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1

FY 2006 ANNUAL REVIEW-SALTSTONE DISPOSAL FACILITY PERFORMANCE ASSESSMENT  

SciTech Connect (OSTI)

The Z-Area Saltstone Disposal Facility (SDF) consists of two disposal units, Vaults 1 and 4, described in the Performance Assessment (PA) (WSRC 1992). The FY06 PA Annual Review concludes that both vaults contain much lower levels of radionuclides (curies) than that allowed by the PA. The PA controls established to govern waste operations and monitor disposal facility performance are determined to be adequate.

Crapse, K; Benjamin Culbertson, B

2007-03-15T23:59:59.000Z

2

Performance assessment for the class L-II disposal facility  

SciTech Connect (OSTI)

This draft radiological performance assessment (PA) for the proposed Class L-II Disposal Facility (CIIDF) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US Department of Energy Order 5820.2A. This PA considers the disposal of low-level radioactive wastes (LLW) over the operating life of the facility and the long-term performance of the facility in providing protection to public health and the environment. The performance objectives contained in the order require that the facility be managed to accomplish the following: (1) Protect public health and safety in accordance with standards specified in environmental health orders and other DOE orders. (2) Ensure that external exposure to the waste and concentrations of radioactive material that may be released into surface water, groundwater, soil, plants, and animals results in an effective dose equivalent (EDE) that does not exceed 25 mrem/year to a member of the public. Releases to the atmosphere shall meet the requirements of 40 CFR Pt. 61. Reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment as low as reasonably achievable. (1) Ensure that the committed EDEs received by individual who inadvertently may intrude into the facility after the loss of active institutional control (100 years) will not exceed 100 mrem/year for continuous exposure of 500 mrem for a single acute exposure. (4) Protect groundwater resources, consistent with federal, state, and local requirements.

NONE

1997-03-01T23:59:59.000Z

3

Near-Field Hydrology Data Package for the Integrated Disposal Facility 2005 Performance Assessment  

SciTech Connect (OSTI)

CH2MHill Hanford Group, Inc. (CHG) is designing and assessing the performance of an Integrated Disposal Facility (IDF) to receive immobilized low-activity waste (ILAW), Low-Level and Mixed Low-Level Wastes (LLW/MLLW), and the Waste Treatment Plant (WTP) melters used to vitrify the ILAW. The IDF Performance Assessment (PA) assesses the performance of the disposal facility to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface water resources, and inadvertent intruders. The PA requires prediction of contaminant migration from the facilities, which is expected to occur primarily via the movement of water through the facilities and the consequent transport of dissolved contaminants in the pore water of the vadose zone. Pacific Northwest National Laboratory (PNNL) assists CHG in its performance assessment activities. One of PNNL’s tasks is to provide estimates of the physical, hydraulic, and transport properties of the materials comprising the disposal facilities and the disturbed region around them. These materials are referred to as the near-field materials. Their properties are expressed as parameters of constitutive models used in simulations of subsurface flow and transport. In addition to the best-estimate parameter values, information on uncertainty in the parameter values and estimates of the changes in parameter values over time are required to complete the PA. These parameter estimates and information were previously presented in a report prepared for the 2001 ILAW PA. This report updates the parameter estimates for the 2005 IDF PA using additional information and data collected since publication of the earlier report.

Meyer, Philip D.; Saripalli, Prasad; Freedman, Vicky L.

2004-06-25T23:59:59.000Z

4

Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

2012-05-01T23:59:59.000Z

5

High Performance Computing Facility Operational Assessment, FY 2010 Oak Ridge Leadership Computing Facility  

SciTech Connect (OSTI)

Oak Ridge National Laboratory's (ORNL's) Cray XT5 supercomputer, Jaguar, kicked off the era of petascale scientific computing in 2008 with applications that sustained more than a thousand trillion floating point calculations per second - or 1 petaflop. Jaguar continues to grow even more powerful as it helps researchers broaden the boundaries of knowledge in virtually every domain of computational science, including weather and climate, nuclear energy, geosciences, combustion, bioenergy, fusion, and materials science. Their insights promise to broaden our knowledge in areas that are vitally important to the Department of Energy (DOE) and the nation as a whole, particularly energy assurance and climate change. The science of the 21st century, however, will demand further revolutions in computing, supercomputers capable of a million trillion calculations a second - 1 exaflop - and beyond. These systems will allow investigators to continue attacking global challenges through modeling and simulation and to unravel longstanding scientific questions. Creating such systems will also require new approaches to daunting challenges. High-performance systems of the future will need to be codesigned for scientific and engineering applications with best-in-class communications networks and data-management infrastructures and teams of skilled researchers able to take full advantage of these new resources. The Oak Ridge Leadership Computing Facility (OLCF) provides the nation's most powerful open resource for capability computing, with a sustainable path that will maintain and extend national leadership for DOE's Office of Science (SC). The OLCF has engaged a world-class team to support petascale science and to take a dramatic step forward, fielding new capabilities for high-end science. This report highlights the successful delivery and operation of a petascale system and shows how the OLCF fosters application development teams, developing cutting-edge tools and resources for next-generation systems.

Bland, Arthur S Buddy [ORNL; Hack, James J [ORNL; Baker, Ann E [ORNL; Barker, Ashley D [ORNL; Boudwin, Kathlyn J. [ORNL; Kendall, Ricky A [ORNL; Messer, Bronson [ORNL; Rogers, James H [ORNL; Shipman, Galen M [ORNL; White, Julia C [ORNL

2010-08-01T23:59:59.000Z

6

NERSC 2011: High Performance Computing Facility Operational Assessment for the National Energy Research Scientific Computing Center  

E-Print Network [OSTI]

NERSC 2011 High Performance Computing Facility Operationalby providing high-performance computing, information, data,s deep knowledge of high performance computing to overcome

Antypas, Katie

2013-01-01T23:59:59.000Z

7

Radiological performance assessment for the Z-Area Saltstone Disposal Facility  

SciTech Connect (OSTI)

This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements.

Cook, J.R.; Fowler, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States)

1992-12-18T23:59:59.000Z

8

Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site  

SciTech Connect (OSTI)

The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

Baer, T.A.; Emery, J.N. [GRAM, Inc., Albuquerque, NM (United States); Price, L.L. [Science Applications International Corp., Albuquerque, NM (United States); Olague, N.E. [Sandia National Labs., Albuquerque, NM (United States)

1994-04-01T23:59:59.000Z

9

E AREA LOW LEVEL WASTE FACILITY DOE 435.1 PERFORMANCE ASSESSMENT  

SciTech Connect (OSTI)

This Performance Assessment for the Savannah River Site E-Area Low-Level Waste Facility was prepared to meet requirements of Chapter IV of the Department of Energy Order 435.1-1. The Order specifies that a Performance Assessment should provide reasonable assurance that a low-level waste disposal facility will comply with the performance objectives of the Order. The Order also requires assessments of impacts to water resources and to hypothetical inadvertent intruders for purposes of establishing limits on radionuclides that may be disposed near-surface. According to the Order, calculations of potential doses and releases from the facility should address a 1,000-year period after facility closure. The point of compliance for the performance measures relevant to the all pathways and air pathway performance objective, as well as to the impact on water resources assessment requirement, must correspond to the point of highest projected dose or concentration beyond a 100-m buffer zone surrounding the disposed waste following the assumed end of active institutional controls 100 years after facility closure. During the operational and institutional control periods, the point of compliance for the all pathways and air pathway performance measures is the SRS boundary. However, for the water resources impact assessment, the point of compliance remains the point of highest projected dose or concentration beyond a 100-m buffer zone surrounding the disposed waste during the operational and institutional control periods. For performance measures relevant to radon and inadvertent intruders, the points of compliance are the disposal facility surface for all time periods and the disposal facility after the assumed loss of active institutional controls 100 years after facility closure, respectively. The E-Area Low-Level Waste Facility is located in the central region of the SRS known as the General Separations Area. It is an elbow-shaped, cleared area, which curves to the northwest, situated immediately north of the Mixed Waste Management Facility. The E-Area Low-Level Waste Facility is comprised of 200 acres for waste disposal and a surrounding buffer zone that extends out to the 100-m point of compliance. Disposal units within the footprint of the low-level waste facilities include the Slit Trenches, Engineered Trenches, Component-in-Grout Trenches, the Low-Activity Waste Vault, the Intermediate-Level Vault, and the Naval Reactor Component Disposal Area. Radiological waste disposal operations at the E-Area Low-Level Waste Facility began in 1994. E-Area Low-Level Waste Facility closure will be conducted in three phases: operational closure, interim closure, and final closure. Operational closure will be conducted during the 25-year operation period (30-year period for Slit and Engineered Trenches) as disposal units are filled; interim closure measures will be taken for some units. Interim closure will take place following the end of operations and will consist of an area-wide runoff cover along with additional grading over the trench units. Final closure of all disposal units in the E-Area Low-Level Waste Facility will take place at the end of the 100-year institutional control period and will consist of the installation of an integrated closure system designed to minimize moisture contact with the waste and to serve as a deterrent to intruders. Radiological dose to human receptors is analyzed in this PA in the all-pathways analysis, the inadvertent intruder analysis and the air pathway analysis, and the results are compared to the relevant performance measures. For the all-pathways analysis, the performance measure of relevance is a 25-mrem/yr EDE to representative members of the public, excluding dose from radon and its progeny in air. For the inadvertent intruder, the applicable performance measures are 100-mrem/yr EDE and 500 mrem/yr EDE for chronic and exposure scenarios, respectively. The relevant performance measure for the air pathway is 10-mrem/yr EDE via the air pathway, excluding dose from radon and its progeny in air. Protecti

Wilhite, E

2008-03-31T23:59:59.000Z

10

Surficial geology and performance assessment for a Radioactive Waste Management Facility at the Nevada Test Site  

SciTech Connect (OSTI)

At the Nevada Test Site, one potentially disruptive scenario being evaluated for the Greater Confinement Disposal (GCD) Facility Performance Assessment is deep post-closure erosion that would expose buried radioactive waste to the accessible environment. The GCD Facility located at the Area 5 Radioactive Waste Management Site (RWMS) lies at the juncture of three alluvial fan systems. Geomorphic surface mapping in northern Frenchman Flat indicates that reaches of these fans where the RWMS is now located have been constructional since at least the middle Quaternary. Mapping indicates a regular sequence of prograding fans with entrenchment of the older fan surfaces near the mountain fronts and construction of progressively younger inset fans farther from the mountain fronts. At the facility, the oldest fan surfaces are of late Pleistocene and Holocene age. More recent geomorphic activity has been limited to erosion and deposition along small channels. Trench and pit wall mapping found maximum incision in the vicinity of the RWMS to be less than 1.5 m. Based on collected data, natural geomorphic processes are unlikely to result in erosion to a depth of more than approximately 2 m at the facility within the 10,000-year regulatory period.

Snyder, K.E. [Lockheed Environmental Systems and Technologies, Co., Las Vegas, NV (United States); Gustafson, D.L.; Huckins-Gang, H.E.; Miller, J.J.; Rawlinson, S.E. [Raytheon Services Nevada, Las Vegas, NV (United States)

1995-02-01T23:59:59.000Z

11

NUMERICAL FLOW AND TRANSPORT SIMULATIONS SUPPORTING THE SALTSTONE FACILITY PERFORMANCE ASSESSMENT  

SciTech Connect (OSTI)

The Saltstone Disposal Facility Performance Assessment (PA) is being revised to incorporate requirements of Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), and updated data and understanding of vault performance since the 1992 PA (Cook and Fowler 1992) and related Special Analyses. A hybrid approach was chosen for modeling contaminant transport from vaults and future disposal cells to exposure points. A higher resolution, largely deterministic, analysis is performed on a best-estimate Base Case scenario using the PORFLOW numerical analysis code. a few additional sensitivity cases are simulated to examine alternative scenarios and parameter settings. Stochastic analysis is performed on a simpler representation of the SDF system using the GoldSim code to estimate uncertainty and sensitivity about the Base Case. This report describes development of PORFLOW models supporting the SDF PA, and presents sample results to illustrate model behaviors and define impacts relative to key facility performance objectives. The SDF PA document, when issued, should be consulted for a comprehensive presentation of results.

Flach, G.

2009-02-28T23:59:59.000Z

12

Development of an ASTM standard guide on performing vulnerability assessments for nuclear facilities  

SciTech Connect (OSTI)

This paper describes an effort undertaken by subcommittee C26.12 (Safeguards) of the American Society for Testing and Materials (ASTM) to develop a standard guide for performing vulnerability assessments (VAs). VAs are performed to determine the effectiveness of safeguards and security systems for both domestic and international nuclear facilities. These assessments address a range of threats, including theft of nuclear material and sabotage, and use an array of methods. The approach to performing and documenting VAs is varied and is largely dependent upon the tools used to perform them. This diversity can lead to tools being misused, making validation of VAs more difficult. The development of a standard guide for performing VAs would, if generally accepted, alleviate these concerns. ASTM provides a forum for developing guides that includes a high level of peer review to assure that the result is acceptable to all potential users. Additionally, the ASTM is widely recognized for setting standards, and endorsement by the Society may increase the likelihood of acceptance by the nuclear community. The goal of this work is to develop a guide that is independent of the tools being used to perform the VA and applicable to the spectrum of threats described above.

Wilkey, D.D.

1995-09-01T23:59:59.000Z

13

Geochemical Data Package for the 2005 Hanford Integrated Disposal Facility Performance Assessment  

SciTech Connect (OSTI)

CH2M HILL Hanford Group, Inc. (CH2M HILL) is designing and assessing the performance of an integrated disposal facility (IDF) to receive low-level waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and failed or decommissioned melters. The CH2M HILL project to assess the performance of this disposal facility is the Hanford IDF Performance Assessment (PA) activity. The goal of the Hanford IDF PA activity is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the vadose zone to groundwater where contaminants may be re-introduced to receptors via drinking water wells or mixing in the Columbia River. Pacific Northwest National Laboratory (PNNL) assists CH2M HILL in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the IDF, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (Kd) and the thermodynamic solubility product (Ksp), respectively. In this data package, we approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. The Kd values and solution concentration limits for each contaminant are direct inputs to subsurface flow and transport codes used to predict the performance of the IDF system. In addition to the best-estimate Kd values, a reasonable conservative value and a range are provided. The data package does not list estimates for the range in solubility limits or their uncertainty. However, the data package does provide different values for both the Kd values and solution concentration limits for different spatial zones in the IDF system and does supply time-varying Kd values for the cement solidified waste. The Kd values and solution concentration limits presented for each contaminant were previously presented in a report prepared by Kaplan and Serne (2000) for the 2001 ILAW PA, and have been updated to include applicable data from investigations completed since the issuance of that report and improvements in our understanding of the geochemistry specific to Hanford. A discussion is also included of the evolution of the Kd values recommended from the original 1999 ILAW PA through the 2001 ILAW and 2003 Supplement PAs to the current values to be used for the 2005 IDF PA for the key contaminants of concern: Cr(VI), nitrate, 129I, 79Se, 99Tc, and U(VI). This discussion provides the rationale for why certain Kd have changed with time.

Krupka, Kenneth M.; Serne, R JEFFREY.; Kaplan, D I.

2004-09-30T23:59:59.000Z

14

Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610  

SciTech Connect (OSTI)

The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling input parameters associated with the modeled features, both initial values (at the time of facility closure) and degradation rates/values. During the development of the PA, evaluations are conducted to reflect not only the results associated with the best available information at the time but also to evaluate potential uncertainties and sensitivities associated with the modeled system. While the PA will reflect the modeled system results from the best available information, it will also identify areas for future work to reduce overall PA uncertainties moving forward. DOE requires a PA Maintenance Program such that work continues to reduce model uncertainties, thus bolstering confidence in PA results that support regulatory decisions. This maintenance work may include new Research and Development activities or modeling as informed by previous PA results and other new information that becomes available. As new information becomes available, it is evaluated against previous PAs and appropriate actions are taken to ensure continued confidence in the regulatory decisions. Therefore, the PA program is a continual process that is not just the development of a PA but seeks to incorporate new information to reduce overall model uncertainty and provide continuing confidence in regulatory decisions. (author)

Rosenberger, Kent H. [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)] [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

15

Program Plan for Revision of the Z-Area Saltstone Disposal Facility Performance Assessment  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) and the Saltstone Project, are embarking on the next revision to the Saltstone Disposal Facility (SDF) performance assessment (PA). This program plan has been prepared to outline the general approach, scope, schedule and resources for the PA revision. The plan briefly describes the task elements of the PA process. It discusses critical PA considerations in the development of conceptual models and interpretation of results. Applicable quality assurance (QA) requirements are identified and the methods for implementing QA for both software and documentation are described. The plan identifies project resources supporting the core team and providing project oversight. Program issues and risks are identified as well as mitigation of those risks. Finally, a preliminary program schedule has been developed and key deliverables identified. A number of significant changes have been implemented since the last PA revision resulting in a new design for future SDF disposal units. This revision will encompass the existing and planned disposal units, PA critical radionuclides and exposure pathways important to SDF performance. An integrated analysis of the overall facility layout, including all disposal units, will be performed to assess the impact of plume overlap on PA results. Finally, a rigorous treatment of uncertainty will be undertaken using probabilistic simulations. This analysis will be reviewed and approved by DOE-SR, DOE-HQ and potentially the Nuclear Regulatory Commission (NRC). This revision will be completed and ready for the start of the DOE review at the end of December 2006. This work supports a Saltstone Vault 2 fee-bearing milestone. This milestone includes completion of the Vault 2 module of the PA revision by the end of FY06.

Cook, James R.

2005-12-07T23:59:59.000Z

16

Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment  

SciTech Connect (OSTI)

This data package documents the experimentally derived input data on the representative waste glasses; LAWA44, LAWB45, and LAWC22. This data will be used for Subsurface Transport Over Reactive Multi-phases (STORM) simulations of the Integrated Disposal Facility (IDF) for immobilized low-activity waste (ILAW). The STORM code will be used to provide the near-field radionuclide release source term for a performance assessment to be issued in July 2005. Documented in this data package are data related to 1) kinetic rate law parameters for glass dissolution, 2) alkali (Na+)-hydrogen (H+) ion exchange rate, 3) chemical reaction network of secondary phases that form in accelerated weathering tests, and 4) thermodynamic equilibrium constants assigned to these secondary phases. The kinetic rate law and Na+-H+ ion exchange rate were determined from single-pass flow-through experiments. Pressurized unsaturated flow (PUF) and product consistency (PCT) tests where used for accelerated weathering or aging of the glasses in order to determine a chemical reaction network of secondary phases that form. The majority of the thermodynamic data used in this data package were extracted from the thermody-namic database package shipped with the geochemical code EQ3/6, version 8.0. Because of the expected importance of 129I release from secondary waste streams being sent to IDF from various thermal treatment processes, parameter estimates for diffusional release and solubility-controlled release from cementitious waste forms were estimated from the available literature.

Pierce, Eric M.; McGrail, B. Peter; Rodriguez, Elsa A.; Schaef, Herbert T.; Saripalli, Prasad; Serne, R. Jeffrey; Krupka, Kenneth M.; Martin, P. F.; Baum, Steven R.; Geiszler, Keith N.; Reed, Lunde R.; Shaw, Wendy J.

2004-09-01T23:59:59.000Z

17

Radiological performance assessment for the E-Area Vaults Disposal Facility. Appendices A through M  

SciTech Connect (OSTI)

These document contains appendices A-M for the performance assessment. They are A: details of models and assumptions, B: computer codes, C: data tabulation, D: geochemical interactions, E: hydrogeology of the Savannah River Site, F: software QA plans, G: completeness review guide, H: performance assessment peer review panel recommendations, I: suspect soil performance analysis, J: sensitivity/uncertainty analysis, K: vault degradation study, L: description of naval reactor waste disposal, M: porflow input file. (GHH)

Cook, J.R.

1994-04-15T23:59:59.000Z

18

Enhancing RESRAD-OFFSITE for Low Level Waste Disposal Facility Performance Assessment  

Broader source: Energy.gov [DOE]

Abstract: The RESRAD-OFFSITE code was developed to evaluate the radiological dose and excess cancer risk to an individual who is exposed while located within or outside the area of initial (primary) contamination. The primary contamination, which is the source of all releases modeled by the code, is assumed to be a layer of soil. The code considers the release of contamination from the source to the atmosphere, to surface runoff, and to groundwater. The radionuclide leaching was modeled as a first order (without transport) release using radionuclide distribution coefficient and infiltration rate calculated from water balance (precipitation, surface runoff, evapotranspiration, etc.). Recently, a new source term model was added the RESRAD-OFFSITE code so that it can be applied to the evaluation of Low Level Waste (LLW) disposal facility performance assessment. This new improved source term model include (1) first order with transport, (2) equilibrium desorption (rinse) release, and (3) uniform release (constant dissolution). With these new source release options, it is possible to simulate both uncontainerized (soil) contamination and containerized (waste drums) contamination. A delay time in the source release was also added to the code. This allows modeling the LLW container degradation as a function of time. The RESRAD-OFFSITE code also allows linking to other codes using improved flux and concentration input options. Additional source release model such as diffusion release may be added later. In addition, radionuclide database with 1252 radionuclides (ICRP 107) and the corresponding dose coefficients (DCFPAK 3.02) and the Department of Energy’s new gender- and age-averaged Reference Person dose coefficients (DOE-STD-1196-2011) which is based on the US census data will be added to the next version of RESRAD-OFFSITE code

19

Radiological performance assessment for the E-Area Vaults Disposal Facility  

SciTech Connect (OSTI)

The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

Cook, J.R.; Hunt, P.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1994-04-15T23:59:59.000Z

20

Assessing the Security Vulnerabilities of Correctional Facilities  

SciTech Connect (OSTI)

The National Institute of Justice has tasked their Satellite Facility at Sandia National Laboratories and their Southeast Regional Technology Center in Charleston, South Carolina to devise new procedures and tools for helping correctional facilities to assess their security vulnerabilities. Thus, a team is visiting selected correctional facilities and performing vulnerability assessments. A vulnerability assessment helps to identi~ the easiest paths for inmate escape, for introduction of contraband such as drugs or weapons, for unexpected intrusion fi-om outside of the facility, and for the perpetration of violent acts on other inmates and correctional employees, In addition, the vulnerability assessment helps to quantify the security risks for the facility. From these initial assessments will come better procedures for performing vulnerability assessments in general at other correctional facilities, as well as the development of tools to assist with the performance of such vulnerability assessments.

Morrison, G.S.; Spencer, D.S.

1998-10-27T23:59:59.000Z

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21

Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling  

SciTech Connect (OSTI)

A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.

Phifer, Mark A.; Smith, Frank G. III

2013-06-21T23:59:59.000Z

22

Facility Interface Capability Assessment (FICA) summary report  

SciTech Connect (OSTI)

The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from the commercial facilities. In support of the development of the CRWMS, OCRWM sponsored the Facility Interface Capability Assessment (FICA) project. The objective of this project was to assess the capability of each commercial facility to handle various spent nuclear fuel shipping casks. The purpose of this report is to summarize the results of the facility assessments completed within the FICA project. The project was conducted in two phases. During Phase I, the data items required to complete the facility assessments were identified and the data base for the project was created. During Phase II, visits were made to 122 facilities on 76 sites to collect data and information, the data base was updated, and assessments of the cask-handling capabilities at each facility were performed.

Viebrock, J.M.; Mote, N. [Nuclear Assurance Corp., Norcross, GA (United States); Pope, R.B. [ed.] [Oak Ridge National Lab., TN (United States)

1992-05-01T23:59:59.000Z

23

PUREX facility hazards assessment  

SciTech Connect (OSTI)

This report documents the hazards assessment for the Plutonium Uranium Extraction Plant (PUREX) located on the US Department of Energy (DOE) Hanford Site. Operation of PUREX is the responsibility of Westinghouse Hanford Company (WHC). This hazards assessment was conducted to provide the emergency planning technical basis for PUREX. DOE Order 5500.3A requires an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification. In October of 1990, WHC was directed to place PUREX in standby. In December of 1992 the DOE Assistant Secretary for Environmental Restoration and Waste Management authorized the termination of PUREX and directed DOE-RL to proceed with shutdown planning and terminal clean out activities. Prior to this action, its mission was to reprocess irradiated fuels for the recovery of uranium and plutonium. The present mission is to establish a passively safe and environmentally secure configuration at the PUREX facility and to preserve that condition for 10 years. The ten year time frame represents the typical duration expended to define, authorize and initiate follow-on decommissioning and decontamination activities.

Sutton, L.N.

1994-09-23T23:59:59.000Z

24

NERSC 2011: High Performance Computing Facility Operational Assessment for the National Energy Research Scientific Computing Center  

E-Print Network [OSTI]

tested, and preventive maintenance is scheduled. Safetyand perform preventive maintenance. Review and update

Antypas, Katie

2013-01-01T23:59:59.000Z

25

Annual summary of Immobilized Low-Activity Waste (ILAW) Performance Assessment for 2003 Incorporating the Integrated Disposal Facility Concept  

SciTech Connect (OSTI)

To Erik Olds 09/30/03 - An annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) is necessary in each year in which a full performance assessment is not issued.

