiological accidents, but is also dictated by economic aspects. The Co-ordination Action – 'VVER Safety Research' (COVERS) project was opened on 1 April 2005 (planned to run for 36 months) with the objective of improving the professional and communication environment necessary to ensure continued safe and efficient operation of Nuclear Power Plants (NPPs) with VVER-440 and VVER-1000 reactors. The project coordination activities cover important areas such as operational safety, materials and equipment ageing, and information and knowledge management, so that the shared information will contribute not only to the enhancement of the plants' safety, but also to their operational efficiency. Effective experience and information exchanges between participating organisations and end-users are based on appropriate communication tools. Significant attention is paid to the task of integrating the resulting information with that accumulated in the countries outside of the EU (Bulgaria, Ukraine, Russia), which operate a large number of VVER reactors.

    Ivo Vasa

    2009-01-01T23:59:59.000Z

    484

    Aerial Work Platform Safety Program  

    E-Print Network [OSTI]

    Aerial Work Platform Safety Program Updated: July 22, 2013 #12;Aerial Work Platform Safety Program ..........................................................................................................11 #12;Aerial Work Platform Safety Program 1 The official version of this information will only for establishing and maintaining the Aerial Work Platform Safety Program. Appropriate safety equipment (e

    Holland, Jeffrey

    485

    SEAS LABORATORY SAFETY OFFICER ORIENTATION  

    E-Print Network [OSTI]

    Investigators. Safety Officers work to develop safety procedures, educate research personnel, identify safety who no longer work in lab Note: Online General Lab Safety and Lab Biosafety courses replace classroom) #12;If assigned by PI, work with other experienced personnel in lab to conduct lab-specific safety

    486

    Final environmental impact statement. Waste Isolation Pilot Plant  

    SciTech Connect (OSTI)

    This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)

    Not Available

    1980-10-01T23:59:59.000Z

    487

    Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project  

    SciTech Connect (OSTI)

    The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL reduce its overall utility costs by decreasing the amount of fuel used to generate steam. Reduced fuel consumption also decreased air emissions. These improvements also helped lower the risk of burn injuries to workers and helped prevent shrapnel injuries resulting from missiles produced by pressurized component failures. In most cases, the economic benefit and cost effectiveness of the SPRS Safety and Energy Efficiency Improvement Project is reflected in payback periods of 1 year or less.

    Lower, Mark D [ORNL; Christopher, Timothy W [ORNL; Oland, C Barry [ORNL

    2011-06-01T23:59:59.000Z

    488

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

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

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

    489

    Occupational Hygiene & Chemical Safety Division Department of Environmental Health & Safety  

    E-Print Network [OSTI]

    Occupational Hygiene & Chemical Safety Division Department of Environmental Health & Safety Risk all connections and fittings prior to start of anesthesia. Carefully pour Isoflurane from Environmental Health & Safety before re-entering the laboratory. REFERENCES 1. Procedure

    Machel, Hans

    490

    Safety of Accelerator Facilities  

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

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

    2001-01-08T23:59:59.000Z

    491

    Safety of Accelerator Facilities  

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

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

    2004-07-23T23:59:59.000Z

    492

    Safety of Accelerator Facilities  

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

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

    2011-07-21T23:59:59.000Z

    493

    EFCOG / DOE Electrical Safety  

    E-Print Network [OSTI]

    of electrical hazards used in the DOE Electrical Safety Handbook and laboratory programs. Thus, portionsEFCOG / DOE Electrical Safety Improvement Project Project Area 4 ­Performance Measurement personnel. This tool is also intended to assist DOE organizations in determining and classifying ORPS

    494

    DOE HANDBOOK ELECTRICAL SAFETY  

    E-Print Network [OSTI]

    DOE HANDBOOK ELECTRICAL SAFETY U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1092 and others guidance for the "Analyze the Hazard" step of DOE's Integrated Safety Management (ISM

    495

    Evaluation of temporary non-code repairs in safety class 3 piping systems  

    SciTech Connect (OSTI)

    Temporary non-ASME Code repairs in safety class 3 pipe and piping components are permissible during plant operation in accordance with Nuclear Regulatory Commission Generic Letter 90-05. However, regulatory acceptance of such repairs requires the licensee to undertake several timely actions. Consistent with the requirements of GL 90-05, this paper presents an overview of the detailed evaluation and relief request process. The technical criteria encompasses both ductile and brittle piping materials. It also lists appropriate evaluation methods that a utility engineer can select to perform a structural integrity assessment for design basis loading conditions to support the use of temporary non-Code repair for degraded piping components. Most use of temporary non-code repairs at a nuclear generating station is in the service water system which is an essential safety related system providing the ultimate heat sink for various plant systems. Depending on the plant siting, the service water system may use fresh water or salt water as the cooling medium. Various degradation mechanisms including general corrosion, erosion/corrosion, pitting, microbiological corrosion, galvanic corrosion, under-deposit corrosion or a combination thereof continually challenge the pressure boundary structural integrity. A good source for description of corrosion degradation in cooling water systems is provided in a cited reference.

    Godha, P.C.; Kupinski, M.; Azevedo, N.F. [Northeast Utilities System, Hartford, CT (United States)

    1996-12-01T23:59:59.000Z

    496

    ARM - ARM Safety Policy  

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

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

    497

    H. UNREVIEWED SAFETY QUESTIONS  

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

    Department of Energy Pt. 835 H. UNREVIEWED SAFETY QUESTIONS 1. The USQ process is an important tool to evaluate whether changes affect the safety basis. A contractor must use the USQ proc- ess to ensure that the safety basis for a DOE nuclear facility is not undermined by changes in the facility, the work performed, the associated hazards, or other factors that support the adequacy of the safety basis. 2. The USQ process permits a contractor to make physical and procedural changes to a nuclear facility and to conduct tests and ex- periments without prior approval, provided these changes do not cause a USQ. The USQ process provides a contractor with the flexi- bility needed to conduct day-to-day oper- ations by requiring only those changes and tests with a potential to impact the safety

    498

    Argonne CNM: Safety Training  

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

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

    499

    VPP Safety Share  

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

    VPP Safety Share VPP Safety Share BlackBerry Safety Brice Cook, HS-1.3 July 22, 2010 2 BlackBerry Safety * Use only approved batteries with your BlackBerry device. * Use of batteries that have not been approved by Research In Motion might present a risk of fire or explosion, which could cause serious harm, death, or property loss. * Use only RIM approved chargers. * Use of chargers that have not been approved by RIM might present a risk of fire or explosion, which could caus