MANN, F M

2003-09-01T23:59:59.000Z

26

Summary of Conceptual Models and Data Needs to Support the INL Remote-Handled Low-Level Waste Disposal Facility Performance Assessment and Composite Analysis  

SciTech Connect (OSTI)

An overview of the technical approach and data required to support development of the performance assessment, and composite analysis are presented for the remote handled low-level waste disposal facility on-site alternative being considered at Idaho National Laboratory. Previous analyses and available data that meet requirements are identified and discussed. Outstanding data and analysis needs are also identified and summarized. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of facility performance and of the composite performance are required to meet the Department of Energy’s Low-Level Waste requirements (DOE Order 435.1, 2001) which stipulate that operation and closure of the disposal facility will be managed in a manner that is protective of worker and public health and safety, and the environment. The corresponding established procedures to ensure these protections are contained in DOE Manual 435.1-1, Radioactive Waste Management Manual (DOE M 435.1-1 2001). Requirements include assessment of (1) all-exposure pathways, (2) air pathway, (3) radon, and (4) groundwater pathway doses. Doses are computed from radionuclide concentrations in the environment. The performance assessment and composite analysis are being prepared to assess compliance with performance objectives and to establish limits on concentrations and inventories of radionuclides at the facility and to support specification of design, construction, operation and closure requirements. Technical objectives of the PA and CA are primarily accomplished through the development of an establish inventory, and through the use of predictive environmental transport models implementing an overarching conceptual framework. This document reviews the conceptual model, inherent assumptions, and data required to implement the conceptual model in a numerical framework. Available site-specific data and data sources are then addressed. Differences in required analyses and data are captured as outstanding data needs.

A. Jeff Sondrup; Annette L. Schafter; Arthur S. Rood

2010-09-01T23:59:59.000Z

27

FY2010 ANNUAL REVIEW E-AREA LOW-LEVEL WASTE FACILITY PERFORMANCE ASSESSMENT AND COMPOSITE ANALYSIS  

SciTech Connect (OSTI)

The E-Area Low-Level Waste Facility (ELLWF) consists of a number of disposal units described in the Performance Assessment (PA)(WSRC, 2008b) and Composite Analysis (CA)(WSRC, 1997; WSRC, 1999): Low-Activity Waste (LAW) Vault, Intermediate Level (IL) Vault, Trenches (Slit Trenches [STs], Engineered Trenches [ETs], and Component-in-Grout [CIG] Trenches), and Naval Reactor Component Disposal Areas (NRCDAs). This annual review evaluates the adequacy of the approved 2008 ELLWF PA along with the Special Analyses (SAs) approved since the PA was issued. The review also verifies that the Fiscal Year (FY) 2010 low-level waste (LLW) disposal operations were conducted within the bounds of the PA/SA baseline, the Savannah River Site (SRS) CA, and the Department of Energy (DOE) Disposal Authorization Statement (DAS). Important factors considered in this review include waste receipts, results from monitoring and research and development (R&D) programs, and the adequacy of controls derived from the PA/SA baseline. Sections 1.0 and 2.0 of this review are a summary of the adequacy of the PA/SA and CA, respectively. An evaluation of the FY2010 waste receipts and the resultant impact on the ELLWF is summarized in Section 3.1. The results of the monitoring program, R&D program, and other relevant factors are found in Section 3.2, 3.3 and 3.4, respectively. Section 4.0 contains the CA annual determination similarly organized. SRS low-level waste management is regulated under DOE Order 435.1 (DOE, 1999a) and is authorized under a DAS as a federal permit. The original DAS was issued by the DOE-Headquarters (DOE-HQ) on September 28, 1999 (DOE, 1999b) for the operation of the ELLWF and the Saltstone Disposal Facility (SDF). The 1999 DAS remains in effect for the regulation of the SDF. Those portions of that DAS applicable to the ELLWF were superseded by revision 1 of the DAS on July 15, 2008 (DOE, 2008b). The 2008 PA and DAS were officially implemented by the facility on October 31, 2008 and are the authorization documents for this FY2010 Annual Review. Department of Energy Headquarters approval of the 2008 DAS was subject to numerous conditions specified in the document. Two of those conditions are to update the ELLWF closure plan and monitoring plan to align with the conceptual model analyzed in the PA. Both of these conditions were met with the issuance of the PA Monitoring Plan (Millings, 2009a) and the Closure Plan (Phifer et al, 2009a). The PA Monitoring Plan was approved by DOE on July 22, 2009 and the Closure Plan was approved by DOE on May 21, 2009. Both will be updated as needed to remain consistent with the PA. The DAS also specifies that the maintenance plan include activities to resolve each of the secondary issues identified in the DOEHQ review of the 2008 PA that were not completely addressed either with supplemental material provided to the review team or in final revisions to the PA. These outstanding issues were originally documented in the 2008 update of the PA/CA Maintenance Plan (WSRC, 2008a) and in subsequent PA/CA Maintenance Plans (most recently SRNS, 2010a) as required and are actively being worked.

Butcher, T.; Swingle, R.; Crapse, K.; Millings, M.; Sink, D.

2011-01-01T23:59:59.000Z

28

Privacy Impact Assessment OFEO Facilities Management System Facilities Center  

E-Print Network [OSTI]

Privacy Impact Assessment OFEO Facilities Management System ­ Facilities Center I. System Identification 1. IT System Name: Facilities Management System - FacilityCenter 2. IT System Sponsor: Office. IT System Manager: Michelle T. Gooch, Facilities Management Systems Manager 5. PIA Author: Michelle T. Gooch

Mathis, Wayne N.

29

Energy Performance Contracting in State Facilities | Department...  

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

Contracting in State Facilities Energy Performance Contracting in State Facilities Provides a brief overview of the performance contracting process, the benefits of using...

30

Independent Oversight Assessment, Salt Waste Processing Facility...  

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

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

31

AGING FACILITY WORKER DOSE ASSESSMENT  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate radiation doses received by personnel working in the Aging Facility performing operations to transfer aging casks to the aging pads for thermal and logistical management, stage empty aging casks, and retrieve aging casks from the aging pads for further processing in other site facilities. Doses received by workers due to aging cask surveillance and maintenance operations are also included. The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation from normal operation. There are no Category 1 event sequences associated with the Aging Facility (BSC 2004 [DIRS 167268], Section 7.2.1). The results of this calculation will be used to support the design of the Aging Facility and to provide occupational dose estimates for the License Application. The calculations contained in this document were developed by Environmental and Nuclear Engineering of the Design and Engineering Organization and are intended solely for the use of the Design and Engineering Organization in its work regarding facility operation. Yucca Mountain Project personnel from the Environmental and Nuclear Engineering should be consulted before use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Environmental and Nuclear Engineering.

R.L. Thacker

2005-03-24T23:59:59.000Z

32

Power Systems Development Facility. Environmental Assessment  

SciTech Connect (OSTI)

The objective of the PSDF would be to provide a modular facility which would support the development of advanced, pilot-scale, coal-based power systems and hot gas clean-up components. These pilot-scale components would be designed to be large enough so that the results can be related and projected to commercial systems. The facility would use a modular approach to enhance the flexibility and capability for testing; consequently, overall capital and operating costs when compared with stand-alone facilities would be reduced by sharing resources common to different modules. The facility would identify and resolve technical barrier, as well as-provide a structure for long-term testing and performance assessment. It is also intended that the facility would evaluate the operational and performance characteristics of the advanced power systems with both bituminous and subbituminous coals. Five technology-based experimental modules are proposed for the PSDF: (1) an advanced gasifier module, (2) a fuel cell test module, (3) a PFBC module, (4) a combustion gas turbine module, and (5) a module comprised of five hot gas cleanup particulate control devices. The final module, the PCD, would capture coal-derived ash and particles from both the PFBC and advanced gasifier gas streams to provide for overall particulate emission control, as well as to protect the combustion turbine and the fuel cell.

Not Available

1993-06-01T23:59:59.000Z

33

Superior Energy Performance Industrial Facility Best Practice...  

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

activities, processes or procedures that are "above and beyond" the requirements of ISO 50001. Superior Energy Performance Industrial Facility Best Practice Scorecard...

34

NETL's Hybrid Performance, or Hyper, facility  

ScienceCinema (OSTI)

NETL's Hybrid Performance, or Hyper, facility is a one-of-a-kind laboratory built to develop control strategies for the reliable operation of fuel cell/turbine hybrids and enable the simulation, design, and implementation of commercial equipment. The Hyper facility provides a unique opportunity for researchers to explore issues related to coupling fuel cell and gas turbine technologies.

None

2014-06-26T23:59:59.000Z

35

NETL's Hybrid Performance, or Hyper, facility  

SciTech Connect (OSTI)

NETL's Hybrid Performance, or Hyper, facility is a one-of-a-kind laboratory built to develop control strategies for the reliable operation of fuel cell/turbine hybrids and enable the simulation, design, and implementation of commercial equipment. The Hyper facility provides a unique opportunity for researchers to explore issues related to coupling fuel cell and gas turbine technologies.

None

2013-06-12T23:59:59.000Z

36

Preliminary melter performance assessment report  

SciTech Connect (OSTI)

The Melter Performance Assessment activity, a component of the Pacific Northwest Laboratory`s (PNL) Vitrification Technology Development (PVTD) effort, was designed to determine the impact of noble metals on the operational life of the reference Hanford Waste Vitrification Plant (HWVP) melter. The melter performance assessment consisted of several activities, including a literature review of all work done with noble metals in glass, gradient furnace testing to study the behavior of noble metals during the melting process, research-scale and engineering-scale melter testing to evaluate effects of noble metals on melter operation, and computer modeling that used the experimental data to predict effects of noble metals on the full-scale melter. Feed used in these tests simulated neutralized current acid waste (NCAW) feed. This report summarizes the results of the melter performance assessment and predicts the lifetime of the HWVP melter. It should be noted that this work was conducted before the recent Tri-Party Agreement changes, so the reference melter referred to here is the Defense Waste Processing Facility (DWPF) melter design.

Elliott, M.L.; Eyler, L.L.; Mahoney, L.A.; Cooper, M.F.; Whitney, L.D.; Shafer, P.J.

1994-08-01T23:59:59.000Z

37

3Q CY2005 (PDF), Facility Representative Program Performance...  

Office of Environmental Management (EM)

3Q CY2005 (PDF), Facility Representative Program Performance Indicators Quarterly Report 3Q CY2005 (PDF), Facility Representative Program Performance Indicators Quarterly Report...

38

Survey of computer codes applicable to waste facility performance evaluations  

SciTech Connect (OSTI)

This study is an effort to review existing information that is useful to develop an integrated model for predicting the performance of a radioactive waste facility. A summary description of 162 computer codes is given. The identified computer programs address the performance of waste packages, waste transport and equilibrium geochemistry, hydrological processes in unsaturated and saturated zones, and general waste facility performance assessment. Some programs also deal with thermal analysis, structural analysis, and special purposes. A number of these computer programs are being used by the US Department of Energy, the US Nuclear Regulatory Commission, and their contractors to analyze various aspects of waste package performance. Fifty-five of these codes were identified as being potentially useful on the analysis of low-level radioactive waste facilities located above the water table. The code summaries include authors, identification data, model types, and pertinent references. 14 refs., 5 tabs.

Alsharif, M.; Pung, D.L.; Rivera, A.L.; Dole, L.R.

1988-01-01T23:59:59.000Z

39

Enterprise Assessments Review, Hanford K-West Annex Facility...  

Energy Savers [EERE]

Review, Hanford K-West Annex Facility Construction Quality - January 2015 Enterprise Assessments Review, Hanford K-West Annex Facility Construction Quality - January 2015 January,...

40

REVIEWING PERFORMANCE ASSESSMENTS SUPPORTING  

E-Print Network [OSTI]

Purpose: To summarize current NRC policy and guidance, which should assist in making informed decisions regarding land disposal of unique low-level radioactive waste streams, including disposal of significant quantities of depleted uranium until a new regulation is implemented. Background: In September 2009, NRC staff conducted two public workshops soliciting early public input on major issues associated with a potential rulemaking for land disposal of unique waste streams including, but not limited to, significant quantities of depleted uranium. During these workshops, a number of stakeholders expressed interest or concern with the review of performance assessments supporting land disposal of unique waste streams prior to completion of the rulemaking process. Discussion: The enclosure contains a summary of existing guidance for reviewing performance assessments with a focus on issues associated with the safe disposal of unique waste streams. NRC staff is providing this guidance to the Agreement States for their information, and for distribution to their licensees, as appropriate. If you have any questions regarding this correspondence, please contact me at 301-415-3340 or the individuals named below.

Robert J. Lewis

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

4Q CY2001, Facility Representative Program Performance Indicators  

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

ID, seven Facility Representatives supported a two-week, around-the-clock assessment of conduct of operations at the Radioactive Waste Management Complex. The assessment provided...

42

Building Confidence in LLW Performance Assessments - 13386  

SciTech Connect (OSTI)

The performance assessment process and incorporated input assumptions for four active and one planned DOE disposal sites were analyzed using a systems approach. The sites selected were the Savannah River E-Area Slit and Engineered Trenches, Hanford Integrated Disposal Facility, Idaho Radioactive Waste Management Complex, Oak Ridge Environmental Management Waste Management Facility, and Nevada National Security Site Area 5. Each disposal facility evaluation incorporated three overall system components (1) site characteristics (climate, geology, geochemistry, etc.), (2) waste properties (waste form and package), and (3) engineered barrier designs (cover system, liner system). Site conceptual models were also analyzed to identity the main risk drivers and risk insights controlling performance for each disposal facility. (authors)

Rustick, Joseph H.; Kosson, David S.; Krahn, Steven L.; Clarke, James H. [Vanderbilt University, Department of Civil and Environmental Engineering and Consortium for Risk Evaluation with Stakeholder Participation, Nashville, Tennessee, 37235 (United States)] [Vanderbilt University, Department of Civil and Environmental Engineering and Consortium for Risk Evaluation with Stakeholder Participation, Nashville, Tennessee, 37235 (United States)

2013-07-01T23:59:59.000Z

43

Communicating Performance Assessments Results - 13609  

SciTech Connect (OSTI)

The F-Area Tank Farms (FTF) and H-Area Tank Farm (HTF) are owned by the U.S. Department of Energy (DOE) and operated by Savannah River Remediation LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF and HTF are active radioactive waste storage and treatment facilities consisting of 51 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. Performance Assessments (PAs) for each Tank Farm have been prepared to support the eventual closure of the underground radioactive waste tanks and ancillary equipment. PAs provide the technical bases and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of the Tank Farms. The Tank Farms are subject to a number of regulatory requirements. The State regulates Tank Farm operations through an industrial waste water permit and through a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Closure documentation will include State-approved Tank Farm Closure Plans and tank-specific closure modules utilizing information from the PAs. For this reason, the State of South Carolina and the EPA must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. PAs are performance-based, risk-informed analyses of the fate and transport of FTF and HTF residual wastes following final closure of the Tank Farms. Since the PAs serve as the primary risk assessment tools in evaluating readiness for closure, it is vital that PA conclusions be communicated effectively. In the course of developing the FTF and HTF PAs, several lessons learned have emerged regarding communicating PA results. When communicating PA results it is important to stress that the primary goal of the PA results is to provide risk understanding, recognizing the magnitude of risk and identifying the conceptual model decisions and critical assumptions that most impact the results. Conceptual models that describe reality using simplified, mathematical approaches, and their roles in arriving at the PA results, must also be communicated. When presenting PA results, evaluations will typically be focused on a single baseline (or Base Case) to provide a foundation for discussion. The PA results are supplemented by other studies (alternate configurations, uncertainty analyses, and sensitivity analyses) which provide a breadth of modeling to supplement the Base Case. The suite of information offered by the various modeling cases and studies provides confidence that the overall risk is understood along with the underlying parameters and conditions that contribute to risk. (author)

Layton, Mark [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)] [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

44

Environmental assessment: South microwave communication facilities  

SciTech Connect (OSTI)

Western Area Power Administration (Western) is proposing to construct, operate, and maintain eight microwave repeater stations in southwestern Colorado, southeastern Utah, and northern Arizona, in order to meet the minimum fade criteria established by the Western Systems Coordinating Council (WSCC) for the operation and protection of electric power systems. The proposed microwave facilities would increase the reliability of communication. This environmental assessment (EA) describes the existing environmental conditions and the impacts from construction of the eight microwave communication facilities. The EA was prepared in compliance with the National Environmental Policy Act of 1969, the Council on Environmental Quality Regulations (40 CFR 1500-1508), and the Department of Energy Guidelines (52 FR 47662, December 15, 1987). The proposed project would consist of constructing eight microwave facilities, each of which would include a self-supported lattice tower, an equipment building, a propane tank, distribution lines to provide electric power to the sites, and access roads to the sites. The facilities would be constructed in San Miguel and Montezuma Counties in Colorado, San Juan County, Utah, and Navajo, Apache, Coconino, and Yavapai Counties in Arizona. 20 refs., 2 figs., 2 tabs.

Not Available

1989-06-01T23:59:59.000Z

45

The surplus facility inventory and assessment project  

SciTech Connect (OSTI)

As a result of the ending of the Cold War, the Department of Energy (DOE) is experiencing a downsizing of the DOE nuclear weapons complex similar to the downsizing and base closures being experienced by the armed forces. Declining budgets across all DOE programs have further contributed to the extent and rate at which DOE`s assets are being declared surplus. The Surplus Facility Inventory and Assessment (SFIA) Project will define the magnitude of risk associated with the DOE surplus, contaminated assets. The results of the SFIA Project will be fundamental to all planning, budgeting, and management associated with the surplus, contaminated inventory.

Weiner, L.A.; Szilagyi, A.P. [DOE, Washington, DC (United States); Rae, L.J.

1994-12-31T23:59:59.000Z

46

Screening Level Risk Assessment for the New Waste Calcining Facility  

SciTech Connect (OSTI)

This screening level risk assessment evaluates potential adverse human health and ecological impacts resulting from continued operations of the calciner at the New Waste Calcining Facility (NWCF) at the Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Engineering and Environmental Laboratory (INEEL). The assessment was conducted in accordance with the Environmental Protection Agency (EPA) report, Guidance for Performing Screening Level Risk Analyses at Combustion Facilities Burning Hazardous Waste. This screening guidance is intended to give a conservative estimate of the potential risks to determine whether a more refined assessment is warranted. The NWCF uses a fluidized-bed combustor to solidify (calcine) liquid radioactive mixed waste from the INTEC Tank Farm facility. Calciner off volatilized metal species, trace organic compounds, and low-levels of radionuclides. Conservative stack emission rates were calculated based on maximum waste solution feed samples, conservative assumptions for off gas partitioning of metals and organics, stack gas sampling for mercury, and conservative measurements of contaminant removal (decontamination factors) in the off gas treatment system. Stack emissions were modeled using the ISC3 air dispersion model to predict maximum particulate and vapor air concentrations and ground deposition rates. Results demonstrate that NWCF emissions calculated from best-available process knowledge would result in maximum onsite and offsite health and ecological impacts that are less then EPA-established criteria for operation of a combustion facility.

M. L. Abbott; K. N. Keck; R. E. Schindler; R. L. VanHorn; N. L. Hampton; M. B. Heiser

1999-05-01T23:59:59.000Z

47

PERFORMANCE ASSESSMENT OF PID CONTROLLERS  

E-Print Network [OSTI]

PERFORMANCE ASSESSMENT OF PID CONTROLLERS W. Tan, H. J. Marquez, and T. Chen§ Abstract: Criteria based on disturbance rejection and system robustness are proposed to assess the performance of PID-loop or multi-loop. Key Words: PID Control; Tuning; Performance; Robustness; Structured Singular Value. 1

Marquez, Horacio J.

48

Waste Encapsulation and Storage Facility (WESF) Hazards Assessment  

SciTech Connect (OSTI)

This report documents the hazards assessment for the Waste Encapsulation and Storage Facility (WESF) located on the U.S. Department of Energy (DOE) Hanford Site. This hazards assessment was conducted to provide the emergency planning technical basis for WESF. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification.

COVEY, L.I.

2000-11-28T23:59:59.000Z

49

Vitrification Facility integrated system performance testing report  

SciTech Connect (OSTI)

This report provides a summary of component and system performance testing associated with the Vitrification Facility (VF) following construction turnover. The VF at the West Valley Demonstration Project (WVDP) was designed to convert stored radioactive waste into a stable glass form for eventual disposal in a federal repository. Following an initial Functional and Checkout Testing of Systems (FACTS) Program and subsequent conversion of test stand equipment into the final VF, a testing program was executed to demonstrate successful performance of the components, subsystems, and systems that make up the vitrification process. Systems were started up and brought on line as construction was completed, until integrated system operation could be demonstrated to produce borosilicate glass using nonradioactive waste simulant. Integrated system testing and operation culminated with a successful Operational Readiness Review (ORR) and Department of Energy (DOE) approval to initiate vitrification of high-level waste (HLW) on June 19, 1996. Performance and integrated operational test runs conducted during the test program provided a means for critical examination, observation, and evaluation of the vitrification system. Test data taken for each Test Instruction Procedure (TIP) was used to evaluate component performance against system design and acceptance criteria, while test observations were used to correct, modify, or improve system operation. This process was critical in establishing operating conditions for the entire vitrification process.

Elliott, D.

1997-05-01T23:59:59.000Z

50

DRY TRANSFER FACILITY WORKER DOSE ASSESSMENT  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate radiation doses received by personnel working in the Dry Transfer Facility No.1 (DTF-1) performing operations to receive transportation casks, transfer wastes, prepare waste packages, and ship out loaded waste packages and empty casks. Doses received by workers due to maintenance operations are also included in this revision. The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation from normal operation, excluding the remediation area of the building. The results of this calculation will be used to support the design of the DTF-1 and to provide occupational dose estimates for the License Application. The calculations contained in this document were developed by Environmental and Nuclear Engineering of the Design and Engineering Organization and are intended solely for the use of the Design and Engineering Organization in its work regarding facility operation. Yucca Mountain Project personnel from the Environmental and Nuclear Engineering should be consulted before use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in the Environmental and Nuclear Engineering.

J.S. Tang

2004-09-23T23:59:59.000Z

51

Integrated performance validation facility for KNICS  

SciTech Connect (OSTI)

For the application of new digital control and monitoring systems in nuclear power plants (NPPs), it is required to satisfy the proven technology requirements. They should have at least three years of documented, satisfactory service as modules of subsystems in power plant applications similar to that of NPP, or it should have three years of documented, satisfactory service in other plant applications which are similar to the use in NPP (EPRI-URD's first option). However, tlte digital control and monitoring systems developed by Korea Nuclear Instrumentation A Control System (KNICS) R and D Center, due to the nature of the firstly developed system, have had no prior application in any NPPs as well as industrial and fossil power plants. Therefore, well defined program using 'Integrated Performance Validation Facility (IPVF) 'for prototype testing has been prepared to verify their performance, operability and reliability according to EPRI-URD's second option: It has satisfactorily completed a defined program of prototype testing which has been designed to verify its performance. The IPVF for KNICS is being designed to justify that new control systems are proven to meet utility's requirements. The IPVF comprises Virtual Operating Crew (VOC) and Test Commander (TC). Human System Interface (HIS). Evaluation System, and Simulator and Interface System. PLC and DCS developed by KNICS are connected with IPVF. Control logics and HIS of real NPP are implemented in the KNICS PLC and DCS, which are the validation object. Finally. IPVF will be extremely valuable for other activities in addition to the validation of the new control system equipment, including the testing and evaluation of plant control algorithms, personnel training, and support for long-term maintenance of the control systems. (authors)

Kim, D. G.; Choi, J. J.; Choi, M. J.; Choe, I. N. [I and C Engineering Dept., Korea Power Engineering Company, 360-9, Mabuk-Dong, Yongin-Si. Gyeonggi-Do. 446-713 (Korea, Republic of); Gong, Y. H.; Kim, K. H. [KNICS R and D Center, 28-1, Seongju-Dong, Changwon-Si. 641-120 (Korea, Republic of)

2006-07-01T23:59:59.000Z

52

Radioactive Waste Management Complex performance assessment: Draft  

SciTech Connect (OSTI)

A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

1990-06-01T23:59:59.000Z

53

4Q CY2000 (PDF), Facility Representative Program Performance...  

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

"The Facility Representative Program Performance Indicators Quarterly Report is attached, covering the period from October to December 2000. Data for these indicators are gathered...

54

Performance viewing and editing in ASSESS Outsider  

SciTech Connect (OSTI)

The Analytic System and Software for Evaluation of Safeguards and Security (ASSESS) Facility module records site information in the path elements and areas of an Adversary Sequence Diagram. The ASSESS Outsider evaluation module takes this information and first calculates performance values describing how much detection and delay is assigned at each path element and then uses the performance values to determine most-vulnerable paths. This paper discusses new Outsider capabilities that allow the user to view how elements are being defeated and to modify some of these values in Outsider. Outsider now displays how different path element segments are defeated and contrasts the probability of detection for alternate methods of defeating a door (e.g., the lock or the door face itself). The user can also override element segment delays and detection probabilities directly during analysis in Outsider. These capabilities allow users to compare element performance and to verify correct path element performance for all elements, not just those on the most-vulnerable path as is the case currently. Improvements or reductions in protection can be easily checked without creating a set of new facility files to accomplish it.

Snell, M.K. [Sandia National Labs., Albuquerque, NM (US); Key, B.; Bingham, B. [Science and Engineering Associates, Inc., Albuquerque, NM (US)

1993-07-01T23:59:59.000Z

55

340 Facility emergency preparedness hazards assessment  

SciTech Connect (OSTI)

This document establishes the technical basis in support of Emergency Planning activities for the 340 Facility on the Hanford Site. Through this document, the technical basis for the development of facility specific Emergency Action Levels and Emergency Planning Zone, is demonstrated.

CAMPBELL, L.R.

1998-11-25T23:59:59.000Z

56

Plantwide Energy Assessment of a Sugarcane Farming and Processing Facility  

SciTech Connect (OSTI)

A plantwide energy assessment was performed at Hawaiian Commercial & Sugar Co., an integrated sugarcane farming and processing facility on the island of Maui in the State of Hawaii. There were four main tasks performed for the plantwide energy assessment: 1) pump energy assessment in both field and factory operations, 2) steam generation assessment in the power production operations, 3) steam distribution assessment in the sugar manufacturing operation, and 4) electric power distribution assessment of the company system grid. The energy savings identified in each of these tasks were summarized in terms of fuel savings, electricity savings, or opportunity revenue that potentially exists mostly from increased electric power sales to the local electric utility. The results of this investigation revealed eight energy saving projects that can be implemented at HC&S. These eight projects were determined to have potential for $1.5 million in annual fuel savings or 22,337 MWh equivalent annual electricity savings. Most of the savings were derived from pump efficiency improvements and steam efficiency improvements both in generation and distribution. If all the energy saving projects were implemented and the energy savings were realized as less fuel consumed, there would be corresponding reductions in regulated air pollutants and carbon dioxide emissions from supplemental coal fuel. As HC&S is already a significant user of renewable biomass fuel for its operations, the projected reductions in air pollutants and emissions will not be as great compared to using only coal fuel for example. A classification of implementation priority into operations was performed for the identified energy saving projects based on payback period and ease of implementation.

Jakeway, L.A.; Turn, S.Q.; Keffer, V.I.; Kinoshita, C.M.

2006-02-27T23:59:59.000Z

57

Total System Performance Assessment Peer Review Panel  

Broader source: Energy.gov [DOE]

Total System Performance Assessment (TSPA) Peer Review Panel for predicting the performance of a repository at Yucca Mountain.

58

Computational Tools to Assess Turbine Biological Performance  

SciTech Connect (OSTI)

Public Utility District No. 2 of Grant County (GCPUD) operates the Priest Rapids Dam (PRD), a hydroelectric facility on the Columbia River in Washington State. The dam contains 10 Kaplan-type turbine units that are now more than 50 years old. Plans are underway to refit these aging turbines with new runners. The Columbia River at PRD is a migratory pathway for several species of juvenile and adult salmonids, so passage of fish through the dam is a major consideration when upgrading the turbines. In this paper, a method for turbine biological performance assessment (BioPA) is demonstrated. Using this method, a suite of biological performance indicators is computed based on simulated data from a CFD model of a proposed turbine design. Each performance indicator is a measure of the probability of exposure to a certain dose of an injury mechanism. Using known relationships between the dose of an injury mechanism and frequency of injury (dose–response) from laboratory or field studies, the likelihood of fish injury for a turbine design can be computed from the performance indicator. By comparing the values of the indicators from proposed designs, the engineer can identify the more-promising alternatives. We present an application of the BioPA method for baseline risk assessment calculations for the existing Kaplan turbines at PRD that will be used as the minimum biological performance that a proposed new design must achieve.

Richmond, Marshall C.; Serkowski, John A.; Rakowski, Cynthia L.; Strickler, Brad; Weisbeck, Molly; Dotson, Curtis L.

2014-07-24T23:59:59.000Z

59

Impacts assessment for the National Ignition Facility  

SciTech Connect (OSTI)

This report documents the economic and other impacts that will be created by the National Ignition Facility (NIF) construction and ongoing operation, as well as the impacts that may be created by new technologies that may be developed as a result of NIF development and operation.

Bay Area Economics

1996-12-01T23:59:59.000Z

60

Verification and Validation of Facilities Procedures Assessment...  

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

another appropriate review mechanism. (DOE O 5480.19 C 4) References: DOE Order 5480.19, Conduct of Operations EM-25, Operations Assessment Field Handbook, June 24, 1999 BN...

Note: This page contains sample records for the topic "facility performance assessments" 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

Guidance for performing preliminary assessments under CERCLA  

SciTech Connect (OSTI)

EPA headquarters and a national site assessment workgroup produced this guidance for Regional, State, and contractor staff who manage or perform preliminary assessments (PAs). EPA has focused this guidance on the types of sites and site conditions most commonly encountered. The PA approach described in this guidance is generally applicable to a wide variety of sites. However, because of the variability among sites, the amount of information available, and the level of investigative effort required, it is not possible to provide guidance that is equally applicable to all sites. PA investigators should recognize this and be aware that variation from this guidance may be necessary for some sites, particularly for PAs performed at Federal facilities, PAs conducted under EPA`s Environmental Priorities Initiative (EPI), and PAs at sites that have previously been extensively investigated by EPA or others. The purpose of this guidance is to provide instructions for conducting a PA and reporting results. This guidance discusses the information required to evaluate a site and how to obtain it, how to score a site, and reporting requirements. This document also provides guidelines and instruction on PA evaluation, scoring, and the use of standard PA scoresheets. The overall goal of this guidance is to assist PA investigators in conducting high-quality assessments that result in correct site screening or further action recommendations on a nationally consistent basis.

NONE

1991-09-01T23:59:59.000Z

62

Salt site performance assessment activities  

SciTech Connect (OSTI)

During this year the first selection of the tools (codes) for performance assessments of potential salt sites have been tentatively selected and documented; the emphasis has shifted from code development to applications. During this period prior to detailed characterization of a salt site, the focus is on bounding calculations, sensitivity and with the data available. The development and application of improved methods for sensitivity and uncertainty analysis is a focus for the coming years activities and the subject of a following paper in these proceedings. Although the assessments to date are preliminary and based on admittedly scant data, the results indicate that suitable salt sites can be identified and repository subsystems designed which will meet the established criteria for protecting the health and safety of the public. 36 references, 5 figures, 2 tables.

Kircher, J.F.; Gupta, S.K.

1983-01-01T23:59:59.000Z

63

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

SciTech Connect (OSTI)

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

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

1996-12-31T23:59:59.000Z

64

PERFORMANCE OBJECTIVES FOR TANK FARM CLOSURE PERFORMANCE ASSESSMENTS  

SciTech Connect (OSTI)

This report documents the performance objectives (metrics, times of analyses, and times of compliance) to be used in performance assessments of Hanford Site tank farm closure.

MANN, F.M.; CRUMPLER, J.D.

2005-09-30T23:59:59.000Z

65

Performance Assessment Report Domain CHP System  

E-Print Network [OSTI]

Performance Assessment Report for the Domain CHP System November 2005 By Burns & McDonnell Engineering #12;Domain CHP System Performance Assessment Report for the Packaged Cooling, Heating and Power

Oak Ridge National Laboratory

66

Performance Assessment Community of Practice Technical Exchange  

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

Interagency Performance and Risk Assessment Community of Practice The Interagency Performance and Risk Assessment Community of Practice (P&RA CoP) was formed to provide a forum to...

67

NREL: Resource Assessment and Forecasting - Facilities  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andData and Resources NREL resource assessment and forecasting

68

IMPROVING CONSISTENCY OF PERFORMANCE ASSESSMENTS IN THE DOE COMPLEX  

SciTech Connect (OSTI)

The low-level waste (LLW) performance assessment (PA) process has been traditionally focused on disposal facilities at a few United States Department of Energy (USDOE) sites and commercial disposal facilities. In recent years, there has been a dramatic increase in the scope of the use of PA-like modeling approaches, involving multiple activities, facilities, contractors and regulators. The scope now includes, for example: (1) National Environmental Policy Act (NEPA) assessments, (2) CERCLA disposal cells, (3) Waste Determinations and High-Level Waste (HLW) Closure activities, (4) Potential on-site disposal of Transuranic (TRU) waste, and (5) In-situ decommissioning (including potential use of existing facilities for disposal). The dramatic increase in the variety of activities requiring more detailed modeling has resulted in a similar increase in the potential for inconsistency in approaches both at a site and complexwide scale. This paper includes a summary of USDOE Environmental Management (EM) sponsored initiatives and activities for improved consistency. New initiatives entitled the Performance Assessment Community of Practice and Performance Assessment Assistance Team are also introduced.

Seitz, R; Elmer Wilhite, E

2009-01-20T23:59:59.000Z

69

Assessment of Space Nuclear Thermal Propulsion Facility and Capability Needs  

SciTech Connect (OSTI)

The development of a Nuclear Thermal Propulsion (NTP) system rests heavily upon being able to fabricate and demonstrate the performance of a high temperature nuclear fuel as well as demonstrating an integrated system prior to launch. A number of studies have been performed in the past which identified the facilities needed and the capabilities available to meet the needs and requirements identified at that time. Since that time, many facilities and capabilities within the Department of Energy have been removed or decommissioned. This paper provides a brief overview of the anticipated facility needs and identifies some promising concepts to be considered which could support the development of a nuclear thermal propulsion system. Detailed trade studies will need to be performed to support the decision making process.

James Werner

2014-07-01T23:59:59.000Z

70

Tech-X Corporation has accessed the high performance computing (HPC) facilities at the Science and Technology Facilities Council's (STFC)  

E-Print Network [OSTI]

Tech-X Corporation has accessed the high performance computing (HPC) facilities at the Science high performance computing (HPC) and simulation technology. A research collaboratory in association

Zharkova, Valentina V.

71

International physical protection self-assessment tool for chemical facilities.  

SciTech Connect (OSTI)

This report is the final report for Laboratory Directed Research and Development (LDRD) Project No.130746, International Physical Protection Self-Assessment Tool for Chemical Facilities. The goal of the project was to develop an exportable, low-cost, computer-based risk assessment tool for small to medium size chemical facilities. The tool would assist facilities in improving their physical protection posture, while protecting their proprietary information. In FY2009, the project team proposed a comprehensive evaluation of safety and security regulations in the target geographical area, Southeast Asia. This approach was later modified and the team worked instead on developing a methodology for identifying potential targets at chemical facilities. Milestones proposed for FY2010 included characterizing the international/regional regulatory framework, finalizing the target identification and consequence analysis methodology, and developing, reviewing, and piloting the software tool. The project team accomplished the initial goal of developing potential target categories for chemical facilities; however, the additional milestones proposed for FY2010 were not pursued and the LDRD funding therefore was redirected.

Tewell, Craig R.; Burdick, Brent A.; Stiles, Linda L.; Lindgren, Eric Richard

2010-09-01T23:59:59.000Z

72

Effect of aging on the seismic performance of petrochemical facilities  

SciTech Connect (OSTI)

This paper discusses the effects of aging of petrochemical facilities with regard to the impact on seismic performance. Examples of typical construction and serious concerns are presented. Requirements in evaluation and retrofits are discussed. A comparison is made with the current state-of-practice in offshore platforms and nuclear power plants.

Johnson, G.S. (EQE International, San Francisco, CA (United States))

1993-05-01T23:59:59.000Z

73

E-Area Performance Assessment Interim Measures Assessment FY2005  

SciTech Connect (OSTI)

After major changes to the limits for various disposal units of the E-Area Low Level Waste Facility (ELLWF) last year, no major changes have been made during FY2005. A Special Analysis was completed which removes the air pathway {sup 14}C limit from the Intermediate Level Vault (ILV). This analysis will allow the disposal of reactor moderator deionizers which previously had no pathway to disposal. Several studies have also been completed providing groundwater transport input for future special analyses. During the past year, since Slit Trenches No.1 and No.2 were nearing volumetric capacity, they were operationally closed under a preliminary closure analysis. This analysis was performed using as-disposed conditions and data and showed that concrete rubble from the demolition of 232-F was acceptable for disposal in the STs even though the latest special analysis for the STs had reduced the tritium limits so that the inventory in the rubble exceeded limits. A number of special studies are planned during the next years; perhaps the largest of these will be revision of the Performance Assessment (PA) for the ELLWF. The revision will be accomplished by incorporating special analyses performed since the last PA revision as well as revising analyses to include new data. Projected impacts on disposal limits of more recent studies have been estimated. No interim measures will be applied during this year. However, it is being recommended that tritium disposals to the Components-in-Grout (CIG) Trenches be suspended until a limited Special Analysis (SA) currently in progress is completed. This SA will give recommendations for optimum placement of tritiated D-Area tower waste. Further recommendations for tritiated waste placement in the CIG Trenches will be given in the upcoming PA revision.

Stallings, M

2006-01-31T23:59:59.000Z

74

ASSESSMENT OF ECONOMIC PERFORMANCE OF MODEL PREDICTIVE  

E-Print Network [OSTI]

ASSESSMENT OF ECONOMIC PERFORMANCE OF MODEL PREDICTIVE CONTROL THROUGH VARIANCE/CONSTRAINT TUNING advanced process control (APC) strategies to deal with multivariable constrained control problems with an ultimate objective towards economic optimization. Any attempt to evaluate MPC performance should therefore

Huang, Biao

75

CARD No. 32 Scope of Performance Assessments  

E-Print Network [OSTI]

that the Waste Isolation Pilot Plant (WIPP) will meet EPA's release limits is conducted through the useCARD No. 32 Scope of Performance Assessments 32.A.1 BACKGROUND The radioactive waste disposal of a process known as a "performance assessment" (PA). The WIPP PA essentially consists of a series of computer

76

RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory  

SciTech Connect (OSTI)

US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL`s assessment of the need for further remedial attention.

Not Available

1987-03-01T23:59:59.000Z

77

RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory  

SciTech Connect (OSTI)

US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention.

Not Available

1987-03-01T23:59:59.000Z

78

High Performance Imaging Streak Camera for the National Ignition Facility  

SciTech Connect (OSTI)

An x-ray streak camera platform has been characterized and implemented for use at the National Ignition Facility. The camera has been modified to meet the experiment requirements of the National Ignition Campaign and to perform reliably in conditions that produce high EMI. A train of temporal UV timing markers has been added to the diagnostic in order to calibrate the temporal axis of the instrument and the detector efficiency of the streak camera was improved by using a CsI photocathode. The performance of the streak camera has been characterized and is summarized in this paper. The detector efficiency and cathode measurements are also presented.

Opachich, Y. P. [LLNL; Kalantar, D. [LLNL; MacPhee, A. [LLNL; Holder, J. [LLNL; Kimbrough, J. [LLNL; Bell, P. M. [LLNL; Bradley, D. [LLNL; Hatch, B. [LLNL; Brown, C. [LLNL; Landen, O. [LLNL; Perfect, B. H. [LLNL, HMC; Guidry, B. [LLNL; Mead, A. [NSTec; Charest, M. [NSTec; Palmer, N. [LLNL; Homoelle, D. [LLNL; Browning, D. [LLNL; Silbernagel, C. [NSTec; Brienza-Larsen, G. [NSTec; Griffin, M. [NSTec; Lee, J. J. [NSTec; Haugh, M. J. [NSTec

2012-12-01T23:59:59.000Z

79

FACSIM/MRS-1: Cask receiving and consolidation performance assessment  

SciTech Connect (OSTI)

A simulation analysis was completed to assess the performance of the shipping cask receiving and spent-fuel handling, consolidation and canistering operations of the Monitored Retrievable Storage (MRS) facility. One purpose of this evaluation was to estimate the limits of MRS operational capabilities and factors leading to those limitations. The model used to obtain the performance assessment, FACSIM/MRS-1, is one of two components of the FACSIM model developed by PNL's simulation effort for the nuclear waste-handling facility. FACSIM/MRS-1 provides the user with information about lag-storage requirements, machine use, cask queues, welder queues, and cask process and cask turnaround times. The model can help determine the effect that the following activities have on operating efficiency: (1) receiving multiple cask shipments, when rail-cask or truck-cask shipments arrive at the facility in groups of two or more, and (2) operating the facility five days per week, three shifts per day or seven days per week, three shifts per day for any conditions. In addition, sensitivity to equipment failure frequency and the time needed for equipment repair can be studied. Information on the above operating characteristics may be obtained for any spent-fuel rate, any split of shipments between truck and rail transport, or any split of boiling water reactor/pressurized water reactor fuel.

Lotz, T.L.; Shay, M.R.

1987-06-01T23:59:59.000Z

80

Facility Energy Decision System (FEDS) Assessment Report for US Army Garrison, Japan - Honshu Installations  

SciTech Connect (OSTI)

This report documents an assessment was performed by a team of engineers from Pacific Northwest National Laboratory (PNNL) under contract to the Installation Management Command (IMCOM) Pacific Region Office (PARO). The effort used the Facility Energy Decision System (FEDS) model to determine how energy is consumed at five U.S. Army Garrison-Japan (USAG-J) installations in the Honshu area, identify the most cost-effective energy retrofit measures, and calculate the potential energy and cost savings.

Kora, Angela R.; Brown, Daryl R.; Dixon, Douglas R.

2010-03-09T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Hanford immobilized low-activity tank waste performance assessment  

SciTech Connect (OSTI)

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis to set requirements on the waste form and the facility design that will protect the long-term public health and safety and protect the environment.

Mann, F.M.

1998-03-26T23:59:59.000Z

82

Ross Hazardous and Toxic Materials Handling Facility: Environmental Assessment.  

SciTech Connect (OSTI)

The Bonneville Power Administration (BPA) owns a 200-acre facility in Washington State known as the Ross Complex. Activities at the Ross Complex routinely involve handling toxic substances such as oil-filled electrical equipment containing polychlorinated biphenyls (PCBs), organic and inorganic compounds for preserving wood transmission poles, and paints, solvents, waste oils, and pesticides and herbicides. Hazardous waste management is a common activity on-site, and hazardous and toxic substances are often generated from these and off-site activities. The subject of this environmental assessment (EA) concerns the consolidation of hazardous and toxic substances handling at the Complex. This environmental assessment has been developed to identify the potential environmental impacts of the construction and operation of the proposal. It has been prepared to meet the requirements of the National Environmental Policy Act (NEPA) to determine if the proposed action is likely to have a significant impact on the environment. In addition to the design elements included within the project, mitigation measures have been identified within various sections that are now incorporated within the project. This facility would be designed to improve the current waste handling practices and to assist BPA in meeting Federal and state regulations.

URS Consultants, Inc.

1992-06-01T23:59:59.000Z

83

Performance Assessment of Photovoltaic Attic Ventilator Fans  

E-Print Network [OSTI]

has long been identified as a method to abate such heat gains. We present test results from using the photovoltaic (PV) attic ventilator fans in a test home to assess impact on attic and cooling energy performance....

Parker, D. S.; Sherwin, J. R.

2000-01-01T23:59:59.000Z

84

Nevada National Security Site Performance Assessment Updates...  

Office of Environmental Management (EM)

December 11 and 12, 2014 To view all the P&RA CoP 2014 Technical Exchange Meeting videos click here. Video Presentation Nevada National Security Site Performance Assessment...

85

Seismic margins assessment of the plutonium processing facility Los Alamos National Laboratory  

SciTech Connect (OSTI)

Results of the recently completed seismic evaluation at the Los Alamos National Laboratory site indicate a need to consider seismic loads greater than design basis for many structures systems and components (SSCs). DOE Order 5480.28 requires that existing SSCs be evaluated to determine their ability to withstand the effects of earthquakes when changes in the understanding of this hazard results in greater loads. In preparation for the implementation of DOE Order 5480.28 and to support the update of the facility Safety Analysis Report, a seismic margin assessment of SSCs necessary for a monitored passive safe shutdown of the Plutonium Processing Facility (PF-4) was performed. The seismic margin methodology is given in EPRI NP-6041-SL, ``A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)``. In this methodology, high confidence of low probability of failure (HCLPF) capacities for SSCs are estimated in a deterministic manner. For comparison to the performance goals given in DOE Order 5480.28, the results of the seismic margins assessment were used to estimate the annual probability of failure for the evaluated SSCs. In general, the results show that the capacity for the SSCs comprising PF-4 is high. This is to be expected for a newer facility as PF-4 was designed in the early 1970`s. The methodology and results of this study are presented in this paper.

Goen, L.K. [Los Alamos National Lab., NM (United States); Salmon, M.W. [EQE International, Irwine, CA (United States)

1995-12-01T23:59:59.000Z

86

Performance Assessment for Environmental Decision Making  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Performance Assessment Departments at Sandia National Laboratories have, over the last twenty (20) years, developed unique, internationally-recognized performance and risk assessment methods to assess options for the safe disposal and remediation of radioactive and non-radioactive hazardous waste/contamination in geohydrologic systems. While these methods were originally developed for the disposal of nuclear waste, ongoing improvements and extensions make them equally applicable to a variety of environmental problems such as those associated with the remediation of EPA designated Superfund sites and the more generic Brownfield sites (industrial sites whose future use is restricted because of real or perceived contamination).

Anderson, D.R.; Fewell, M.E.; Gomez, L.S.; Marietta, M.G.; Swift, P.N.; Trauth, K.M.; Vaughn, P. [Sandia National Labs., Albuquerque, NM (United States); MacKinnon, R.J. [Applied Physics, Inc., Albuquerque, NM (United States)

1997-12-01T23:59:59.000Z

87

PERFORMANCE ASSESSMENT ASSISTANCE ACTIVITIES IN THE DOE COMPLEX  

SciTech Connect (OSTI)

The United States Department of Energy Office of Environmental Management (DOE-EM) has established a Performance Assessment Community of Practice (PA CoP) to foster the sharing of information among performance assessment (PA) and risk assessment practitioners, regulators and oversight personnel. The general intent is to contribute to continuous improvement in the consistency, technical adequacy and quality of implementation of PAs and risk assessments around the DOE Complex. The PA CoP activities have involved commercial disposal facilities and international participants to provide a global perspective. The PA CoP has also sponsored annual technical exchanges as a means to foster improved communication and to share lessons learned from on-going modelling activities. The PA CoP encourages activities to provide programmatic and technical assistance in the form of sharing experience and lessons learned with practitioners during the development of PAs and risk assessments. This assistance complements DOE-EM reviews through the Low-Level Waste Disposal Facility Federal Review Group (LFRG) that are conducted after modelling efforts are completed. Such up-front assistance is providing additional value in terms of improving consistency and sharing of information. There has been a substantial increase in the amount of assistance being provided. The assistance has been well received by practitioners and regulators that have been involved. The paper highlights assistance and sharing of information that has been conducted in the last two years to support activities underway in support of proposed disposal facilities at Paducah, Portsmouth, and the Idaho National Laboratory and tank closure at Hanford.

Seitz, R.

2012-01-23T23:59:59.000Z

88

Consideration of liners and covers in performance assessments  

SciTech Connect (OSTI)

On-site disposal cells are in use and being considered at several United States Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These disposal cells are typically regulated by States and/or the U.S. Environmental Protection Agency under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) in addition to having to comply with requirements in DOE Order 435.1, Radioactive Waste Management due to the radioactive waste. The USDOE-Environmental Management Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these CERCLA disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to CERCLA risk assessments and DOE Order 435.1 performance assessments in support of a Record of Decision and Disposal Authorization Statement, respectively. One of the issues considered by the working group, which is addressed in this report, was how to appropriately consider the performance of covers and liners/leachate collections systems in the context of a DOE Order 435.1 performance assessment (PA). This same information may be appropriate for consideration within CERCLA risk assessments for these facilities. These OSDCs are generally developed to meet hazardous waste (HW) disposal design standards under the Resource Conservation and Recovery Act (RCRA) as well as the DOE Order 435.1 performance based standards for disposal of radioactive waste. To meet the standards for HW, the facilities typically include engineered covers and liner/leachate collection systems. Thus, when considering such facilities in the context of a DOE Order 435.1 PA, there is a need to address the evolution of performance of covers and liner/leachate collection systems in the context of meeting a performance standard considering time frames of 1,000 years for compliance and potentially thousands of years based on the wastes to test the robustness of the system. Experience has shown that there are a range of expectations and perspectives from the different regulators involved at different sites when reviewing assumptions related to cover and liner/leachate collection system performance. However for HW disposal alone under RCRA the design standards are typically considered sufficient by the regulators without a requirement to assess long-term performance thus avoiding the need to consider the details addressed in this report. This report provides suggestions for a general approach to address covers and liners/leachate collection systems in a DOE Order 435.1 PA and how to integrate assessments with defense-in-depth considerations such as design, operations, and waste acceptance criteria to address uncertainties. The emphasis is on water balances and management in such assessments. Specific information and references are provided for details needed to address the evolution of individual components of cover and liner/leachate collection systems. This information was then synthesized into suggestions for best practices for cover and liner system design and examples of approaches to address the performance of covers and liners as part of a performance assessment of the disposal system. Numerous references are provided for sources of information to help describe the basis for performance of individual components of cover and liner systems.

Phifer, Mark A. [Savannah River National Laboratory, Aiken, SC (United States); Seitz, Robert R. [Savannah River National Laboratory, Aiken, SC (United States); Suttora, Linda C. [USDOE Enviromental Management, Washington, DC (United States)

2014-09-18T23:59:59.000Z

89

Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management  

SciTech Connect (OSTI)

The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility, waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management.

Bissani, M; Fischer, R; Kidd, S; Merrigan, J

2006-04-03T23:59:59.000Z

90

Cooling Performance Assessment of Building America Homes  

E-Print Network [OSTI]

nine homes in three climate regions. Data from potential zero energy homes and minimum code homes provide upper and lower performance bounds. Comparisons are based on regression analysis of daily cooling energy per 1,000 square foot of floor area... and construction and with cooling equipment of varying efficiency. Plotting such data on a common graph required generalizations that limit the ability to make direct house to house comparisons, but instead provides a broad assessment of cooling performance...

Chasar, D.; Chandra, S.; Parker, D.; Sherwin, J.; Beal, D.; Hoak, D.; Moyer, N.; McIlvaine, J.

2006-01-01T23:59:59.000Z

91

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio). Volume 6. Screening ecological risk assessment (SERA). Draft report  

SciTech Connect (OSTI)

This report constitutes a comprehensive site-specific risk assessment for the WTI incineration facility located in East Liverpool, OH. The Screening Ecological Risk Assessment (SERA) is an analysis of the potential significance of risks to ecological receptors (e.g., plants, fish, wildlife) from exposure to facility emissions. The SERA was performed using conservative assumptions and approaches to determine if a further, more refined analysis is warranted. Volume VI describes in detail the methods used in the SERA and reports the results of the SERA in terms of site-specific risks to ecological receptors.

NONE

1995-11-01T23:59:59.000Z

92

Seismic Risk Assessment of Port Facilities Ung Jin Na, Samit Ray Chaudhuri  

E-Print Network [OSTI]

Seismic Risk Assessment of Port Facilities Ung Jin Na, Samit Ray Chaudhuri Faculty Advisor : Prof Estimation Methodology Applications (in progress) Port of Long Beach · Seismic Risk Assessment, Decision & Vertical movement, Settlement of Apron Seismic Vulnerability - quay Wall

Shinozuka, Masanobu

93

List of Topics for Interagency Performance & Risk Assessment...  

Office of Environmental Management (EM)

List of Topics for Interagency Performance & Risk Assessment Community of Practice (P&RA CoP) Discussion List of Topics for Interagency Performance & Risk Assessment Community of...

94

COMPARATIVE ASSESSMENT OF MATERIAL PERFORMANCE IN DEMO  

E-Print Network [OSTI]

for sufficient time. Reliable estimates of component lifetimes are an important part of power plant design The basic DEMO design used in the present study is a 1.8 GW device (2.2 GW total thermal power ­ including simulation models and capabilities to assess material performance under the neutron irradiation conditions

95

WINTER PERFORMANCE ASSESSMENT OF PERMEABLE PAVEMENTS  

E-Print Network [OSTI]

WINTER PERFORMANCE ASSESSMENT OF PERMEABLE PAVEMENTS A COMPARATIVE STUDY OF POROUS ASPHALT, PERVIOUS CONCRETE, AND CONVENTIONAL ASPHALT IN A NORTHERN CLIMATE BY KRISTOPHER M. HOULE BS, Worcester the University of New Hampshire, the Northern New England Concrete Promotion Association (NNECPA), the Northeast

96

Benefits of Multi-day Industrial Center Assessments for Large Energy-Intensive Facilities  

E-Print Network [OSTI]

1 Benefits of Multi-day Industrial Center Assessments for Large Energy- Intensive Facilities1 Warren M. Heffington, Texas A&M University James A. Eggebrecht, Texas A&M University ABSTRACT Multi-day Industrial Assessment Center (IAC...) assessments are shown to be effective in serving the energy efficiency needs of large energy-intensive industrial facilities. Assessment results from two and three-day visits to eight large Industries of the Future (IOF) plants are discussed and compared...

Heffington, W.M.; Eggebrecht, J.A.

97

Radiological Assessment for the Vance Road Facility Source Vault, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

From the 1950s, the Vance Road laboratories had been used for a broad range of nuclear medicine research involving numerous radionuclides. These radionuclides were stored in the a source vault located on the first floor of the facility. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault after it had been remediated and in preparation for converting the area to office space.

J. R. Morton

2000-09-01T23:59:59.000Z

98

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2003  

SciTech Connect (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP - U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection - Air Emissions. In these assessments, potential unabated offsite doses were evaluated for emission locations at facilities owned by the U.S. Department of Energy and operated by Pacific Northwest National Laboratory (PNNL) on the Hanford Site. This report describes the inventory-based methods and provides the results for the assessment performed in 2003.

Ballinger, Marcel Y.; Sula, Monte J.; Gervais, Todd L.; Edwards, Daniel L.

2003-12-05T23:59:59.000Z

99

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2001  

SciTech Connect (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP - U.S. Code of Federal Regulations, Title 40 Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection - Air Emissions. In these assessments, potential unabated offsite doses were evaluated for emission locations at facilities owned by the U.S. Department of Energy and operated by Pacific Northwest National Laboratory (PNNL) on the Hanford Site. This report describes the inventory-based methods, and provides the results, for the assessment performed in 2001.

Ballinger, Marcel Y.; Sula, Monte J.; Gervais, Todd L.; Shields, Keith D.; Edwards, Daniel R.

2001-09-28T23:59:59.000Z

100

Mission and Readiness Assessment for Fusion Nuclear Facilities  

SciTech Connect (OSTI)

Magnetic fusion development toward DEMO will most likely require a number of fusion nuclear facilities (FNF), intermediate between ITER and DEMO, to test and validate plasma and nuclear technologies and to advance the level of system integration. The FNF mission space is wide, ranging from basic materials research to net electricity demonstration, so there is correspondingly a choice among machine options, scope, and risk in planning such a step. Readiness requirements to proceed with a DEMO are examined, and two FNF options are assessed in terms of the contributions they would make to closing DEMO readiness gaps, and their readiness to themselves proceed with engineering design about ten years from now. An advanced tokamak (AT) pilot plant with superconducting coils and a mission to demonstrate net electricity generation would go a long way toward DEMO. As a next step, however, a pilot plant would entail greater risk than a copper-coil FNSF-AT with its more focussed mission and technology requirements. The stellarator path to DEMO is briefly discussed. Regardless of the choice of FNF option, an accompanying science and technology development program, also aimed at DEMO readiness, is absolutely essential.

G.H. Neilson, et. al.

2012-12-12T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

4Q CY2004, Facility Representative Program Performance Indicators  

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

atmosphere to the environment. These changes combined with improvements in Conduct of Operations with in the facility create a better, safer, and cleaner environment for the...

102

2Q CY2003, Facility Representative Program Performance Indicators  

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

will produce isotopes for the Brookhaven National Laboratory Positron Emission Tomography Facility. Attachment AreaOps Office Staffing Analysis FTE Level Actual Staffing %...

103

Assessing the Costs and Benefits of the Superior Energy Performance Program  

SciTech Connect (OSTI)

Industrial companies are seeking to manage energy consumption and costs, mitigate risks associated with energy, and introduce transparency into reports of their energy performance achievements. Forty industrial facilities are participating in the U.S. DOE supported Superior Energy Performance (SEP) program in which facilities implement an energy management system based on the ISO 50001 standard, and pursue third-party verification of their energy performance improvements. SEP certification provides industrial facilities recognition for implementing a consistent, rigorous, internationally recognized business process for continually improving energy performance and achievement of established energy performance improvement targets. This paper focuses on the business value of SEP and ISO 50001, providing an assessment of the costs and benefits associated with SEP implementation at nine SEP-certified facilities across a variety of industrial sectors. These cost-benefit analyses are part of the U.S. DOE?s contribution to the Global Superior Energy Performance (GSEP) partnership, a multi-country effort to demonstrate, using facility data, that energy management system implementation enables companies to improve their energy performance with a greater return on investment than business-as-usual (BAU) activity. To examine the business value of SEP certification, interviews were conducted with SEP-certified facilities. The costs of implementing the SEP program, including internal facility staff time, are described and a marginal payback of SEP certification has been determined. Additionally, more qualitative factors with regard to the business value and challenges related to SEP and ISO 50001 implementation are summarized.

Therkelsen, Peter; McKane, Aimee; Sabouini, Ridah; Evans, Tracy

2013-07-01T23:59:59.000Z

104

Performance Evaluation Of An Irradiation Facility Using An Electron Accelerator  

SciTech Connect (OSTI)

Irradiation parameters over a period of seven years have been evaluated for a radiation processing electron accelerator facility. The parameters monitored during this time were the electron beam energy, linearity of beam current, linearity of dose with the reciprocal value of the samples speed, and dose uniformity along the scanning area after a maintenance audit performed by the electron accelerator manufacturer. The electron energy was determined from the depth-dose curve by using a two piece aluminum wedge and measuring the practical range from the obtained curves. The linearity of dose with beam current, and reciprocal value of the speed and dose uniformity along the scanning area of the electron beam were determined by measuring the dose under different beam current and cart conveyor speed conditions using film dosimetry. The results of the experiments have shown that the energy in the range from 1 to 5 MeV has not changed by more than 15% from the High Voltage setting of the machine over the evaluation period, and dose linearity with beam current and cart conveyor speed has not changed. The dose uniformity along the scanning direction of the beam showed a dose uniformity of 90% or better for energies between 2 and 5 MeV, however for 1 MeV electrons this value was reduced to 80%. This parameter can be improved by changing the beam optics settings in the control console of the accelerator though.

Uribe, R. M.; Hullihen, K. [Kent State University, Kent, Ohio (United States); Filppi, E. [Case Western Reserve University, Cleveland OH (United States)

2011-06-01T23:59:59.000Z

105

WIPP Remote Handled Waste Facility: Performance Dry Run Operations  

SciTech Connect (OSTI)

The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

2003-02-24T23:59:59.000Z

106

1Q CY2005 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from January to March 2005. Data for these indicators are gathered by Field elements...

107

2Q CY2008 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators QuarterlyReport covering the period from April to June 2008. Data for these indicators aregathered by Field elements...

108

2Q CY2003 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative Program Performance Indicators (PIs) Quarterly Report Covering the Period from April to June  2003. Data for these indicators are gathered by Field elements...

109

3Q CY2011 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

This memorandum summarizes the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the Period July  through September 2011. Data for these indicators were gathered...

110

1Q CY2006 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from January  to March 2006. Data for these indicators are gathered by Field...

111

3Q CY2003 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative Program Performance Indicators (PIs) Quarterly Report Covering the Period from July to September  2003. Data for these indicators are gathered by Field...

112

3Q CY2010 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

This memorandum summarizes the highlights of the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period of July through September 2010. Data for these...

113

4Q CY2007 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"Attached is the Facility Representative (FR) Program Performance Indicators QuarterlyReport covering the period from October to December 2007. Data for these indicators aregathered by Field...

114

2Q CY2004 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report Covering the Period from April to June  2004. Data for these indicators are gathered by Field elements...

115

4Q CY2002 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative Program Performance Indicators (Pis) Quarterly Report Covering the Period from October to December 2002. Data for these indicators are gathered by Field...

116

1Q CY2012 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

This memorandum summarizes the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from January through March 2012. Data for these indicators were...

117

3Q CY2001 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representive Program Performance Indicators (PIs) Quarterly Report is attached covering the period from July to September 2001. Data for these indicators are gathered by the Field...

118

2Q CY2011 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"This memorandum summarizes the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period April through June 20 1 1. Data for these indicators were gathered...

119

3Q CY2004 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report Covering the Period from July to September  2004. Data for these indicators are gathered by Field...

120

1Q CY2010 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"Attached is the Facility Representative (FR) Program Performance Indicators Quarterly  Report covering the period from January to March2010. Data for these indicators are gathered by Field...

Note: This page contains sample records for the topic "facility performance assessments" 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

3Q CY2009 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly  Report covering the period from July to September 2009. Data for these indicators are gathered by Field...

122

4Q CY2006 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from October to December 2006. Data for these indicators are gathered by Field...

123

4Q CY2009 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"Attached is the Facility Representative (FR) Program Performance Indicators Quarterly  Report covering the period from October to December 2009. Data for these indicators are gathered by Field...

124

3Q CY2002 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representive Program Performance Indicators (PIs) Quarterly Report is attached covering the period from July  to September  2002. Data for these indicators are gathered by the Field...

125

2Q CY2007 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from April to June 2007. Data for these indicators are gathered by field elements...

126

3Q CY2006 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from July to September 2006. Data for these indicators are gathered by Field...

127

1Q CY2001 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representive Program Performance Indicators (PIs) Quarterly Report is attached covering the period from January to March 2001. Data for these indicators are gathered by the Field...

128

4Q CY2011 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"This memorandum summarizes the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from October through December 2011. Data for these indicators were...

129

1Q CY2002 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representive Program Performance Indicators (PIs) Quarterly Report is attached covering the period from January  to March  2002. Data for these indicators are gathered by the Field...

130

4Q CY2005 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from October to December 2005. Data for these indicators are gathered by Field...

131

4Q CY2010 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"This memorandum summarizes the highlights of the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period October through December 2010. Data for these...

132

4Q CY2004 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report Covering the Period from October to December  2004. Data for these indicators are gathered by Field...

133

3Q C&2008 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"Attached is the Facility Representative (FR) Program Performance Indicators Quarterly  Report covering the period from July to September   2008. Data for these indicators aregathered by Field...

134

1Q CY2009 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"Attached is the Facility Representative (FR) Program Performance Indicators Quarterly  Report covering the period from January to March 2009. Data for these indicators are gathered by Field...

135

2Q CY2005 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from April to June 2005. Data for these indicators are gathered by Field elements...

136

4Q CY2003 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative Program Performance Indicators (PIs) Quarterly Report Covering the Period from October to December  2003. Data for these indicators are gathered by Field...

137

1Q CY2007 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from January to March 2007. Data for these indicators are gathered by Field elements...

138

1Q CY2011 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

This memorandum summarizes the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the Period January through March 2011. Data for these indicators were gathered...

139

4Q CY2001 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representive Program Performance Indicators (PIs) Quarterly Report is attached covering the period from October to December  2001. Data for these indicators are gathered by the Field...

140

4Q CY2008 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"Attached is the Facility Representative (FR) Program Performance Indicators Quarterly  Report covering the period from October to December   2008. Data for these indicators are  gathered by Field...

Note: This page contains sample records for the topic "facility performance assessments" 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

2Q CY2009 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"Attached is the Facility Representative (FR) Program Performance Indicators Quarterly  Report covering the period from April to June  2009. Data for these indicators are gathered by Field elements...

142

2Q CY2006 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from April to June 2006. Data for these indicators are gathered by Field elements...

143

2Q CY2010 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

This memorandum summarizes the highlight of, and announces the availablity on-line of, the Facility Representative (FR) Program Performance Indicators are gathered by Field elements quarterly per...

144

2Q CY2002 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representive Program Performance Indicators (PIs) Quarterly Report is attached covering the period from April  to June 2002. Data for these indicators are gathered by the Field...

145

2Q CY2012 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"This memorandum summarizes the Facility Representative (FR) Program Performance Indicators Quarterly Report covering the period from April through June 2012. Data for these indicators were...

146

1Q CY2003 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

Attached is the Facility Representative Program Performance Indicators (PIs) Quarterly Report Covering the Period from January to March  2003. Data for these indicators are gathered by Field...

147

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

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

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

148

RCRA Facility Investigation/Remedial Investigation Report with Baseline Risk Assessment for the Fire Department Hose Training Facility (904-113G)  

SciTech Connect (OSTI)

This report documents the Resource Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation/Baseline Risk Assessment (RFI/RI/BRA) for the Fire Department Hose Training Facility (FDTF) (904-113G).

Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-04-01T23:59:59.000Z

149

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incineration facility (East Liverpool, Ohio). Volume 1. Executive summary  

SciTech Connect (OSTI)

Contents: Introduction and Summary of Results; Facility Background; Facility Emissions; Atmospheric Dispersion and Deposition Modeling of Emissions; Human Health Risk Assessment; Screening Ecological Risk Assessment; Accident Analysis; Additional Analysis in Response to Peer Review Recommendations; References.

NONE

1997-05-01T23:59:59.000Z

150

Performance objectives for the Hanford immobilized low-activity waste (ILAW) performance assessment  

SciTech Connect (OSTI)

Before low-level waste may be disposed of, a performance assessment must be written and then approved by the DOE (DOE 1988a DOE 1999a). The performance assessment is to determine whether ''reasonable assurance'' exists that the performance objectives of the disposal facility will be met. The DOE requirements for waste disposal (DOE 1988a DOE 1999a) require the protection of public health and safety; and the protection of the environment. Although quantitative limits are sometimes stated (for example, the all-pathways exposure limit is 25 mrem/year), usually the requirements are stated in a general nature. Quantitative limits were established by: investigating all potentially applicable regulations as well as interpretations of the review panels which DOE has established to review performance assessments, interacting with program management to establish the additional requirements of the program, and interacting with the public (i.e., the Hanford Advisory Board members; as well as affected Tribal Governments) to understand the values of residents in the Pacific Northwest. Because of space considerations, not all radionuclides and dangerous chemicals are listed in this document. The radionuclides listed here are those which were explicitly treated in the ILAW PA (Mann 1998). The dangerous chemicals listed here are those most often detected in Hanford tank waste as documented in the Regulatory Data Quality Objectives Supporting Tank Waste Remediation System Privatization Project (Wiemers 1998).

MANN, F.M.

1999-09-09T23:59:59.000Z

151

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incineration facility (East Liverpool, Ohio). Volume 2. Introduction  

SciTech Connect (OSTI)

Contents: Overview; Facility Background; Risk Assessment History at WTI; Peer Review Comments and Key Assumptions; and References.

NONE

1997-05-01T23:59:59.000Z

152

Facile synthesis of Li2Spolypyrrole composite structures for high-performance Li2S cathodes  

E-Print Network [OSTI]

Facile synthesis of Li2S­polypyrrole composite structures for high-performance Li2S cathodes Zhi demon- strate facile, in situ synthesis of Li2S­polypyrrole composites for use as high-performance Li2S polysulfides during cycling. Poly- pyrrole, being a conducting polymer, also helps to facilitate elec- tronic

Cui, Yi

153

Diagnosing implosion performance at the National Ignition Facility (NIF) by means of neutron spectrometry  

E-Print Network [OSTI]

, Cambridge, MA 02139, USA 2 Lawrence Livermore National Laboratory, Livermore, CA 94550, USA 3 LaboratoryDiagnosing implosion performance at the National Ignition Facility (NIF) by means of neutron.1088/0029-5515/53/4/043014 Diagnosing implosion performance at the National Ignition Facility (NIF) by means of neutron spectrometry J

154

A Facile Approach Using MgCl2 to Formulate High Performance Mg2...  

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

Using MgCl2 to Formulate High Performance Mg2+ Electrolytes for Rechargeable Mg Batteries. A Facile Approach Using MgCl2 to Formulate High Performance Mg2+ Electrolytes for...

155

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio)  

SciTech Connect (OSTI)

The report constitutes a comprehensive site-specific risk assessment for the WTI incineration facility located in East Liverpool, OH. Volume I is a description of the components and methodologies used in the risk assessment and provides a summary of the major results from the three components of the assessment.

NONE

1995-11-01T23:59:59.000Z

156

Research Support Facility (RSF): Leadership in Building Performance (Brochure)  

SciTech Connect (OSTI)

This brochure/poster provides information on the features of the Research Support Facility including a detailed illustration of the facility with call outs of energy efficiency and renewable energy technologies. Imagine an office building so energy efficient that its occupants consume only the amount of energy generated by renewable power on the building site. The building, the Research Support Facility (RSF) occupied by the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) employees, uses 50% less energy than if it were built to current commercial code and achieves the U.S. Green Building Council's Leadership in Energy and Environmental Design (LEED{reg_sign}) Platinum rating. With 19% of the primary energy in the U.S. consumed by commercial buildings, the RSF is changing the way commercial office buildings are designed and built.

Not Available

2011-09-01T23:59:59.000Z

157

An assessment of the video analytics technology gap for transportation facilities  

E-Print Network [OSTI]

We conduct an assessment of existing video analytic technology as applied to critical infrastructure protection, particularly in the transportation sector. Based on discussions with security personnel at multiple facilities, ...

Thornton, Jason R.

158

Performance assessment task team progress report  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Headquarters EM-35, established a Performance Assessment Task Team (referred to as the Team) to integrate the activities of the sites that are preparing performance assessments (PAs) for disposal of new low-level waste, as required by Chapter III of DOE Order 5820.2A, {open_quotes}Low-Level Waste Management{close_quotes}. The intent of the Team is to achieve a degree of consistency among these PAs as the analyses proceed at the disposal sites. The Team`s purpose is to recommend policy and guidance to the DOE on issues that impact the PAs, including release scenarios and parameters, so that the approaches are as consistent as possible across the DOE complex. The Team has identified issues requiring attention and developed discussion papers for those issues. Some issues have been completed, and the recommendations are provided in this document. Other issues are still being discussed, and the status summaries are provided in this document. A major initiative was to establish a subteam to develop a set of test scenarios and parameters for benchmarking codes in use at the various sites. The activities of the Team are reported here through December 1993.

Wood, D.E.; Curl, R.U.; Armstrong, D.R.; Cook, J.R.; Dolenc, M.R.; Kocher, D.C.; Owens, K.W.; Regnier, E.P.; Roles, G.W.; Seitz, R.R. [and others

1994-05-01T23:59:59.000Z

159

Using vulnerability assessments to design facility safeguards and security systems  

SciTech Connect (OSTI)

The Weapons Complex Reconfiguration (WCR) Program is meant to prepare the Department of Energy (DOE) weapons complex to meet the needs of the next century through construction of now facilities or upgrades-in-place at existing facilities. This paper describes how a vulnerability (VA) was used to identify potential S&S features for the conceptual design for a plutonium storage facility as part of the WCR Program. We distinguish those features of the design that need to be investigated at the conceptual stage from those that can be evaluated later. We also examined what protection features may allow reduced S&S operating costs, with the main focus on protective force costs. While some of these concepts hold the promise for significantly reducing life-cycle protective force costs, their use depends on resolving long-standing tradeoffs between S&S and safety, which are discussed in the study.

Snell, M.; Jaeger, C.

1994-08-01T23:59:59.000Z

160

Interagency Performance and Risk Assessment Community of Practice...  

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

Interagency Performance and Risk Assessment Community of Practice (P&RA CoP) Charter Interagency Performance and Risk Assessment Community of Practice (P&RA CoP) Charter Charter...

Note: This page contains sample records for the topic "facility performance assessments" 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

TRANSPORTATION CASK RECEIPT AND RETURN FACILITY WORKER DOSE ASSESSMENT  

SciTech Connect (OSTI)

The purpose of this design calculation is to estimate radiation doses received by personnel working in the Transportation Cask Receipt and Return Facility (TCRRF) of the repository including the personnel at the security gate and cask staging areas. This calculation is required to support the preclosure safety analysis (PCSA) to ensure that the predicted doses are within the regulatory limits prescribed by the U.S. Nuclear Regulatory Commission (NRC). The Cask Receipt and Return Facility receives NRC licensed transportation casks loaded with spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The TCRRF operation starts with the receipt, inspection, and survey of the casks at the security gate and the staging areas, and proceeds to the process facilities. The transportation casks arrive at the site via rail cars or trucks under the guidance of the national transportation system. This calculation was developed by the Environmental and Nuclear Engineering organization and is intended solely for the use of Design and Engineering in work regarding facility design. Environmental and Nuclear Engineering personnel should be consulted before using this calculation for purposes other than those stated herein or for use by individuals other than authorized personnel in the Environmental and Nuclear Engineering organization.

V. Arakali

2005-02-24T23:59:59.000Z

162

Performing Probabilistic Risk Assessment Through RAVEN  

SciTech Connect (OSTI)

The Reactor Analysis and Virtual control ENviroment (RAVEN) code is a software tool that acts as the control logic driver and post-processing engine for the newly developed Thermal-Hydraulic code RELAP-7. RAVEN is now a multi-purpose Probabilistic Risk Assessment (PRA) software framework that allows dispatching different functionalities: Derive and actuate the control logic required to simulate the plant control system and operator actions (guided procedures), allowing on-line monitoring/controlling in the Phase Space Perform both Monte-Carlo sampling of random distributed events and Dynamic Event Tree based analysis Facilitate the input/output handling through a Graphical User Interface (GUI) and a post-processing data mining module

A. Alfonsi; C. Rabiti; D. Mandelli; J. Cogliati; R. Kinoshita

2013-06-01T23:59:59.000Z

163

ORNL instrumentation performance for Slab Core Test Facility (SCTF)-Core I Reflood Test Facility  

SciTech Connect (OSTI)

Instrumentation was developed for making measurements in experimental refill-reflood test facilities. These unique instrumentation systems were designed to survive the severe environmental conditions that exist during a simulated pressurized water reactor loss-of-coolant accident (LOCA). Measurement of in-vessel fluid phenomena such as two-phase flow velocity and void fraction and film thickness and film velocity are required for better understanding of reactor behavior during LOCAs. The Advanced Instrumentation for Reflood Studies (AIRS) Program fabricated and delivered instrumentation systems and data reduction software algorithms that allowed the above measurements to be made. Data produced by AIRS sensors during three experimental runs in the Japanese Slab Core Test Facility are presented. Although many of the sensors failed before any useful data could be obtained, the remaining probes gave encouraging and useful results. These results are the first of their kind produced during simulated refill-reflood stage of a LOCA near actual thermohydrodynamic conditions.

Hardy, J E; Hess, R A; Hylton, J O

1983-11-01T23:59:59.000Z

164

CRAD, Verification and Validation of Facilities Procedures Assessment...  

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

Plan More Documents & Publications OPS 9.16 Procedure Content and Use 82498 CRAD, Conduct of Operations Assessment Plan CRAD, Conduct of Operations - Oak Ridge National...

165

A framework for simulation-based real-time whole building performance assessment  

E-Print Network [OSTI]

Performance Assessment Xiufeng Pang, Michael Wetter, PrajeshPerformance Assessment Xiufeng Pang, Michael Wetter, Prajesh

Pang, Xiufeng

2013-01-01T23:59:59.000Z

166

PERFORMANCE STATUS OF THE RF-GUN BASED INJECTOR OF THE TESLA TEST FACILITY LINAC  

E-Print Network [OSTI]

PERFORMANCE STATUS OF THE RF-GUN BASED INJECTOR OF THE TESLA TEST FACILITY LINAC S. SchreiberÂŁ for the TESLA Collaboration, DESY, 22603 Hamburg, Germany Abstract The TESLA Test Facility Linac (TTFL) at DESY uses two modules with 8 TESLA superconducting accelerat- ing structures each to accelerate an electron

167

Gas Test Loop Facilities Alternatives Assessment Report Rev 1  

SciTech Connect (OSTI)

An important task in the Gas Test Loop (GTL) conceptual design was to determine the best facility to serve as host for this apparatus, which will allow fast-flux neutron testing in an existing nuclear facility. A survey was undertaken of domestic and foreign nuclear reactors and accelerator facilities to arrive at that determination. Two major research reactors in the U.S. were considered in detail, the Advanced Test Reactor (ATR) and the High Flux Isotope Reactor (HFIR), each with sufficient power to attain the required neutron fluxes. HFIR routinely operates near its design power limit of 100 MW. ATR has traditionally operated at less than half its design power limit of 250 MW. Both of these reactors should be available for at least the next 30 years. The other major U.S. research reactor, the Missouri University Research Reactor, does not have sufficient power to reach the required neutron flux nor do the smaller research reactors. Of the foreign reactors investigated, BOR-60 is perhaps the most attractive. Monju and BN 600 are power reactors for their respective electrical grids. Although the Joyo reactor is vigorously campaigning for customers, local laws regarding transport of radioactive material mean it would be very difficult to retrieve test articles from either Japanese reactor for post irradiation examination. PHENIX is scheduled to close in 2008 and is fully booked until then. FBTR is limited to domestic (Indian) users only. Data quality is often suspect in Russia. The only accelerator seriously considered was the Fuel and Material Test Station (FMTS) currently proposed for operation at Los Alamos National Laboratory. The neutron spectrum in FMTS is similar to that found in a fast reactor, but it has a pronounced high-energy tail that is atypical of fast fission reactor spectra. First irradiation in the FMTS is being contemplated for 2008. Detailed review of these facilities resulted in the recommendation that the ATR would be the best host for the GTL.

William J. Skerjanc; William F. Skerjanc

2005-07-01T23:59:59.000Z

168

Life cycle assessment of the environmental emissions of waste-to-energy facilities  

SciTech Connect (OSTI)

Over the past ten years, environmental issues have become an increasing priority for both government and industry alike. In the U.S. as well as in Europe, the emphasis has gradually shifted from a site specific focus to a product specific focus. For this reason, tools are needed to scientifically assess the overall environmental performance of products and/or industrial systems. Life Cycle Assessment (LCA) belongs to that category of tools, and is used to perform this study. In numerous industrial countries, LCA is now recognized, and is rapidly becoming the tool of preference, to successfully provide quantitative and scientific analyses of the environmental impacts of industrial systems. By providing an unbiased analysis of entire systems, LCA has shown that the reality behind widely held beliefs regarding {open_quotes}green{close_quotes} issues, such as reusable vs. one way products, and {open_quotes}natural{close_quotes} vs. synthetic products, were far more complex than expected, and sometimes not as {open_quotes}green{close_quotes} as assumed. This paper describes the modeling and assumptions of an LCA, commissioned by the Integrated Waste Services Association (IWSA), that summarizes the environmental emissions of waste-to-energy facilities, and compares them to the environmental emissions generated by major combustible energy sources of the northeast part of the United States (NE). The geographical boundary for this study is, therefore, the NE US.

Besnainou, J.; Landfield, A. [Ecobalance, Inc., Rockville, MD (United States)

1997-12-01T23:59:59.000Z

169

A retrospective tiered environmental assessment of the Mount Storm Wind Energy Facility, West Virginia,USA  

SciTech Connect (OSTI)

Bird and bat fatalities from wind energy projects are an environmental and public concern, with post-construction fatalities sometimes differing from predictions. Siting facilities in this context can be a challenge. In March 2012 the U.S. Fish and Wildlife Service (USFWS) released Land-based Wind Energy Guidelines to assess collision fatalities and other potential impacts to species of concern and their habitats to aid in siting and management. The Guidelines recommend a tiered approach for assessing risk to wildlife, including a preliminary site evaluation that may evaluate alternative sites, a site characterization, field studies to document wildlife and habitat and to predict project impacts, post construction studies to estimate impacts, and other post construction studies. We applied the tiered assessment framework to a case study site, the Mount Storm Wind Energy Facility in Grant County, West Virginia, USA, to demonstrate the use of the USFWS assessment approach, to indicate how the use of a tiered assessment framework might have altered outputs of wildlife assessments previously undertaken for the case study site, and to assess benefits of a tiered ecological assessment framework for siting wind energy facilities. The conclusions of this tiered assessment for birds are similar to those of previous environmental assessments for Mount Storm. This assessment found risk to individual migratory tree-roosting bats that was not emphasized in previous preconstruction assessments. Differences compared to previous environmental assessments are more related to knowledge accrued in the past 10 years rather than to the tiered structure of the Guidelines. Benefits of the tiered assessment framework include good communication among stakeholders, clear decision points, a standard assessment trajectory, narrowing the list of species of concern, improving study protocols, promoting consideration of population-level effects, promoting adaptive management through post-construction assessment and mitigation, and sharing information that can be used in other assessments.

Efroymson, Rebecca Ann [ORNL; Day, Robin [No Affiliation; Strickland, M. Dale [Western EcoSystems Technology

2012-11-01T23:59:59.000Z

170

2009 Performance Assessment for the Saltstone Disposal Facility |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power Systems Engineering ResearchServices4/08VirginiaOsuna- FLIGHT - -July05 Ways

171

Performance assessment for continuing and future operations at solid waste storage area 6  

SciTech Connect (OSTI)

This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility.

NONE

1997-09-01T23:59:59.000Z

172

Assessment of Geochemical Environment for the Proposed INL Remote-Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

Conservative sorption parameters have been estimated for the proposed Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility. This analysis considers the influence of soils, concrete, and steel components on water chemistry and the influence of water chemistry on the relative partitioning of radionuclides over the life of the facility. A set of estimated conservative distribution coefficients for the primary media encountered by transported radionuclides has been recommended. These media include the vault system, concrete-sand-gravel mix, alluvium, and sedimentary interbeds. This analysis was prepared to support the performance assessment required by U.S. Department of Energy Order 435.1, 'Radioactive Waste Management.' The estimated distribution coefficients are provided to support release and transport calculations of radionuclides from the waste form through the vadose zone. A range of sorption parameters are provided for each key transport media, with recommended values being conservative. The range of uncertainty has been bounded through an assessment of most-likely-minimum and most-likely-maximum distribution coefficient values. The range allows for adequate assessment of mean facility performance while providing the basis for uncertainty analysis.

D. Craig Cooper

2011-11-01T23:59:59.000Z

173

2Q CY2000 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

"The Facility Representative Program Performance Indicators (PIs) Quarterly Report is attached, covering the period from April 2000 to June 2000. Data for these indicators are gathered by the Field...

174

2Q CY2001 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representive Program Performance Indicators (PIs) Quarterly Report is attached covering the period from April to June 2001. Data for these indicators are gathered by the Field elements...

175

3Q CY2002, Facility Representative Program Performance Indicators  

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

into a pressured argon line) performed on an already reviewed work order and that lockouttagout procedures were not followed. These problems were formally addressed,...

176

2011 PERFORMANCE ASSESSMENT COMMUNITY OF PRACTICE TECHNICAL EXCHANGE - SUMMARY  

SciTech Connect (OSTI)

The Performance Assessment Community of Practice (PA CoP) was developed in 2008 to improve consistency and quality in the preparation of performance assessments (PAs) and risk assessments across the Department of Energy (DOE) Complex. The term, PA, is used to represent all of these modeling applications in this report. The PA CoP goals are to foster the exchange of information among PA practitioners and to share lessons learned from PAs conducted for DOE, commercial disposal facilities, and international entities. Technical exchanges and workshops are a cornerstone of PA CoP activities. Previous technical exchanges have addressed Engineered Barriers (2009 - http://www.cresp.org/education/workshops/pacop/), the Advanced Simulation Capability for Environmental Management and the Cementitious Barriers Partnership (2010 - http://srnl.doe.gov/copexchange/links.htm). Each technical exchange also includes summary presentations regarding activities at DOE, the Nuclear Regulatory Commission (NRC) and other organizations (e.g., International Atomic Energy Agency (IAEA)) as well as a number of presentations from selected sites to provide insight and perspective from on-going modeling activities. Through the deployment of PA Assistance Teams, the PA CoP has also been engaged in the development of new PAs across the DOE Complex. As a way of improving consistency in the preparation of new PAs, the teams provide technical advice and share experiences, noteworthy practices, and lessons learned from previous Low-Level Waste Disposal Facility Federal Review Group (LFRG) reviews. Teams have provided support for PAs at Hanford, Idaho, Paducah and Portsmouth. The third annual PA CoP Technical Exchange was held on May 25-26, 2011 in Atlanta, GA. The PA CoP Steering Committee Meeting held its first meeting on May 24 prior to the Technical Exchange. Decision making using models and software quality assurance were the topical emphasis for the exchange. A new feature at the 2011 technical exchange was the use of panel discussions to solicit feedback from regulators and practitioners. This report summarizes discussions and recommendations from the steering committee meeting and presentations and feedback obtained at the technical exchange. Appendix I includes the steering committee meeting agenda and Appendix II includes the agenda for the technical exchange and a screenshot of the presentations and video files that are available online.

Seitz, R.

2011-12-30T23:59:59.000Z

177

Evolution Of USDOE Performance Assessments Over 20 Years  

SciTech Connect (OSTI)

Performance assessments (PAs) have been used for many years for the analysis of post-closure hazards associated with a radioactive waste disposal facility and to provide a reasonable expectation of the ability of the site and facility design to meet objectives for the protection of members of the public and the environment. The use of PA to support decision-making for LLW disposal facilities has been mandated in United States Department of Energy (USDOE) directives governing radioactive waste management since 1988 (currently DOE Order 435.1, Radioactive Waste Management). Prior to that time, PAs were also used in a less formal role. Over the past 20+ years, the USDOE approach to conduct, review and apply PAs has evolved into an efficient, rigorous and mature process that includes specific requirements for continuous improvement and independent reviews. The PA process has evolved through refinement of a graded and iterative approach designed to help focus efforts on those aspects of the problem expected to have the greatest influence on the decision being made. Many of the evolutionary changes to the PA process are linked to the refinement of the PA maintenance concept that has proven to be an important element of USDOE PA requirements in the context of supporting decision-making for safe disposal of LLW. The PA maintenance concept represents the evolution of the graded and iterative philosophy and has helped to drive the evolution of PAs from a deterministic compliance calculation into a systematic approach that helps to focus on critical aspects of the disposal system in a manner designed to provide a more informed basis for decision-making throughout the life of a disposal facility (e.g., monitoring, research and testing, waste acceptance criteria, design improvements, data collection, model refinements). A significant evolution in PA modeling has been associated with improved use of uncertainty and sensitivity analysis techniques to support efficient implementation of the graded and iterative approach. Rather than attempt to exactly predict the migration of radionuclides in a disposal unit, the best PAs have evolved into tools that provide a range of results to guide decision-makers in planning the most efficient, cost effective, and safe disposal of radionuclides.

Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States); Suttora, Linda C. [U.S. Department of Energy, Office of Site Restoration, Germantown, MD (United States)

2013-02-26T23:59:59.000Z

178

Evolution of US DOE Performance Assessments Over 20 Years - 13597  

SciTech Connect (OSTI)

Performance assessments (PAs) have been used for many years for the analysis of post-closure hazards associated with a radioactive waste disposal facility and to provide a reasonable expectation of the ability of the site and facility design to meet objectives for the protection of members of the public and the environment. The use of PA to support decision-making for LLW disposal facilities has been mandated in United States Department of Energy (US DOE) directives governing radioactive waste management since 1988 (currently DOE Order 435.1, Radioactive Waste Management). Prior to that time, PAs were also used in a less formal role. Over the past 20+ years, the US DOE approach to conduct, review and apply PAs has evolved into an efficient, rigorous and mature process that includes specific requirements for continuous improvement and independent reviews. The PA process has evolved through refinement of a graded and iterative approach designed to help focus efforts on those aspects of the problem expected to have the greatest influence on the decision being made. Many of the evolutionary changes to the PA process are linked to the refinement of the PA maintenance concept that has proven to be an important element of US DOE PA requirements in the context of supporting decision-making for safe disposal of LLW. The PA maintenance concept is central to the evolution of the graded and iterative philosophy and has helped to drive the evolution of PAs from a deterministic compliance calculation into a systematic approach that helps to focus on critical aspects of the disposal system in a manner designed to provide a more informed basis for decision-making throughout the life of a disposal facility (e.g., monitoring, research and testing, waste acceptance criteria, design improvements, data collection, model refinements). A significant evolution in PA modeling has been associated with improved use of uncertainty and sensitivity analysis techniques to support efficient implementation of the graded and iterative approach. Rather than attempt to exactly predict the migration of radionuclides in a disposal unit, the best PAs have evolved into tools that provide a range of results to guide decision-makers in planning the most efficient, cost effective, and safe disposal of radionuclides. (authors)

Suttora, Linda C. [U.S. Department of Energy, Office of Site Restoration, 19901 Germantown Rd, Germantown, MD 20874-1290 (United States)] [U.S. Department of Energy, Office of Site Restoration, 19901 Germantown Rd, Germantown, MD 20874-1290 (United States); Seitz, Roger R. [Savannah River National Laboratory, Savannah River Site, Bldg 773-43A, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Bldg 773-43A, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

179

EM Performs Tenth Technology Readiness Assessment  

Broader source: Energy.gov [DOE]

WASHINGTON, D.C. – EM recently completed its tenth Technology Readiness Assessment (TRA) since piloting the TRA process in 2006.

180

Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1  

SciTech Connect (OSTI)

The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

King, J.W.

1993-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Preliminary assessment report for National Guard Facility, Installation 25255, Rehoboth, Massachusetts. Installation Restoration Program  

SciTech Connect (OSTI)

This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Massachusetts Army National Guard (MAARNG) property known as the Rehoboth National Guard Facility (RNGF) in Rehoboth, Massachusetts. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for ftirther action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the RNGF property, phase I of the Department of Defense Installation Restoration Program (IRP). The scope of this assessment is limited to the facilities under the control of the MAARNG and the past activities contained within that area.

Haffenden, R.; Flaim, S.; Krokosz, M.

1993-08-01T23:59:59.000Z

182

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

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

manuals and data have been incorporated into activity documents. EN. 1.2 Spare parts inventory for activity and support equipment is adequate for activity performance. EN. 1.3 A...

183

Performance Assessment Monitoring Plan for the Hanford Site Low Level Waste Burial Grounds  

SciTech Connect (OSTI)

As directed by the U.S. Department of Energy (DOE), Richland Operations Office (DOE-RL), Fluor Hanford, Inc. will implement the requirements of DOE Order 435.1, Radioactive Waste Management, as the requirements relate to the continued operation of the low-level waste disposal facilities on the Hanford Site. DOE Order 435.1 requires a disposal authorization statement authorizing operation (or continued operation) of a low-level waste disposal facility. The objective of this Order is to ensure that all DOE radioactive waste is managed in a manner that protects the environment and personnel and public health and safety. The manual (DOE Order 435.1 Manual) implementing the Order states that a disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) of 1980 documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility. Failure to obtain a disposal authorization statement shall result in shutdown of an operational disposal facility. In fulfillment of the requirements of DOE Order 435.1, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area and the 200 West Area Low-Level Burial Grounds. The disposal authorization statement constitutes approval of the performance assessment and composite analysis, authorizes operation of the facility, and includes conditions that the disposal facility must meet. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area Low-Level Burial Grounds be written and approved by the DOE-RL. The monitoring plan is to be updated and implemented within 1 year following issuance of the disposal authorization statement to incorporate and implement conditions specified in the statement. The plan must meet the following criteria. The site-specific performance assessment and composite analysis shall be used to determine the media, locations, radionuclides, and other substances monitored. The environmental monitoring program shall be designed to include measuring and evaluating releases, migration of radionuclides, disposal unit subsidence, and changes in disposal facility and disposal site parameters that may affect long-term performance. The environmental monitoring programs shall be capable of detecting changing trends in performance to allow application of any necessary corrective action before exceeding the performance objectives stated in the order.

SONNICHSEN, J.C.

2000-11-15T23:59:59.000Z

184

RCRA Facility Investigation/Remedial Investigation Report with the Baseline Risk Assessment for the 716-A Motor Shops Seepage Basin  

SciTech Connect (OSTI)

This document describes the RCRA Facility Investigation/Remedial Investigation/Baseline Risk Assessment of the 716-A Motor Shops Seepage Basin.

Palmer, E.

1997-08-25T23:59:59.000Z

185

Performance Assessment Updates for Waste Isolation Pilot Plant...  

Office of Environmental Management (EM)

December 12, 2014 To view all the P&RA CoP 2014 Technical Exchange Meeting videos click here. Video Presentation Performance Assessment Updates for Waste Isolation...

186

Assessing the Costs and Benefits of the Superior Energy Performance...  

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

This paper focuses on the business value of Superior Energy Performance (SEP(tm)) and ISO 50001, providing an assessment of the costs and benefits associated with SEP...

187

Historical Background on the Performance Assessment for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the U.S. Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a Research and development facility for the safe management storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and after site selection, the U.S. Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance. assessment conducted in 1996, which is summarized in this special issue of Reliability Engineering and System Safety. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This paper provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project.

RECHARD,ROBERT P.

1999-10-21T23:59:59.000Z

188

Mira Performance Boot Camp 2015 | Argonne Leadership Computing Facility  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challenge fundProject8 -3EutecticMindingMira Performance Boot Camp 2015

189

PERFORMANCE OF THE TESLA TEST FACILITY LINAC for the TESLA Collaboration  

E-Print Network [OSTI]

PERFORMANCE OF THE TESLA TEST FACILITY LINAC P. Castro for the TESLA Collaboration Abstract In order to test the performance of a superconducting linac, the TESLA Collaboration has built and operated for the TESLA design. Results of recent running periods will be summarized in this paper. 1 INTRODUCTION

190

Environmental Assessment for the new Whole Body Counter facility at the Savannah River Site  

SciTech Connect (OSTI)

The U.S. Department of Energy proposes to construct and operate a new in-vivo counting facility at the Savannah River Site for the monitoring of employees for internal radionuclides. The proposed facility, titled the new Whole Body Counter (WBC) facility, would house both the existing and additional new invivo counting equipment and facility support operations. The proposed facility would be sited and located in an area of the SRS in which background radiation levels are sufficiently low to assure accurate in-vivo counts and a location that would assure ease of access for occupational workers. This Environmental Assessment has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, and the requirements of the Council on Environmental Quality Regulations for Implementing NEPA (40 CPR Parts 1500-1508). NEPA requires the assessment of environmental consequences of Federal actions that may affect the quality of the human environment. The proposed action has independent utility to the Savannah River operations and will be necessary to support plant activities regardless of the makeup of the future mission at the site. As such, the proposed new WBC facility is treated as part of the preliminary Reconfiguration Programmatic Environmental Impact Statement ``No Action`` alternative.

Not Available

1993-01-01T23:59:59.000Z

191

Performance objectives for the Hanford Immobilized Low-Activity Waste (ILAW) performance assessment  

SciTech Connect (OSTI)

Performance objectives for the disposal of low activity waste from Hanford Waste Tanks have been developed. These objectives have been based on DOE requirements, programmatic requirements, and public involvement. The DOE requirements include regulations that direct the performance assessment and are cited within the Radioactive Waste Management Order (DOE Order 435.1). Performance objectives for other DOE complex performance assessments have been included.

MANN, F.M.

1999-03-17T23:59:59.000Z

192

Facility Energy Decision System (FEDS) Assessment Report for Fort Buchanan, Puerto Rico  

SciTech Connect (OSTI)

This report documents the findings of the Facility Energy Decision System (FEDS) assessment at Fort Buchanan, Puerto Rico, by a team of PNNL engineers under contract to the Installation Management Agency (IMA) Southeast Region Office (SERO). Funding support was also provided by the Department of Energy's Federal Energy Management Program. The purpose of the assessment was to determine how energy is consumed at Fort Buchanan, identify the most cost-effective energy retrofit measures, and calculate the potential energy and cost savings.

Chvala, William D.; Solana, Amy E.; Dixon, Douglas R.

2005-02-01T23:59:59.000Z

193

Historical Relationship Between Performance Assessment for Radioactive Waste Disposal and Other Types of Risk Assessment in the United States  

SciTech Connect (OSTI)

This paper describes the evolution of the process for assessing the hazards of a geologic disposal system for radioactive waste and, similarly, nuclear power reactors, and the relationship of this process with other assessments of risk, particularly assessments of hazards from manufactured carcinogenic chemicals during use and disposal. This perspective reviews the common history of scientific concepts for risk assessment developed to the 1950s. Computational tools and techniques developed in the late 1950s and early 1960s to analyze the reliability of nuclear weapon delivery systems were adopted in the early 1970s for probabilistic risk assessment of nuclear power reactors, a technology for which behavior was unknown. In turn, these analyses became an important foundation for performance assessment of nuclear waste disposal in the late 1970s. The evaluation of risk to human health and the environment from chemical hazards is built upon methods for assessing the dose response of radionuclides in the 1950s. Despite a shared background, however, societal events, often in the form of legislation, have affected the development path for risk assessment for human health, producing dissimilarities between these risk assessments and those for nuclear facilities. An important difference is the regulator's interest in accounting for uncertainty and the tools used to evaluate it.

RECHARD,ROBERT P.

2000-07-14T23:59:59.000Z

194

Regulatory basis for the Waste Isolation Pilot Plant performance assessment  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is the first operational repository designed for the safe disposal of transuranic (TRU) radioactive waste from the defense programs of the US Department of Energy (DOE). The US Environmental Protection Agency (EPA) is responsible for certifications and regulation of the WIPP facility for the radioactive components of the waste. The EPA has promulgated general radioactive waste disposal standards at 40 CFR Part 191. and WIPP-specific criteria to implement and interpret the generic disposal standards at 40 CFR Part 194. In October 1996. the DOE submitted its Compliance Certification Application (CCA) to the EPA to demonstrate compliance with the disposal standards at Subparts B and C of 40 CFR Part 191. This paper summarizes the development of the overall legal framework for radioactive waste disposal at the WIPP, the parallel development of the WIPP performance assessment (PA), and how the EPA disposal standards and implementing criteria formed the basis for the CCA WIPP PA. The CCA resulted in a certification in May 1998 by the EPA of the WIPP'S compliance with the EPA's disposal standard, thus enabling the WIPP to begin radioactive waste disposal.

HOWARD,BRYAN A.; CRAWFORD,M.B.; GALSON,D.A.; MARIETTA,MELVIN G.

2000-05-22T23:59:59.000Z

195

Renewable Energy Assessment of Bureau of Reclamation Land and Facilities Using Geographic Information Systems  

SciTech Connect (OSTI)

This report summarizes results of geographic information system screening for solar and wind potential at select Bureau of Reclamation lands in the western United States. The study included both utility-scale and facility-scale potential. This study supplements information in the report titled Renewable Energy Assessment for the Bureau of Reclamation: Final Report.

Heimiller, D.; Haase, S.; Melius, J.

2013-05-01T23:59:59.000Z

196

Final Pantex Report - 2006 [Phase 1 plan for assessment of Former Workers at the Pantex Facility  

SciTech Connect (OSTI)

The purpose of this project was to develop a Phase 1 plan for assessment of Former Workers at the Pantex Facility in Amarillo, TX and to determine the suitability to start a medical surveillance program among former workers for this site.

Abdo, Ronna

2013-07-18T23:59:59.000Z

197

Integrated assessment of a new Waste-to-Energy facility in Central Greece in the context of regional perspectives  

SciTech Connect (OSTI)

The main aim of this study is the integrated assessment of a proposed Waste-to-Energy facility that could contribute in the Municipal Solid Waste Management system of the Region of Central Greece. In the context of this paper alternative transfer schemes for supplying the candidate facility were assessed considering local conditions and economical criteria. A mixed-integer linear programming model was applied for the determination of optimum locations of Transfer Stations for an efficient supplying chain between the waste producers and the Waste-to-Energy facility. Moreover different Regional Waste Management Scenarios were assessed against multiple criteria, via the Multi Criteria Decision Making method ELECTRE III. The chosen criteria were total cost, Biodegradable Municipal Waste diversion from landfill, energy recovery and Greenhouse Gas emissions and the analysis demonstrated that a Waste Management Scenario based on a Waste-to-Energy plant with an adjacent landfill for disposal of the residues would be the best performing option for the Region, depending however on the priorities of the decision makers. In addition the study demonstrated that efficient planning is necessary and the case of three sanitary landfills operating in parallel with the WtE plant in the study area should be avoided. Moreover alternative cases of energy recovery of the candidate Waste-to-Energy facility were evaluated against the requirements of the new European Commission Directive on waste in order for the facility to be recognized as recovery operation. The latter issue is of high significance and the decision makers in European Union countries should take it into account from now on, in order to plan and implement facilities that recover energy efficiently. Finally a sensitivity check was performed in order to evaluate the effects of increased recycling rate, on the calorific value of treated Municipal Solid Waste and the gate fee of the candidate plant and found that increased recycling efforts would not diminish the potential for incineration with energy recovery from waste and neither would have adverse impacts on the gate fee of the Waste-to-Energy plant. In general, the study highlighted the need for efficient planning in solid waste management, by taking into account multiple criteria and parameters and utilizing relevant tools and methodologies into this context.

Perkoulidis, G. [Laboratory of Heat Transfer and Environmental Engineering, Department of Mechanical Engineering, Aristotle University of Thessaloniki, Box 483, GR-54124 Thessaloniki (Greece); Papageorgiou, A., E-mail: giou6@yahoo.g [Laboratory of Heat Transfer and Environmental Engineering, Department of Mechanical Engineering, Aristotle University of Thessaloniki, Box 483, GR-54124 Thessaloniki (Greece); Karagiannidis, A. [Laboratory of Heat Transfer and Environmental Engineering, Department of Mechanical Engineering, Aristotle University of Thessaloniki, Box 483, GR-54124 Thessaloniki (Greece); Kalogirou, S. [Waste to Energy Research and Technology Council (Greece)

2010-07-15T23:59:59.000Z

198

Pollution prevention opportunity assessment for MicroFab and SiFab facilities at Sandia National Laboratories.  

SciTech Connect (OSTI)

This Pollution Prevention Opportunity Assessment (PPOA) was conducted for the MicroFab and SiFab facilities at Sandia National Laboratories/New Mexico in Fiscal Year 2011. The primary purpose of this PPOA is to provide recommendations to assist organizations in reducing the generation of waste and improving the efficiency of their processes and procedures. This report contains a summary of the information collected, the analyses performed, and recommended options for implementation. The Sandia National Laboratories Environmental Management System (EMS) and Pollution Prevention (P2) staff will continue to work with the organizations to implement the recommendations.

Gerard, Morgan Evan

2011-12-01T23:59:59.000Z

199

CARD No. 33 Consideration of Drilling Events in Performance Assessments  

E-Print Network [OSTI]

CARD No. 33 Consideration of Drilling Events in Performance Assessments 33.A.1 BACKGROUND have an effect on the disposal system (61 FR 5228). Section 194.33, "Consideration of drilling events in performance assessments," sets forth specific requirements for incorporation of human-initiated drilling

200

Annual Summary of Immobilized Low Activity Tank Waste (ILAW) Performance Assessment  

SciTech Connect (OSTI)

As required by the Department of Energy (DOE) order on radioactive waste management (DOE 1999a) as implemented by the Maintenance Plan for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (Mann 2000a), an annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) must be submitted to DOE headquarters each year that a performance assessment is not submitted. Considering the results of data collection and analysis, the conclusions of the 1998 version of the ILAW PA (Mann 1998) as conditionally approved (DOE 1999b) remain valid, but new information indicates more conservatism in the results than previously estimated. A white paper (Mann 2000b) is attached as Appendix A to justify this statement. Recent ILAW performance estimates used on the waste form and geochemical data have resulted in increased confidence that the disposal of ILAW will meet performance objectives. The ILAW performance assessment program will continue to interact with science and technology activities, disposal facility design staff, and operations, as well as to continue to collect new waste form and disposal system data to further increase the understanding of the impacts of the disposal of ILAW. The next full performance assessment should be issued in the spring of 2001.

MANN, F M

2000-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" from the National Library of EnergyBeta (NLEBeta).
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201

A Dynamic Waste Isolation Pilot Plant Performance Assessment Tool - 12490  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Performance Assessment (PA) methodology comprises a toolbox used to demonstrate regulatory compliance of the repository after facility closure. The PA framework rests upon an extensive suite of computational codes. In some cases, significant alteration of code inputs is a tedious and difficult task. Due to the nature of the application for which they are used, PA codes used in support of WIPP regulatory compliance demonstration must satisfy stringent quality assurance requirements. Consequently, many of the coding practices used during original code development are still implemented today. A more efficient workflow configuration has the potential to alleviate difficulties associated with extensive code input modifications. Here, this potential is assessed via an implementation of a more flexible scientific workflow system for a subset of the codes used in WIPP PA. The scientific workflow approach taken here for a dynamic PA system enables users from disparate backgrounds to dramatically shorten the time between hypothesis and analysis by decreasing the amount of a priori knowledge, from a range of disciplines, needed to execute the code. Having smaller iteration times allows for more ideas to be tested and explored, which leads to safer and more optimized systems. Note that these high-level, dynamic tools are intended only for initial scoping studies on the personal computer of a researcher. Full, regulatory compliance calculations may occur only within a qualified computing environment. However, the WIPP PA tools here may guide future research and indicate regions of the analysis space that are worth further study. This next generation of PA software provides the ability to perform scoping investigations of repository performance quickly and easily, and has an accessible and useful interface to a variety of users, such as fuel cycle systems designers, domain experts such as repository modelers, and policy makers. The purview of this project allows for many opportunities for future work. Foremost among these is the desire to implement the full BRAGFLO suite within the workflow. This will entail porting or wrapping Genmesh, Matset, LHS, and ICSet within Python. Moreover, unifying the two GUIs into a single driver application would be a natural next step. Once the BRAGFLO suite is completed, other portions of WIPP PA could be implemented with corresponding and inter-operable work-flows. Likely first candidates for this are those codes that are similarly computationally intensive, such as the one used to generate complementary cumulative distribution functions used to demonstrate regulatory compliance (code CCDFGF). (authors)

Scopatz, Anthony M.; March, Jonathan; Weckesser, Warren; Jones, Eric [Enthought Inc, Austin, Texas, 78701 (United States); Lee, Moo; Camphouse, Chris [Sandia National Laboratories, Carlsbad, NM, 88220 (United States)

2012-07-01T23:59:59.000Z

202

Fort Irwin integrated resource assessment. Volume 3: Sitewide Energy Project identification for buildings and facilities  

SciTech Connect (OSTI)

The U.S. Army Forces Command (FORSCOM) has tasked the U.S. Department of Energy (DOE) Federal Energy Management Program (FEMP), supported by the Pacific Northwest Laboratory, to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Irwin. This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the FORSCOM Fort Irwin facility located near Barstow, California. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analyses of EROs are presented in 16 common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). A narrative description of each ERO is provided, along with a table detailing information on the installed cost, energy and dollar savings; impacts on operations and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO and present the results of the life-cycle cost (LCC) analysis indicating the net present valve (NPV) and savings-to-investment ratio (SIR) of each ERO.

Keller, J.M.; Dittmer, A.L.; Elliott, D.B.; McMordie, K.L.; Richman, E.E.; Stucky, D.J.; Wahlstrom, R.R.; Hadley, D.L.

1995-02-01T23:59:59.000Z

203

Assessing the performance of the saltstone wasteform at the Savannah River Site  

SciTech Connect (OSTI)

The radiological performance of the saltstone disposal facility (SDF) for low-level waste (LLW) at the Savannah River Site is being assessed in accordance with a US Department of Energy Order which was issued in 1988. Saltstone is a high-nitrate concrete matrix formed as a result of solidification of LLW streams. Potential human exposures to radionuclides that will be disposed of in the facility are being addressed. Engineered features of the SDF reduce and retard releases of radionuclides from the facility, but degradation of the features must be considered. Because prediction of the extent and timing of degradation becomes more uncertain over time, predicted releases also become more uncertain, particularly for long-lived radionuclides still present in the facility far into the future. Preliminary analyses indicate that long-lived radionuclides are the saltstone constitutents of greatest concern for radiological protection of groundwater resources. Application of federal drinking water standards to untreated groundwater may be a limiting requirement for LLW disposal facilities like the SDF, where the groundwater pathway is the most important for human exposure to radionuclides. The 4-mrem annual dose limit imposed by these standards is well below limits imposed by other regulations with which the disposal facilities must comply.

McDowell-Boyer, L.M.; Kocher, D.C. [Oak Ridge National Lab., TN (United States); Cook, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States)

1992-03-01T23:59:59.000Z

204

Assessing the performance of the saltstone wasteform at the Savannah River Site  

SciTech Connect (OSTI)

The radiological performance of the saltstone disposal facility (SDF) for low-level waste (LLW) at the Savannah River Site is being assessed in accordance with a US Department of Energy Order which was issued in 1988. Saltstone is a high-nitrate concrete matrix formed as a result of solidification of LLW streams. Potential human exposures to radionuclides that will be disposed of in the facility are being addressed. Engineered features of the SDF reduce and retard releases of radionuclides from the facility, but degradation of the features must be considered. Because prediction of the extent and timing of degradation becomes more uncertain over time, predicted releases also become more uncertain, particularly for long-lived radionuclides still present in the facility far into the future. Preliminary analyses indicate that long-lived radionuclides are the saltstone constitutents of greatest concern for radiological protection of groundwater resources. Application of federal drinking water standards to untreated groundwater may be a limiting requirement for LLW disposal facilities like the SDF, where the groundwater pathway is the most important for human exposure to radionuclides. The 4-mrem annual dose limit imposed by these standards is well below limits imposed by other regulations with which the disposal facilities must comply.

McDowell-Boyer, L.M.; Kocher, D.C. (Oak Ridge National Lab., TN (United States)); Cook, J.R. (Westinghouse Savannah River Co., Aiken, SC (United States))

1992-01-01T23:59:59.000Z

205

Quality assessment: A performance-based approach to assessments  

SciTech Connect (OSTI)

Revision C to US Department of Energy (DOE) Order 5700.6 (6C) ``Quality Assurance`` (QA) brings significant changes to the conduct of QA. The Westinghouse government-owned, contractor-operated (GOCO) sites have updated their quality assurance programs to the requirements and guidance of 6C, and are currently implementing necessary changes. In late 1992, a Westinghouse GOCO team led by the Waste Isolation Division (WID) conducted what is believed to be the first assessment of implementation of a quality assurance program founded on 6C.

Caplinger, W.H.; Greenlee, W.D.

1993-08-01T23:59:59.000Z

206

Money for Research, Not for Energy Bills: Finding Energy and Cost Savings in High Performance Computer Facility Designs  

E-Print Network [OSTI]

Journal of High Performance Computing Applications 22 (2).is both a model of high-performance computing and a showcaseAbstract High-performance computing facilities in the United

Sartor, Dale

2011-01-01T23:59:59.000Z

207

Technical Basis for Assessing Uranium Bioremediation Performance  

SciTech Connect (OSTI)

In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation.

PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N’Guessan

2008-04-01T23:59:59.000Z

208

US DOE-EM On-Site Disposal Cell Working Group - Fostering Communication On Performance Assessment Challenges  

SciTech Connect (OSTI)

On-site disposal cells are in use and being considered at several U.S. Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These facilities are typically developed with regulatory oversight from States and/or the US Environmental Protection Agency (USEPA) in addition to USDOE. The facilities are developed to meet design standards for disposal of hazardous waste as well as the USDOE performance based standards for disposal of radioactive waste. The involvement of multiple and different regulators for facilities across separate sites has resulted in some differences in expectations for performance assessments and risk assessments (PA/RA) that are developed for the disposal facilities. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. The working group holds teleconferences, as needed, focusing on specific topics of interest. The topics addressed to date include an assessment of the assumptions used for performance assessments and risk assessments (PA/RAs) for on-site disposal cells, requirements and assumptions related to assessment of inadvertent intrusion, DOE Manual 435.1-1 requirements, and approaches for consideration of the long-term performance of liners and covers in the context of PAs. The working group has improved communication among the staff and oversight personnel responsible for onsite disposal cells and has provided a forum to identify and resolve common concerns.

Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States); Suttora, Linda C. [U.S. Department of Energy, Office of Site Restoration, Germantown, MD (United States); Phifer, Mark [Savannah River Site (SRS), Aiken, SC (United States)

2014-03-01T23:59:59.000Z

209

Performance assessment for continuing and future operations at Solid Waste Storage Area 6  

SciTech Connect (OSTI)

This radiological performance assessment for the continued disposal operations at Solid Waste Storage Area 6 (SWSA 6) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US DOE. The analysis of SWSA 6 required the use of assumptions to supplement the available site data when the available data were incomplete for the purpose of analysis. Results indicate that SWSA 6 does not presently meet the performance objectives of DOE Order 5820.2A. Changes in operations and continued work on the performance assessment are expected to demonstrate compliance with the performance objectives for continuing operations at the Interim Waste Management Facility (IWMF). All other disposal operations in SWSA 6 are to be discontinued as of January 1, 1994. The disposal units at which disposal operations are discontinued will be subject to CERCLA remediation, which will result in acceptable protection of the public health and safety.

Not Available

1994-02-01T23:59:59.000Z

210

AUTOMATICALLY ASSESSING THE PERFORMANCE OF AN ...  

E-Print Network [OSTI]

efficiently by taking explicit advantage of the family of discretizations. ... This might be appropriate if a single property of the optimization problem would be ... either as a by-product of finding the solution or with low-cost auxiliary computations. ..... A line search is then performed to determine the new estimate of the solution:.

2008-05-02T23:59:59.000Z

211

Total system performance assessment - 1995: An evaluation of the potential Yucca Mountain repository  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is currently investigating the feasibility of permanently disposing the nation`s commercial high-level radioactive wastes (in the form of spent fuel from the over 100 electric power-generating nuclear reactors across the U.S.) and a portion of the defense high-level radioactive wastes (currently stored at federal facilities around the country) in the unsaturated tuffaceous rocks at Yucca Mountain, Nevada. Quantitative predictions based on the most current understanding of the processes and parameters potentially affecting the long-term behavior of the disposal system are used to assess the ability of the site and its associated engineered designs to meet regulatory objectives of the US NRC and the US EPA. The evaluation of the ability of the overall system to meet the performance objectives specified in the applicable regulatory standards has been termed total system performance assessment (TSPA). Total system performance assessments require the explicit quantification of the relevant processes and process interactions. In addition assessments are useful to help define the most significant processes, the information gaps and uncertainties and therefore the additional information required for more robust and defensible assessment of the overall performance. The aim of any total system performance assessment is to be as complete and reasonably conservative as possible and to assure that the descriptions of the predictive models and parameters are sufficient to ascertain their accuracy. Total system performance assessments evolve with time. Previous iterations of total system performance assessment of the Yucca Mountain site and associated engineered barriers have been conducted in 1991 and 1993.

Atkins, J.E.; Lee, J.H.; Lingineni, S.; Mishra, S; McNeish, J.A.; Sassani, D.C.; Sevougian, S.D.

1995-11-01T23:59:59.000Z

212

Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

Not Available

1992-09-01T23:59:59.000Z

213

Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana  

SciTech Connect (OSTI)

The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI).

NONE

1995-12-01T23:59:59.000Z

214

Money for Research, Not for Energy Bills: Finding Energy and Cost Savings in High Performance Computer Facility Designs  

SciTech Connect (OSTI)

High-performance computing facilities in the United States consume an enormous amount of electricity, cutting into research budgets and challenging public- and private-sector efforts to reduce energy consumption and meet environmental goals. However, these facilities can greatly reduce their energy demand through energy-efficient design of the facility itself. Using a case study of a facility under design, this article discusses strategies and technologies that can be used to help achieve energy reductions.

Drewmark Communications; Sartor, Dale; Wilson, Mark

2010-07-01T23:59:59.000Z

215

An Integrated Assessment of Location-Dependent Scaling for Microalgae Biofuel Production Facilities  

SciTech Connect (OSTI)

Successful development of a large-scale microalgae-based biofuels industry requires comprehensive analysis and understanding of the feedstock supply chain—from facility siting/design through processing/upgrading of the feedstock to a fuel product. The evolution from pilot-scale production facilities to energy-scale operations presents many multi-disciplinary challenges, including a sustainable supply of water and nutrients, operational and infrastructure logistics, and economic competitiveness with petroleum-based fuels. These challenges are addressed in part by applying the Integrated Assessment Framework (IAF)—an integrated multi-scale modeling, analysis, and data management suite—to address key issues in developing and operating an open-pond facility by analyzing how variability and uncertainty in space and time affect algal feedstock production rates, and determining the site-specific “optimum” facility scale to minimize capital and operational expenses. This approach explicitly and systematically assesses the interdependence of biofuel production potential, associated resource requirements, and production system design trade-offs. The IAF was applied to a set of sites previously identified as having the potential to cumulatively produce 5 billion-gallons/year in the southeastern U.S. and results indicate costs can be reduced by selecting the most effective processing technology pathway and scaling downstream processing capabilities to fit site-specific growing conditions, available resources, and algal strains.

Coleman, Andre M.; Abodeely, Jared; Skaggs, Richard; Moeglein, William AM; Newby, Deborah T.; Venteris, Erik R.; Wigmosta, Mark S.

2014-06-19T23:59:59.000Z

216

Status Updates on the Performance and Risk Assessment Community...  

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

NV December 11-12, 2014 To view all the P&RA CoP 2014 Technical Exchange Meeting videos click here. Video Presentation Status Updates on the Performance and Risk Assessment...

217

Annual Performance Assessment and Composite Analysis Review for the ICDF Landfill FY 2008  

SciTech Connect (OSTI)

This report addresses low-level waste disposal operations at the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) landfill from the start of operations in Fiscal Year 2003 through Fiscal Year 2008. The ICDF was authorized in the Operable Unit 3-13 Record of Decision for disposal of waste from the Idaho National Laboratory Site CERCLA environmental restoration activities. The ICDF has been operating since 2003 in compliance with the CERCLA requirements and the waste acceptance criteria developed in the CERCLA process. In developing the Operable Unit 3-13 Record of Decision, U.S. Department of Energy Order (DOE) 435.1, 'Radioactive Waste Management', was identified as a 'to be considered' requirement for the ICDF. The annual review requirement under DOE Order 435.1 was determined to be an administrative requirement and, therefore, annual reviews were not prepared on an annual basis. However, the landfill has been operating for 5 years and, since the waste forms and inventories disposed of have changed from what was originally envisioned for the ICDF landfill, the ICDF project team has decided that this annual review is necessary to document the changes and provide a basis for any updates in analyses that may be necessary to continue to meet the substantive requirements of DOE Order 435.1. For facilities regulated under DOE Order 435.1-1, U.S. DOE Manual 435.1-1, 'Radioactive Waste Management', IV.P.(4)(c) stipulates that annual summaries of low-level waste disposal operations shall be prepared with respect to the conclusions and recommendations of the performance assessment and composite analysis. Important factors considered in this review include facility operations, waste receipts, and results from monitoring and research and development programs. There have been no significant changes in operations at the landfill in respect to the disposal geometry, the verification of waste characteristics, and the tracking of inventories against total limits that would affect the results and conclusions of the performance assessment. Waste receipts to date and projected waste receipts through Fiscal Year 2012 are both greater than the inventory assessed in the performance assessment and composite analysis. The waste forms disposed of to the landfill are different from the waste form (compacted soil) assessed in the performance assessment. The leak detection system and groundwater monitoring results indicate the landfill has not leaked. The results of the performance assessment/composite analysis are valid (i.e., there is still a reasonable expectation of meeting performance objectives) but the new information indicates less conservatism in the results than previously believed.

Karen Koslow

2009-08-31T23:59:59.000Z

218

Hanford low-level tank waste interim performance assessment  

SciTech Connect (OSTI)

The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

Mann, F.M.

1997-09-12T23:59:59.000Z

219

Hanford low-level tank waste interim performance assessment  

SciTech Connect (OSTI)

The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single- and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and its performance as early as possible in the project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

Mann, F.M.

1996-09-16T23:59:59.000Z

220

Synchronous and Cogged Fan Belt Performance Assessment  

SciTech Connect (OSTI)

The GSA Regional GPG Team commissioned the National Renewable Energy Laboratory (NREL) to perform monitoring of cogged V-belts and synchronous belts on both a constant volume and a variable air volume fan at the Byron G. Rodgers Federal Building and U.S. Courthouse in Denver, Colorado. These motor/fan combinations were tested with their original, standard V-belts (appropriately tensioned by an operation and maintenance professional) to obtain a baseline for standard operation. They were then switched to the cogged V-belts, and finally to synchronous belts. The power consumption by the motor was normalized for both fan speed and air density changes. This was necessary to ensure that the power readings were not influenced by a change in rotational fan speed or by the power required to push denser air. Finally, energy savings and operation and maintenance savings were compiled into an economic life-cycle cost analysis of the different belt options.

Cutler, D.; Dean, J.; Acosta, J.

2014-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Formation of a performance-based MC&A assessment program  

SciTech Connect (OSTI)

Department of Energy Order 5633.3, Control and Accountability of Nuclear Materials, requires each facility possessing nuclear material (NM) to {open_quotes}establish a program to assess its control and accountability systems and procedures, and to assure the integrity and quality of these systems.{close_quotes} This paper describes the formation of a performance-based assessment group within Westinghouse Savannah River Company (WSRC) Material Control and Accountability (MC&A) in response to this requirement. The Assessment Group was formed to evaluate both compliance to requirements and system performance capability as determined by performance testing. Evaluations address the five functional areas of MC&A: administration, containment, accounting, measurement, and inventory programs. The assessments performed by this group are used to substantiate the degree of MC&A compliance with requirements and to determine system capability to protect NM in accordance with graded safeguards. Assessment reports provide documented evidence of the integrity and quality of the systems comprising the MC&A program at WSRC.

Johnson, H.D.; Wolf, D.A.

1993-07-01T23:59:59.000Z

222

Performance Assessment of the Wave Dragon Wave Energy Converter  

E-Print Network [OSTI]

Performance Assessment of the Wave Dragon Wave Energy Converter Based on the EquiMar Methodology S of the wave energy sector, device developers are called to provide reliable estimates on power performanceMar, Nissum Bredning, Hanstholm, North Sea, Ekofisk, Wave-to-wire, Wave energy. I. INTRODUCTION The wave

Hansen, René Rydhof

223

DOE High Performance Computing Operational Review (HPCOR): Enabling Data-Driven Scientific Discovery at HPC Facilities  

SciTech Connect (OSTI)

U.S. Department of Energy (DOE) High Performance Computing (HPC) facilities are on the verge of a paradigm shift in the way they deliver systems and services to science and engineering teams. Research projects are producing a wide variety of data at unprecedented scale and level of complexity, with community-specific services that are part of the data collection and analysis workflow. On June 18-19, 2014 representatives from six DOE HPC centers met in Oakland, CA at the DOE High Performance Operational Review (HPCOR) to discuss how they can best provide facilities and services to enable large-scale data-driven scientific discovery at the DOE national laboratories. The report contains findings from that review.

Gerber, Richard; Allcock, William; Beggio, Chris; Campbell, Stuart; Cherry, Andrew; Cholia, Shreyas; Dart, Eli; England, Clay; Fahey, Tim; Foertter, Fernanda; Goldstone, Robin; Hick, Jason; Karelitz, David; Kelly, Kaki; Monroe, Laura; Prabhat,; Skinner, David; White, Julia

2014-10-17T23:59:59.000Z

224

Environmental Assessment for the LGF Spill Test Facility at Frenchman Flat, Nevada Test Site  

SciTech Connect (OSTI)

The LGF Spill Test Facility at Frenchman Flat, Nevada Test Site, is being constructed by the United States Department of Energy (DOE). In this Environmental Assessment, environmental consequences of spilling hazardous materials in the Frenchman Flat basin are evaluated and mitigations and recommendations are stated in order to protect natural resources and reduce land-use impacts. Guidelines and restrictions concerning spill-test procedures will be determined by the LGF Test Facility Operations Manager and DOE based on toxicity documentation for the test material, provided by the user, and mitigations imposed by the Environmental Assessment. In addition to Spill Test Facility operational procedures, certain assumptions have been made in preparation of this document: no materials will be considered for testing that have cumulative, long-term persistence in the environment; spill tests will consist of releases of 15 min or less; and sufficient time will be allowed between tests for recovery of natural resources. Geographic limits to downwind concentrations of spill materials were primarily determined from meteorological data, human occupational exposure standards to hazardous materials and previous spill tests. These limits were established using maximum spill scenarios and environmental impacts are discussed as worst case scenarios; however, spill-test series will begin with smaller spills, gradually increasing in size after the impacts of the initial tests have been evaluated.

Patton, S.E.; Novo, M.G.; Shinn, J.H.

1986-04-01T23:59:59.000Z

225

Assessment of External Hazards at Radioactive Waste and Used Fuel Management Facilities - 13505  

SciTech Connect (OSTI)

One of the key lessons from the Fukushima accident is the importance of having a comprehensive identification and evaluation of risks posed by external events to nuclear facilities. While the primary focus has been on nuclear power plants, the Canadian nuclear industry has also been updating hazard assessments for radioactive waste and used fuel management facilities to ensure that lessons learnt from Fukushima are addressed. External events are events that originate either physically outside the nuclear site or outside its control. They include natural events, such as high winds, lightning, earthquakes or flood due to extreme rainfall. The approaches that have been applied to the identification and assessment of external hazards in Canada are presented and analyzed. Specific aspects and considerations concerning hazards posed to radioactive waste and used fuel management operations are identified. Relevant hazard identification techniques are described, which draw upon available regulatory guidance and standard assessment techniques such as Hazard and Operability Studies (HAZOPs) and 'What-if' analysis. Consideration is given to ensuring that hazard combinations (for example: high winds and flooding due to rainfall) are properly taken into account. Approaches that can be used to screen out external hazards, through a combination of frequency and impact assessments, are summarized. For those hazards that cannot be screened out, a brief overview of methods that can be used to conduct more detailed hazard assessments is also provided. The lessons learnt from the Fukushima accident have had a significant impact on specific aspects of the approaches used to hazard assessment for waste management. Practical examples of the effect of these impacts are provided. (authors)

Gerchikov, Mark; Schneider, Glenn; Khan, Badi; Alderson, Elizabeth [AMEC NSS, 393 University Ave., Toronto, ON (Canada)] [AMEC NSS, 393 University Ave., Toronto, ON (Canada)

2013-07-01T23:59:59.000Z

226

Total system performance assessment - 1995: An evaluation of the potential Yucca Mountain Repository  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is currently investigating the feasibility of permanently disposing the nation`s commercial high-level radioactive wastes (in the form of spent fuel from the over 100 electric power-generating nuclear reactors across the U.S.) and a portion of the defense high-level radioactive wastes (currently stored at federal facilities around the country) in the unsaturated tuffaceous rocks at Yucca Mountain, Nevada. Quantitative predictions based on the most current understanding of the processes and parameters potentially affecting the long-term behavior of the disposal system are used to assess the ability of the site and its associated engineered designs to meet regulatory objectives set forward by the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental Protection Agency (EPA). The evaluation of the ability of the overall system to meet the performance objectives specified in the applicable regulatory standards has been termed total system performance assessment (TSPA). The aim of any total system performance assessment is to be as complete and reasonably conservative as possible and to assure that the descriptions of the predictive models and parameters are sufficient to ascertain their accuracy. Total system performance assessments evolve with time. As additional site and design information is generated, performance assessment analyses can be revised to become more representative of the expected conditions and remove some of the conservative assumptions necessitated by the incompleteness of site and design data. Previous iterations of total system performance assessment of the Yucca Mountain site and associated engineered barriers have been conducted in 1991 and 1993. These analyses have been documented in Barnard, Eslinger, Wilson and Andrews.

NONE

1995-11-01T23:59:59.000Z

227

A formal expert judgment procedure for performance assessments of the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is an experimental facility located in southeastern New Mexico. It has been designed to determine the feasibility of the geologic disposal of defense-generated transuranic waste in a deep bedded-salt formation. The WIPP was also designed for disposal and will operate in that capacity if approved. The WIPP Performance Assessment Department at Sandia National Laboratories has been conducting analyses to assess the long-term performance of the WIPP. These analyses sometimes require the use of expert judgment. This Department has convened several expert-judgment panels and from that experience has developed an internal quality-assurance procedure to guide the formal elicitation of expert judgment. This protocol is based on the principles found in the decision-analysis literature.

Trauth, K.M. [Sandia National Labs., Albuquerque, NM (United States); Guzowski, R.V. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States). Business Administration & Economics Div.

1994-09-01T23:59:59.000Z

228

White paper updating conclusions of 1998 ILAW performance assessment  

SciTech Connect (OSTI)

The purpose of this document is to provide a comparison of the estimated immobilized low-activity waste (LAW) disposal system performance against established performance objectives using the beat estimates for parameters and models to describe the system. The principal advances in knowledge since the last performance assessment (known as the 1998 ILAW PA [Mann 1998a]) have been in site specific information and data on the waste form performance for BNFL, Inc. relevant glass formulations. The white paper also estimates the maximum release rates for technetium and other key radionuclides and chemicals from the waste form. Finally, this white paper provides limited information on the impact of changes in waste form loading.

MANN, F.M.

2000-05-11T23:59:59.000Z

229

Data Quality Assessment and Control for the ARM Climate Research Facility  

SciTech Connect (OSTI)

The mission of the Atmospheric Radiation Measurement (ARM) Climate Research Facility is to provide observations of the earth climate system to the climate research community for the purpose of improving the understanding and representation, in climate and earth system models, of clouds and aerosols as well as their coupling with the Earth's surface. In order for ARM measurements to be useful toward this goal, it is important that the measurements are of a known and reasonable quality. The ARM data quality program includes several components designed to identify quality issues in near-real-time, track problems to solutions, assess more subtle long-term issues, and communicate problems to the user community.

Peppler, R

2012-06-26T23:59:59.000Z

230

RELAP5/MOD3.2 Assessment Using CHF Data from the KS-1 and V-200 Experiment Facilities  

SciTech Connect (OSTI)

The RELAP/MOD3.2 computer code has been assessed using rod bundle critical heat flux data from the KS-1 and V-200 facilities. This work was performed as part of the U.S. Department of Energy’s International Nuclear Safety Program, and is part of the effort addressing the capability of the RELAP5/MOD3.2 code to model transients in Soviet-designed reactors. Designated VVER Standard Problem 7, these tests addressed one of the important phenomena related to VVER behavior that the code needs to simulate well, core heat transfer. The code was judged to be in minimal agreement with the experiment data, consistently overpredicting the measured critical heat flux. It is recommended that a model development effort be undertaken to develop a critical heat flux model for RELAP5 that better represents the behavior in VVER rod bundles.

Bayless, Paul David

2001-07-01T23:59:59.000Z

231

Facilities Condition and Hazards Assessment for Materials and Fuel Complex Facilities MFC-799, 799A, and 770C  

SciTech Connect (OSTI)

The Materials & Fuel Complex (MFC) facilities 799 Sodium Processing Facility (a single building consisting of two areas: the Sodium Process Area (SPA) and the Carbonate Process Area (CPA), 799A Caustic Storage Area, and 770C Nuclear Calibration Laboratory have been declared excess to future Department of Energy mission requirements. Transfer of these facilities from Nuclear Energy to Environmental Management, and an associated schedule for doing so, have been agreed upon by the two offices. The prerequisites for this transfer to occur are the removal of nonexcess materials and chemical inventory, deinventory of the calibration source in MFC-770C, and the rerouting and/or isolation of utility and service systems. This report provides a description of the current physical condition and any hazards (material, chemical, nuclear or occupational) that may be associated with past operations of these facilities. This information will document conditions at time of transfer of the facilities from Nuclear Energy to Environmental Management and serve as the basis for disposition planning. The process used in obtaining this information included document searches, interviews and facility walk-downs. A copy of the facility walk-down checklist is included in this report as Appendix A. MFC-799/799A/770C are all structurally sound and associated hazardous or potentially hazardous conditions are well defined and well understood. All installed equipment items (tanks, filters, etc.) used to process hazardous materials remain in place and appear to have maintained their integrity. There is no evidence of leakage and all openings are properly sealed or closed off and connections are sound. The pits appear clean with no evidence of cracking or deterioration that could lead to migration of contamination. Based upon the available information/documentation reviewed and the overall conditions observed during the facilities walk-down, it is concluded that these facilities may be disposed of at minimal risk to human health, safety or the environment.

Gary Mecham; Don Konoyer

2009-11-01T23:59:59.000Z

232

Environmental assessment for device assembly facility operations, Nevada Test Site, Nye County, Nevada. Final report  

SciTech Connect (OSTI)

The U.S. Department of Energy, Nevada Operations Office (DOE/NV), has prepared an environmental assessment (EA), (DOE/EA-0971), to evaluate the impacts of consolidating all nuclear explosive operations at the newly constructed Device Assembly Facility (DAF) in Area 6 of the Nevada Test Site. These operations generally include assembly, disassembly or modification, staging, transportation, testing, maintenance, repair, retrofit, and surveillance. Such operations have previously been conducted at the Nevada Test Site in older facilities located in Area 27. The DAF will provide enhanced capabilities in a state-of-the-art facility for the safe, secure, and efficient handling of high explosives in combination with special nuclear materials (plutonium and highly enriched uranium). Based on the information and analyses in the EA, DOE has determined that the proposed action would not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (42 U.S.C. 4321 et seq.). Therefore, an environmental impact statement is not required, and DOE is issuing this finding of no significant impact.

NONE

1995-05-01T23:59:59.000Z

233

Environmental assessment for the Radioactive and Mixed Waste Management Facility: Sandia National Laboratories/New Mexico  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0466) under the National Environmental Policy Act (NEPA) of 1969 for the proposed completion of construction and subsequent operation of a central Radioactive and Mixed Waste Management Facility (RMWMF), in the southeastern portion of Technical Area III at Sandia National Laboratory, Albuquerque (SNLA). The RMWMF is designed to receive, store, characterize, conduct limited bench-scale treatment of, repackage, and certify low-level waste (LLW) and mixed waste (MW) (as necessary) for shipment to an offsite disposal or treatment facility. The RMWMF was partially constructed in 1989. Due to changing regulatory requirements, planned facility upgrades would be undertaken as part of the proposed action. These upgrades would include paving of road surfaces and work areas, installation of pumping equipment and lines for surface impoundment, and design and construction of air locks and truck decontamination and water treatment systems. The proposed action also includes an adjacent corrosive and reactive metals storage area, and associated roads and paving. LLW and MW generated at SNLA would be transported from the technical areas to the RMWMF in containers approved by the Department of Transportation. The RMWMF would not handle nonradioactive hazardous waste. Based on the analysis in the EA, the proposed completion of construction and operation of the RMWMF does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of NEPA. Therefore, preparation of an environmental impact statement for the proposed action is not required.

Not Available

1993-06-01T23:59:59.000Z

234

Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993  

SciTech Connect (OSTI)

Assessments for evaluating compliance with airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAPs - U.S. Code of Federal Regulations, Title 40 Part 61, Subparts H and I) were performed for 33 buildings at the U.S. Department of Energy`s (DOE) Pacific Northwest Laboratory on the Hanford Site, and for five buildings owned and operated by Battelle, Pacific Northwest Laboratories in Richland, Washington. The assessments were performed using building radionuclide inventory data obtained in 1992 and 1993. Results of the assessments are summarized in Table S.1 for DOE-PNL buildings and in Table S.2 for Battelle-owned buildings. Based on the radionuclide inventory assessments, four DOE-PNL buildings (one with two emission points) require continuous sampling for radionuclides per 40 CFR 61. None of the Battelle-owned buildings require continuous emission sampling.

Sula, M.J.; Jette, S.J.

1994-09-01T23:59:59.000Z

235

Use of the UNCLE Facility to Assess Integrated Online Monitoring Systems for Detection of Diversions at Uranium Conversion Facilities  

SciTech Connect (OSTI)

Historically, the approach to safeguarding nuclear material in the front end of the fuel cycle was implemented only at the stage when UF6 was declared as feedstock for enrichment plants. Recent International Atomic Energy Agency (IAEA) circulars and policy papers have sought to implement safeguards when any purified aqueous uranium solution or uranium oxides suitable for isotopic enrichment or fuel fabrication exist. Oak Ridge National Laboratory has developed the Uranyl Nitrate Calibration Loop Equipment (UNCLE) facility to simulate the full-scale operating conditions for a purified uranium-bearing aqueous stream exiting the solvent extraction process conducted in a natural uranium conversion plant (NUCP) operating at 6000 MTU/year. Monitoring instruments, including the 3He passive neutron detector developed at Los Alamos National Laboratory and the Endress+Hauser Promass 83F Coriolis meter, have been tested at UNCLE and field tested at Springfields. The field trials demonstrated the need to perform full-scale equipment testing under controlled conditions prior to field deployment of operations and safeguards monitoring at additional plants. Currently, UNCLE is testing neutron-based monitoring for detection of noncompliant activities; however, gamma-ray source term monitoring is currently being explored complementary to the neutron detector in order to detect undeclared activities in a more timely manner. The preliminary results of gamma-ray source term modeling and monitoring at UNCLE are being analyzed as part of a comprehensive source term and detector benchmarking effort. Based on neutron source term detection capabilities, alternative gamma-based detection and monitoring methods will be proposed to more effectively monitor NUCP operations in verifying or detecting deviations from declared conversion activities.

Dewji, Shaheen A [ORNL; Chapman, Jeffrey Allen [ORNL; Lee, Denise L [ORNL; Rauch, Eric [Los Alamos National Laboratory (LANL); Hertel, Nolan [Georgia Institute of Technology

2011-01-01T23:59:59.000Z

236

Radionuclide release rates from spent fuel for performance assessment modeling  

SciTech Connect (OSTI)

In a scenario of aqueous transport from a high-level radioactive waste repository, the concentration of radionuclides in water in contact with the waste constitutes the source term for transport models, and as such represents a fundamental component of all performance assessment models. Many laboratory experiments have been done to characterize release rates and understand processes influencing radionuclide release rates from irradiated nuclear fuel. Natural analogues of these waste forms have been studied to obtain information regarding the long-term stability of potential waste forms in complex natural systems. This information from diverse sources must be brought together to develop and defend methods used to define source terms for performance assessment models. In this manuscript examples of measures of radionuclide release rates from spent nuclear fuel or analogues of nuclear fuel are presented. Each example represents a very different approach to obtaining a numerical measure and each has its limitations. There is no way to obtain an unambiguous measure of this or any parameter used in performance assessment codes for evaluating the effects of processes operative over many millennia. The examples are intended to suggest by example that in the absence of the ability to evaluate accuracy and precision, consistency of a broadly based set of data can be used as circumstantial evidence to defend the choice of parameters used in performance assessments.

Curtis, D.B.

1994-11-01T23:59:59.000Z

237

Historical Background on Assessment the Performance of the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the US Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a research and development facility for the safe management, storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and 25 years after site selection, the US Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance assessment conducted in 1996. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This report provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project. For example, the federal requirement to provide environmental impact statements and negotiated agreements with the State of New Mexico influenced the type of scientific areas that were investigated and the engineering analysis prior to 1989 for the WIPP.

Rechard, R.P.

1999-06-01T23:59:59.000Z

238

Performance of High-Convergence, Layered DT Implosions with Extended-Duration Pulses at the National Ignition Facility  

E-Print Network [OSTI]

Radiation-driven, low-adiabat, cryogenic DT layered plastic capsule implosions were carried out on the National Ignition Facility (NIF) to study the sensitivity of performance to peak power and drive duration. An implosion ...

Gatu Johnson, Maria

239

OVERVIEW OF THE U.S. DEPARTMENT OF ENERGY AND NUCLEAR REGULATORY COMMISSION PERFORMANCE ASSESSMENT APPROACHES: CEMENTITIOUS BARRIERS PARTNERSHIP  

SciTech Connect (OSTI)

Engineered barriers including cementitious barriers are used at sites disposing or contaminated with low-level radioactive waste to enhance performance of the natural environment with respect to controlling the potential spread of contaminants. Drivers for using cementitious barriers include: high radionuclide inventory, radionuclide characteristics (e.g., long half-live, high mobility due to chemical form/speciation, waste matrix properties, shallow water table, and humid climate that provides water for leaching the waste). This document comprises the first in a series of reports being prepared for the Cementitious Barriers Partnership. The document is divided into two parts which provide a summary of: (1) existing experience in the assessment of performance of cementitious materials used for radioactive waste management and disposal and (2) sensitivity and uncertainty analysis approaches that have been applied for assessments. Each chapter is organized into five parts: Introduction, Regulatory Considerations, Specific Examples, Summary of Modeling Approaches and Conclusions and Needs. The objective of the report is to provide perspective on the state of the practice for conducting assessments for facilities involving cementitious barriers and to identify opportunities for improvements to the existing approaches. Examples are provided in two contexts: (1) performance assessments conducted for waste disposal facilities and (2) performance assessment-like analyses (e.g., risk assessments) conducted under other regulatory regimes. The introductory sections of each section provide a perspective on the purpose of performance assessments and different roles of cementitious materials for radioactive waste management. Significant experience with assessments of cementitious materials associated with radioactive waste disposal concepts exists in the US Department of Energy Complex and the commercial nuclear sector. Recently, the desire to close legacy facilities has created a need to assess the behavior of cementitious materials for applications in environmental remediation and decontamination and decommissioning (D&D) applications. The ability to assess the use and benefits of cementitious materials for these applications can significantly affect decisions related to cleanup activities. For example the need for costly remedial actions may not be necessary if existing or new cementitious barriers were adequately represented. The sections dealing with regulatory considerations include summaries of the different regulations that are relevant for various applications involving cementitious materials. A summary of regulatory guidance and/or policies pertaining to performance assessment of cementitious materials and sensitivity and uncertainty analyses is also provided in the following chapters. Numerous examples of specific applications are provided in each report. The examples are organized into traditional waste disposal applications (performance assessments), applications related to environmental remediation and D&D, and reactor and spent fuel related assessments. Sections that discuss specific facilities or sites contain: (1) descriptions of the role of the cementitious barriers or sensitivity/uncertainty analysis, (2) parameter assumptions and conceptual models, and (3) a relative discussion of the significance in the context of the assessment. Examples from both the U.S. Department of Energy Sites and the U.S. Nuclear Regulatory Commission are provided to illustrate the variety of applications and approaches that have been used. In many cases, minimal credit was taken for cementitious barriers. However, in some of those cases, benefits of being able to take credit for barriers were identified. The examples included: (1) disposal facilities (vaults, trenches, tank closures, cementitious waste forms and containers, etc.), (2) environmental remediation (old disposal facilities), (3) reactor and large structure decommissioning, and (4) spent fuel pools. These examples were selected to provide a perspective on the various ne

Langton, C.; Burns, H.

2009-05-29T23:59:59.000Z

240

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio). Volume 3. Characterization of the nature and magnitude of emissions. Draft report  

SciTech Connect (OSTI)

This report constitutes a comprehensive site-specific risk assessment for the WTI incineration facility located in East Liverpool, OH. Volume III of the report describes the methods used to estimate both stack and fugitive emission rates from the facility.

NONE

1995-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Methodology for assessing performance of waste management systems  

SciTech Connect (OSTI)

The purpose of the methodology provided in this report is to select the optimal way to manage particular sets of waste streams from generation to disposal in a safe and cost-effective manner. The methodology described is designed to review the entire waste management system, assess its performance, ensure that the performance objectives are met, compare different LLW management alternatives, and select the optimal alternative. The methodology is based on decision analysis approach, in which costs and risk are considered for various LLW management alternatives, a comparison of costs, risks, and benefits is made, and an optimal system is selected which minimizes costs and risks and maximizes benefits. A ''zoom-lens'' approach is suggested, i.e., one begins by looking at gross features and gradually proceeds to more and more detail. Performance assessment requires certain information about the characteristics of the waste streams and about the various components of the waste management system. Waste acceptance criteria must be known for each component of the waste management system. Performance assessment for each component requires data about properties of the waste streams and operational and design characteristics of the processing or disposal components. 34 refs., 2 figs., 1 tab.

Meshkov, N.K.; Herzenberg, C.L.; Camasta, S.F.

1988-01-01T23:59:59.000Z

242

Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky  

SciTech Connect (OSTI)

DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

NONE

1994-06-01T23:59:59.000Z

243

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

244

Monitored retrievable storage submission to Congress: Volume 2, Environmental assessment for a monitored retrievable storage facility. [Contains glossary  

SciTech Connect (OSTI)

This Environmental Assessment (EA) supports the DOE proposal to Congress to construct and operate a facility for monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portion of Oak Ridge, Tennessee. The first part of this document is an assessment of the value of, need for, and feasibility of an MRS facility as an integral component of the waste management system. The second part is an assessment and comparison of the potential environmental impacts projected for each of six site-design combinations. The MRS facility would be centrally located with respect to existing reactors, and would receive and canister spent fuel in preparation for shipment to and disposal in a geologic repository. 207 refs., 57 figs., 132 tabs.

none,

1986-02-01T23:59:59.000Z

245

Management Challenges in Developing Performance Assessments and Effectively Communicating Their Results - 13612  

SciTech Connect (OSTI)

The end of the Cold War has left a legacy of approximately 37 million gallons of radioactive waste in the aging waste tanks at the Department of Energy's Savannah River Site (SRS). A robust program is in place to remove waste from these tanks, treat the waste to separate into a relatively small volume of high level waste and a large volume of low-level waste, and to actively dispose of the low-level waste on-site and close the cleaned waste tanks and associated ancillary structures. To support performance-based, risk-informed decision making, performance assessments have been developed for the low-level waste disposal facility and for the SRS Tank Farms. Although these performance assessments share many similar features, the nature of the hazards and associated containments differ. As a management team, we are challenged to effectively communicate both the similarities and differences of these performance assessments, how they should be used to support sound decision making for treatment, disposal and waste tank cleaning decisions, and in defending their respective assumptions to the regulatory community and the public but, equally important, to our own corporate decision makers and operations personnel. Effective development and defense of these performance assessments, and effective interpretation and communication of the results are key to making cost-effective, pragmatic decisions for the safe disposal of the low-level waste and stabilization and operational closure of the cleaned tanks and associated structures. This paper will focus on the importance and challenges in communicating key attributes, conclusions and operational implications within a company. (authors)

Thomas, Steve; Mahoney, Mark [Savannah River Remediations LLC, Building 705-1C, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River Remediations LLC, Building 705-1C, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

246

Contractor Performance Assessment Reporting System (CPARS) | Department of  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTieCelebrate EarthEnergy Contractor Performance Assessment Reporting

247

Advanced Energy Retrofit Guide (AERG): Practical Ways to Improve Energy Performance; Healthcare Facilities (Book)  

SciTech Connect (OSTI)

The Advanced Energy Retrofit Guide for Healthcare Facilities is part of a series of retrofit guides commissioned by the U.S. Department of Energy. By presenting general project planning guidance as well as detailed descriptions and financial payback metrics for the most important and relevant energy efficiency measures (EEMs), the guides provide a practical roadmap for effectively planning and implementing performance improvements in existing buildings. The Advanced Energy Retrofit Guides (AERGs) are intended to address key segments of the U.S. commercial building stock: retail stores, office buildings, K-12 schools, grocery stores, and healthcare facilities. The guides' general project planning considerations are applicable nationwide; the energy and cost savings estimates for recommended EEMs were developed based on energy simulations and cost estimates for an example hospital tailored to five distinct climate regions. These results can be extrapolated to other U.S. climate zones. Analysis is presented for individual EEMs, and for packages of recommended EEMs for two project types: existing building commissioning projects that apply low-cost and no-cost measures, and whole-building retrofits involving more capital-intensive measures.

Hendron, R.; Leach, M.; Bonnema, E.; Shekhar, D.; Pless, S.

2013-09-01T23:59:59.000Z

248

Computational Fluid Dynamics Framework for Turbine Biological Performance Assessment  

SciTech Connect (OSTI)

In this paper, a method for turbine biological performance assessment is introduced to bridge the gap between field and laboratory studies on fish injury and turbine design. Using this method, a suite of biological performance indicators is computed based on simulated data from a computational fluid dynamics (CFD) model of a proposed turbine design. Each performance indicator is a measure of the probability of exposure to a certain dose of an injury mechanism. If the relationship between the dose of an injury mechanism and frequency of injury (dose-response) is known from laboratory or field studies, the likelihood of fish injury for a turbine design can be computed from the performance indicator. By comparing the values of the indicators from various turbine designs, the engineer can identify the more-promising designs. Discussion here is focused on Kaplan-type turbines, although the method could be extended to other designs. Following the description of the general methodology, we will present sample risk assessment calculations based on CFD data from a model of the John Day Dam on the Columbia River in the USA.

Richmond, Marshall C.; Serkowski, John A.; Carlson, Thomas J.; Ebner, Laurie L.; Sick, Mirjam; Cada, G. F.

2011-05-04T23:59:59.000Z

249

Performance assessment methodology and preliminary results for low-level radioactive waste disposal in Taiwan.  

SciTech Connect (OSTI)

Sandia National Laboratories (SNL) and Taiwan's Institute for Nuclear Energy Research (INER) have teamed together to evaluate several candidate sites for Low-Level Radioactive Waste (LLW) disposal in Taiwan. Taiwan currently has three nuclear power plants, with another under construction. Taiwan also has a research reactor, as well as medical and industrial wastes to contend with. Eventually the reactors will be decomissioned. Operational and decommissioning wastes will need to be disposed in a licensed disposal facility starting in 2014. Taiwan has adopted regulations similar to the US Nuclear Regulatory Commission's (NRC's) low-level radioactive waste rules (10 CFR 61) to govern the disposal of LLW. Taiwan has proposed several potential sites for the final disposal of LLW that is now in temporary storage on Lanyu Island and on-site at operating nuclear power plants, and for waste generated in the future through 2045. The planned final disposal facility will have a capacity of approximately 966,000 55-gallon drums. Taiwan is in the process of evaluating the best candidate site to pursue for licensing. Among these proposed sites there are basically two disposal concepts: shallow land burial and cavern disposal. A representative potential site for shallow land burial is located on a small island in the Taiwan Strait with basalt bedrock and interbedded sedimentary rocks. An engineered cover system would be constructed to limit infiltration for shallow land burial. A representative potential site for cavern disposal is located along the southeastern coast of Taiwan in a tunnel system that would be about 500 to 800 m below the surface. Bedrock at this site consists of argillite and meta-sedimentary rocks. Performance assessment analyses will be performed to evaluate future performance of the facility and the potential dose/risk to exposed populations. Preliminary performance assessment analyses will be used in the site-selection process and to aid in design of the disposal system. Final performance assessment analyses will be used in the regulatory process of licensing a site. The SNL/INER team has developed a performance assessment methodology that is used to simulate processes associated with the potential release of radionuclides to evaluate these sites. The following software codes are utilized in the performance assessment methodology: GoldSim (to implement a probabilistic analysis that will explicitly address uncertainties); the NRC's Breach, Leach, and Transport - Multiple Species (BLT-MS) code (to simulate waste-container degradation, waste-form leaching, and transport through the host rock); the Finite Element Heat and Mass Transfer code (FEHM) (to simulate groundwater flow and estimate flow velocities); the Hydrologic Evaluation of Landfill performance Model (HELP) code (to evaluate infiltration through the disposal cover); the AMBER code (to evaluate human health exposures); and the NRC's Disposal Unit Source Term -- Multiple Species (DUST-MS) code (to screen applicable radionuclides). Preliminary results of the evaluations of the two disposal concept sites are presented.

Arnold, Bill Walter; Chang, Fu-lin (Institute of Nuclear Energy Research, Taiwan); Mattie, Patrick D.; Knowlton, Robert G.; Chuang, W-S (Institute of Nuclear Energy Research, Taiwan); Chi, L-M (Institute of Nuclear Energy Research, Taiwan); Jow, Hong-Nian; Tien, Norman C. (Institute of Nuclear Energy Research, Taiwan); Ho, Clifford Kuofei

2006-02-01T23:59:59.000Z

250

An assessment of the quality and educational adequacy of educational facilities and their perceived impact on the learning environment as reported by middle school administrators and teachers in Humble Independent School District, Humble, Texas  

E-Print Network [OSTI]

an assessment of the impact that these facilities have on the learning environment. This study also assesses the quality and adequacy of these middle school facilities through a purely quantitative evaluation conducted by an unbiased assessment team. Humble ISD...

Monk, Douglas Matthew

2007-04-25T23:59:59.000Z

251

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio). Volume 2. Introduction. Draft report  

SciTech Connect (OSTI)

This volume provides a description of the facility, and its location and setting in the three-state area of Ohio, Pennsylvania, and West Virginia; an overview of previous risk assessments conducted by U.S. EPA for this site, including the preliminary assessment of inhalation exposure and the screening-level risk analyses of indirect exposure; and a summary of comments provided by the Peer Review Panel on the Project Plan.

NONE

1995-11-01T23:59:59.000Z

252

An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities  

SciTech Connect (OSTI)

Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000’s of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose during the 1) institutional control period (0-100 years), compliance period (0-1000 years) and post-compliance period (>1000 years). Evaluation of the all pathway dose included the dose from ingestion and irrigation of contaminated groundwater extracted from a well 100 meters downgradient, in addition to the dose received from direct contact of radionuclides deposited near the surface resulting from facility overflow. Depending on the disposal facility radionuclide inventory, facility design, cover performance, and the location and environment where the facility is situated, the dose from exposure via direct contact of near surface deposited radionuclides can be much greater than the dose received via transport to the groundwater and subsequent ingestion.

Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

2011-03-01T23:59:59.000Z

253

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14  

SciTech Connect (OSTI)

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

Schneider, K.J.

1982-09-01T23:59:59.000Z

254

The SECO suite of codes for site Performance Assessment  

SciTech Connect (OSTI)

Modeling for Performance Assessment of the Waste Isolation Pilot Plant (WIPP ) has led to development of the SECO suite of codes for groundwater flow, particle tracking, and transport. Algorithm and code developments include the following areas: facilitation of grid convergence tests in multiple domains; correct treatment of transmissivity factors for unconfined aquifers; efficient multigrid algorithms; a formulation of brine Darcy flow equations that uses freshwater head as the dependent able; boundary-fitted coordinates; temporal high order particle tracking; an efficient and accurate implicit Finite Volume TVD algorithm for radionuclide transport in (possibly) fractured porous media; accurate calculation of advection via a flux-based modified method of characteristics; and Quality Assurance procedures.

Roache, P.J. [Ecodynamics Research Associates, Inc., Albuquerque, NM (United States)

1993-03-01T23:59:59.000Z

255

Strategy for experimental validation of waste package performance assessment  

SciTech Connect (OSTI)

A strategy for the experimental validation of waste package performance assessment has been developed as part of a program supported by the Repository Technology Program. The strategy was developed by reviewing the results of laboratory analog experiments, in-situ tests, repository simulation tests, and material interaction tests. As a result of the review, a listing of dependent and independent variables that influence the ingress of water into the near-field environment, the reaction between water and the waste form, and the transport of radionuclides from the near-field environment was developed. The variables necessary to incorporate into an experimental validation strategy were chosen by identifying those which had the greatest effect of each of the three major events, i.e., groundwater ingress, waste package reactions, and radionuclide transport. The methodology to perform validation experiments was examined by utilizing an existing laboratory analog approach developed for unsaturated testing of glass waste forms. 185 refs., 9 figs., 2 tabs.

Bates, J.K.; Abrajano, T.A. Jr.; Wronkiewicz, D.J.; Gerding, T.J.; Seils, C.A.

1990-07-01T23:59:59.000Z

256

Confined Spaces Assessment Plan - Developed By NNSA/Nevada Site...  

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

CONFINED SPACES Assessment Plan NNSANevada Site Office Facility Representative Division Performance Objective: This assessment provides a basis for evaluating the safety...

257

PORFLOW MODELING FOR A PRELIMINARY ASSESSMENT OF THE PERFORMANCE OF NEW SALTSTONE DISPOSAL UNIT DESIGNS  

SciTech Connect (OSTI)

At the request of Savannah River Remediation (SRR), SRNL has analyzed the expected performance obtained from using seven 32 million gallon Saltstone Disposal Units (SDUs) in the Z-Area Saltstone Disposal Facility (SDF) to store future saltstone grout. The analysis was based on preliminary SDU final design specifications. The analysis used PORFLOW modeling to calculate the release of 20 radionuclides from an SDU and transport of the radionuclides and daughters through the vadose zone. Results from this vadose zone analysis were combined with previously calculated releases from existing saltstone vaults and FDCs and a second PORFLOW model run to calculate aquifer transport to assessment points located along a boundary 100 m from the nearest edge of the SDF sources. Peak concentrations within 12 sectors spaced along the 100 m boundary were determined over a period of evaluation extending 20,000 years after SDF closure cap placement. These peak concentrations were provided to SRR to use as input for dose calculations.

Smith, F.

2012-08-06T23:59:59.000Z

258

THE PENA BLANCA NATURAL ANALOGUE PERFORMANCE ASSESSMENT MODEL  

SciTech Connect (OSTI)

The Nopal I uranium mine in the Sierra Pena Blanca, Chihuahua, Mexico serves as a natural analogue to the Yucca Mountain repository. The Pena Blanca Natural Analogue Performance Assessment Model simulates the mobilization and transport of radionuclides that are released from the mine and transported to the saturated zone. The Pena Blanca Natural Analogue Performance Assessment Model uses probabilistic simulations of hydrogeologic processes that are analogous to the processes that occur at the Yucca Mountain site. The Nopal I uranium deposit lies in fractured, welded, and altered rhyolitic ash-flow tuffs that overlie carbonate rocks, a setting analogous to the geologic formations at the Yucca Mountain site. The Nopal I mine site has the following analogous characteristics as compared to the Yucca Mountain repository site: (1) Analogous source--UO{sub 2} uranium ore deposit = spent nuclear fuel in the repository; (2) Analogous geology--(i.e. fractured, welded, and altered rhyolitic ash-flow tuffs); (3) Analogous climate--Semiarid to arid; (4) Analogous setting--Volcanic tuffs overlie carbonate rocks; and (5) Analogous geochemistry--Oxidizing conditions Analogous hydrogeology: The ore deposit lies in the unsaturated zone above the water table.

G. Saulnier and W. Statham

2006-04-16T23:59:59.000Z

259

Data-Based Performance Assessments for the DOE Hydropower Advancement Project  

SciTech Connect (OSTI)

The U. S. Department of Energy s Hydropower Advancement Project (HAP) was initiated to characterize and trend hydropower asset conditions across the U.S.A. s existing hydropower fleet and to identify and evaluate the upgrading opportunities. Although HAP includes both detailed performance assessments and condition assessments of existing hydropower plants, this paper focuses on the performance assessments. Plant performance assessments provide a set of statistics and indices that characterize the historical extent to which each plant has converted the potential energy at a site into electrical energy for the power system. The performance metrics enable benchmarking and trending of performance across many projects in a variety contexts (e.g., river systems, power systems, and water availability). During FY2011 and FY2012, assessments will be performed on ten plants, with an additional fifty plants scheduled for FY2013. This paper focuses on the performance assessments completed to date, details the performance assessment process, and describes results from the performance assessments.

March, Patrick [Hydro Performance Processes, Inc.] [Hydro Performance Processes, Inc.; Wolff, Dr. Paul [WolffWare Ltd.] [WolffWare Ltd.; Smith, Brennan T [ORNL] [ORNL; Zhang, Qin Fen [ORNL] [ORNL; Dham, Rajesh [U.S. Department of Energy] [U.S. Department of Energy

2012-01-01T23:59:59.000Z

260

Performance Improvements to the Neutron Imaging System at the National Ignition Facility  

SciTech Connect (OSTI)

A team headed by LANL and including many members from LLNL and NSTec LO and NSTec LAO fielded a neutron imaging system (NIS) at the National Ignition Facility at the start of 2011. The NIS consists of a pinhole array that is located 32.5 cm from the source and that creates an image of the source in a segmented scintillator 28 m from the source. The scintillator is viewed by two gated, optical imaging systems: one that is fiber coupled, and one that is lens coupled. While there are a number of other pieces to the system related to pinhole alignment, collimation, shielding and data acquisition, those pieces are discussed elsewhere and are not relevant here. The system is operational and has successfully obtained data on more that ten imaging shots. This remainder of this whitepaper is divided in five main sections. In Section II, we identify three critical areas of improvement that we believe should be pursued to improve the performance of the system for future experiments: spatial resolution, temporal response and signal-to-noise ratio. In Section III, we discuss technologies that could be used to improve these critical performance areas. In Section IV, we describe a path to evolve the current system to achieve improved performance with minimal impact on the ability of the system to operate on shots. In Section V, we discuss the abilities, scope and timescales of the current teams and the Commissariat energie atomique (CEA). In Section VI, we summarize and make specific recommendations for collaboration on improvements to the NIS.

Fittinghoff, D N; Bower, D E; Drury, O B; Dzenitis, J M; Hatarik, R; Merrill, F E; Grim, G P; Wilde, C H; Wilson, D C; Landoas, O; Caillaud, T; Bourgade, J; Buckles, R A; Lee, J; Weiss, P B

2011-09-26T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Data-assessment reports for CEMS (continuous emission monitoring systems) at Subpart DA facilities  

SciTech Connect (OSTI)

EPA promulgated minimum quality assurance (QA) requirements for Continuous Emission Monitoring Systems (CEMS) in 40 CFR Part 60 Appendix F. Appendix F requires the development of site-specific QA plans and the reporting of results of EPA specified QA activities each calendar quarter. The report of QA activities under Appendix F is called a Data Assessment Report (DAR). The DAR includes identifying and descriptive information for the CEMS, results of periodic audits, identification of periods when calibration drift exceeds specified criteria, identification of periods when the analyzers or CEMS are out of control (OOC), and descriptions of corrective actions in response to OOC conditions. The principal objective of the study is an evaluation of the information in DARs for the first and second quarters of calendar year 1988. Secondary study objectives include the establishment of contacts with agency staff who normally receive the DARs each quarter and identification of facilities for which DARs were apparently not received, for follow-up by the appropriate agency.

Walsh, G.

1989-03-01T23:59:59.000Z

262

Environmental Assessment for the construction and operation of the Health Physics Site Support Facility on the Savannah River Site  

SciTech Connect (OSTI)

DOE has prepared an environmental assessment for the proposed construction and operation of the Health Physics Site Support Facility on the Savannah River Site. This (new) facility would meet requirements of the site radiological protection program and would ensure site compliance with regulations. It was determined that the proposed action is not a major Federal action significantly affecting the quality of the environment within the meaning of NEPA. Therefore, a finding of no significant impact is made, and no environmental impact statement is needed.

NONE

1995-07-01T23:59:59.000Z

263

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio). Volume 7. Accident analysis: Selection and assessment of potential release scenarios. Draft report  

SciTech Connect (OSTI)

This report constitutes a comprehensive site-specific risk assessment for the WTI incineration facility located in East Liverpool, OH. The Accident Analysis is an evaluation of the likelihood of occurrence and resulting consequences from several general classes of accidents that could potentially occur during operation of the facility. The Accident Analysis also evaluates the effectiveness of existing mitigation measures in reducing off-site impacts. Volume VII describes in detail the methods used to conduct the Accident Analysis and reports the results of evaluations of likelihood and consequence for the selected accident scenarios.

NONE

1995-11-01T23:59:59.000Z

264

3Q CY2000 (PDF), Facility Representative Program Performance Indicators Quarterly Report  

Broader source: Energy.gov [DOE]

The Facility Representative Program Indicators (Pis) Quarterly Report attached, covering the period from July to September 2000. Data for these indicators are gathered by the Field elements...

265

Design Tools to Assess Hydro-Turbine Biological Performance: Priest Rapids Dam Turbine Replacement Project  

SciTech Connect (OSTI)

Over the past two decades, there have been many studies describing injury mechanisms associated with turbine passage, the response of various fish species to these mechanisms, and the probability of survival through dams. Although developing tools to design turbines that improve passage survival has been difficult and slow, a more robust quantification of the turbine environment has emerged through integrating physical model data, fish survival data, and computational fluid dynamics (CFD) studies. Grant County Public Utility District (GCPUD) operates the Priest Rapids Dam (PRD), a hydroelectric facility on the Columbia River in Washington State. The dam contains 10 Kaplan-type turbine units that are now almost 50 years old. The Utility District plans to refit all of these aging turbines with new turbines. The Columbia River at PRD is a migratory pathway for several species of juvenile and adult salmonids, so passage of fish through the dam is a major consideration when replacing the turbines. In this presentation, a method for turbine biological performance assessment (BioPA) is introduced. Using this method, a suite of biological performance indicators is computed based on simulated data from a CFD model of a proposed turbine design. Each performance indicator is a measure of the probability of exposure to a certain dose of an injury mechanism. Using known relationships between the dose of an injury mechanism and frequency of injury (dose–response) from laboratory or field studies, the likelihood of fish injury for a turbine design can be computed from the performance indicator. By comparing the values of the indicators from proposed designs, the engineer can identify the more-promising alternatives. We will present application of the BioPA method for baseline risk assessment calculations for the existing Kaplan turbines at PRD that will be used as the minimum biological performance that a proposed new design must achieve.

Richmond, Marshall C.; Rakowski, Cynthia L.; Serkowski, John A.; Strickler, Brad; Weisbeck, Molly; Dotson, Curtis L.

2013-06-25T23:59:59.000Z

266

Performance Assessment for e-Government Services: An Experience Report  

SciTech Connect (OSTI)

The transformation and integration of government services, enabled by the use of new technologies such as application servers and Web services, is fundamental to reduce the cost of government and improving service outcomes to citizens. Many core Government information systems comprise applications running on legacy mainframes, databases and transaction processing monitors. As Governments worldwide provide direct access over the Internet to these legacy applications from the general public, they may be exposed to workloads well above the origin design parameters of these back-end systems. This creates a significant risk of high profile failures for Government agencies whose newly integrated systems become overloaded. In this paper we describe how we conducted a performance assessment of a business-critical, Internet-facing Web services that integrated new and legacy systems from two Australian Government agencies. We leveraged prototype tools from our own research along with known techniques in performance modeling. We were able to clearly demonstrate that the existing hardware and software would be adequate to handle the predicted workload for the next financial year. We were also able to do ‘what-if’ analysis and predict how the system can perform with alternative strategies to scale the system. We conclude by summarizing the lessons learnt, including the importance of architecture visibility, benchmarking data quality, and measurement feasibility due to issues of outsourcing, privacy legislation and cross-agency involvement.

Liu, Yan; Zhu, Liming; Gorton, Ian

2007-08-14T23:59:59.000Z

267

A Bulk Tungsten Tile for JET: Derivation of Power-Handling Performance and Validation of the Thermal Model, in the MARION Facility  

E-Print Network [OSTI]

A Bulk Tungsten Tile for JET: Derivation of Power-Handling Performance and Validation of the Thermal Model, in the MARION Facility

268

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility  

SciTech Connect (OSTI)

The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique.

Dionne, B.J.; Morris, S. III; Baum, J.W. [and others

1998-03-01T23:59:59.000Z

269

324 Facility special-case waste assessment in support of 324 closure (TPA milestone M-89-05)  

SciTech Connect (OSTI)

Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement Milestone M-89-05, requires US Department of Energy, Richland Operations Office to complete a 324 Facility Special-Case Waste Assessment in Support of 324 Closure. This document, HNF-1270, has been prepared with the intent of meeting this regulatory commitment. Alternatives for the special-case wastes located in the 324 Building were defined and analyzed. Based on the criteria of safety, environmental, complexity of interfaces, risk, cost, schedule, and long-term operability and maintainability, the best alternative was chosen. Waste packaging and transportation options are also included in the recommendations. The waste disposition recommendations for the B-Cell dispersibles/tank heels and High-Level Vault packaged residuals are to direct them to the Plutonium Uranium Extraction Facility (PUREX) Number 2 storage tunnel.

Hobart, R.L.

1998-06-25T23:59:59.000Z

270

Use of international data sets to evaluate and validate pathway assessment models applicable to exposure and dose reconstruction at DOE facilities. Progress report, August 1993--January 1994  

SciTech Connect (OSTI)

This project, ``Use of International Data Sets to Evaluate and Validate Pathway Assessment Models Applicable to Exposure and Dose Reconstruction at DOE Facilities,`` grew out of several activities being conducted by the Principal Investigator Dr. F Owen Hoffman. One activity was originally part of the Chernobyl Studies Project and began as Task 7.1D, ``Internal Dose From Direct Contamination of Terrestrial Food Sources.`` The objective of Task 7.1D was to (1) establish a collaborative US USSR effort to improve and validate our methods of forecasting doses and dose commitments from the direct contamination of food sources, and (2) perform experiments and validation studies to improve our ability to predict rapidly and accurately the long-term internal dose from the contamination of agricultural soil. The latter was to include the consideration of remedial measures to block contamination of food grown on contaminated soil. The current objective of this project is to evaluate and validate pathway-assessment models applicable to exposure and dose reconstruction at DOE facilities through use of international data sets. This project incorporates the activity of Task 7.1D into a multinational effort to evaluate data used for the prediction of radionuclide transfer through agricultural and aquatic systems to humans. It also includes participation in two multinational studies, BIOMOVS (BIOspheric MOdel Validation Study) with the Swedish National Institute for Radiation Protection and VAMP (VAlidation of Model Predictions) with the International Atomic Energy Agency, that address testing the performance of models of radionuclide transport through foodchains.

Hendrickson, S.M. [ed.] [Lawrence Livermore National Lab., CA (United States)] [ed.; Lawrence Livermore National Lab., CA (United States); Hoffman, F.O. [Senes Oak Ridge, Inc., TN (United States). Center for Risk Analysis] [Senes Oak Ridge, Inc., TN (United States). Center for Risk Analysis

1994-03-01T23:59:59.000Z

271

Lawrence Livermore National Laboratory Emergency Response Capability 2009 Baseline Needs Assessment Performance Assessment  

SciTech Connect (OSTI)

This document was prepared by John A. Sharry, LLNL Fire Marshal and Division Leader for Fire Protection and was reviewed by Sandia/CA Fire Marshal, Martin Gresho. This document is the second of a two-part analysis of Emergency Response Capabilities of Lawrence Livermore National Laboratory. The first part, 2009 Baseline Needs Assessment Requirements Document established the minimum performance criteria necessary to meet mandatory requirements. This second part analyses the performance of Lawrence Livermore Laboratory Emergency Management Department to the contents of the Requirements Document. The document was prepared based on an extensive review of information contained in the 2004 BNA, a review of Emergency Planning Hazards Assessments, a review of building construction, occupancy, fire protection features, dispatch records, LLNL alarm system records, fire department training records, and fire department policies and procedures. On October 1, 2007, LLNL contracted with the Alameda County Fire Department to provide emergency response services. The level of service called for in that contract is the same level of service as was provided by the LLNL Fire Department prior to that date. This Compliance Assessment will evaluate fire department services beginning October 1, 2008 as provided by the Alameda County Fire Department.

Sharry, J A

2009-12-30T23:59:59.000Z

272

Environmental assessment of oil degasification at four Strategic Petroleum Reserve facilities in Texas and Louisiana  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) proposes to treat gassy oil at four Strategic Petroleum Reserve (SPR) storage sites to lower the gas content of the stored crude oil and help ensure safe transfer of the oil during drawdown. The crude oil is stored underground in caverns created in salt domes. The degree of gassiness of the oil varies substantially among sites and among caverns within a site. This environmental assessment describes the proposed degasification operation, its alternatives, and potential environmental impacts. The need for degasification has arisen because over time, gases, principally methane and nitrogen, have migrated into and become dissolved in the stored crude oil. This influx of gas has raised the crude oil vapor pressure above limits required by safety and emission guidelines. When oil is drawn from the caverns, excess gases may come out of solution. Based on preliminary data from an ongoing sampling program, between 200 and 350 million of the 587 million barrels of crude oil stored at these four sites would require processing to remove excess gas. Degasification, a commonly used petroleum industry process, would be done at four crude oil storage facilities: Bryan Mound and Big Hill in Texas, and West Hackberry and Bayou Choctaw in Louisiana. DOE would use a turnkey services contract for engineering, procurement, fabrication, installation, operation and maintenance of two degasification plants. These would be installed initially at Bryan Mound and West Hackberry. Degasification would be complete in less than three years of continuous operations. This report summarizes the environmental impacts of this gasification process.

Not Available

1994-09-01T23:59:59.000Z

273

Barge loading facilities in conjunction with wood chipping and sawlog mill, Tennessee River Mile 145. 9R: Environmental assessment  

SciTech Connect (OSTI)

The purpose of this Environmental Assessment (EA) is to evaluate the environmental consequences of approving, denying, or adopting reasonable alternatives to a request for barge loading facilities. These facilities would serve a proposed wood chipping and sawlog products operation at Tennessee River Mile (TRM) 145.9, right descending bank, (Kentucky Lake), in Perry County, Tennessee. The site is located between Short Creek and Peters Landing. The applicant is Southeastern Forest Products, L.P. (SFP), Box 73, Linden, Tennessee and the proposed facilities would be constructed on or adjacent to company owned land. Portions of the barge terminal would be constructed on land over which flood easement rights are held by the United States of America and administered by the Tennessee Valley Authority (TVA). The US Army Corps of Engineers (CE) and TVA have regulatory control over the proposed barge terminal facilities since the action would involve construction in the Tennessee River which is a navigable water of the United States. The wood chipping and sawlog products facilities proposed on the upland property are not regulated by the CE or TVA. On the basis of the analysis which follows, it has been determined that a modified proposal (as described herein) would not significantly affect the quality of the human environment, and does not require the preparation of an environmental impact statement. 8 refs.

Not Available

1990-08-01T23:59:59.000Z

274

Enhanced Performance Assessment System (EPAS) for carbon sequestration.  

SciTech Connect (OSTI)

Carbon capture and sequestration (CCS) is an option to mitigate impacts of atmospheric carbon emission. Numerous factors are important in determining the overall effectiveness of long-term geologic storage of carbon, including leakage rates, volume of storage available, and system costs. Recent efforts have been made to apply an existing probabilistic performance assessment (PA) methodology developed for deep nuclear waste geologic repositories to evaluate the effectiveness of subsurface carbon storage (Viswanathan et al., 2008; Stauffer et al., 2009). However, to address the most pressing management, regulatory, and scientific concerns with subsurface carbon storage (CS), the existing PA methodology and tools must be enhanced and upgraded. For example, in the evaluation of a nuclear waste repository, a PA model is essentially a forward model that samples input parameters and runs multiple realizations to estimate future consequences and determine important parameters driving the system performance. In the CS evaluation, however, a PA model must be able to run both forward and inverse calculations to support optimization of CO{sub 2} injection and real-time site monitoring as an integral part of the system design and operation. The monitoring data must be continually fused into the PA model through model inversion and parameter estimation. Model calculations will in turn guide the design of optimal monitoring and carbon-injection strategies (e.g., in terms of monitoring techniques, locations, and time intervals). Under the support of Laboratory-Directed Research & Development (LDRD), a late-start LDRD project was initiated in June of Fiscal Year 2010 to explore the concept of an enhanced performance assessment system (EPAS) for carbon sequestration and storage. In spite of the tight time constraints, significant progress has been made on the project: (1) Following the general PA methodology, a preliminary Feature, Event, and Process (FEP) analysis was performed for a hypothetical CS system. Through this FEP analysis, relevant scenarios for CO{sub 2} release were defined. (2) A prototype of EPAS was developed by wrapping an existing multi-phase, multi-component reservoir simulator (TOUGH2) with an uncertainty quantification and optimization code (DAKOTA). (3) For demonstration, a probabilistic PA analysis was successfully performed for a hypothetical CS system based on an existing project in a brine-bearing sandstone. The work lays the foundation for the development of a new generation of PA tools for effective management of CS activities. At a top-level, the work supports energy security and climate change/adaptation by furthering the capability to effectively manage proposed carbon capture and sequestration activities (both research and development as well as operational), and it greatly enhances the technical capability to address this national problem. The next phase of the work will include (1) full capability demonstration of the EPAS, especially for data fusion, carbon storage system optimization, and process optimization of CO{sub 2} injection, and (2) application of the EPAS to actual carbon storage systems.

Wang, Yifeng; Sun, Amy Cha-Tien; McNeish, Jerry A. (Sandia National Laboratories, Livermore, CA); Dewers, Thomas A.; Hadgu, Teklu; Jove-Colon, Carlos F.

2010-09-01T23:59:59.000Z

275

SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY  

SciTech Connect (OSTI)

The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is dependent on the confidence that DOE has in the long term mission for T Plant, is proposed: (1) If the confidence level in a durable, extended T Plant mission independent of sludge storage is high, then the Sludge Treatment Project (STP) would continue to implement the path forward previously described in the Alternatives Report (HNF-39744). Risks to the sludge project can be minimized through the establishment of an Interface Control Document (ICD) defining agreed upon responsibilities for both the STP and T Plant Operations regarding the transfer and storage of sludge and ensuring that the T Plant upgrade and operational schedule is well integrated with the sludge storage activities. (2) If the confidence level in a durable, extended T Plant mission independent of sludge storage is uncertain, then the ASF conceptual design should be pursued on a parallel path with preparation of T Plant for sludge storage until those uncertainties are resolved. (3) Finally, if the confidence level in a durable, extended T Plant mission independent of sludge storage is low, then the ASF design should be selected to provide independence from the T Plant mission risk.

RUTHERFORD WW; GEUTHER WJ; STRANKMAN MR; CONRAD EA; RHOADARMER DD; BLACK DM; POTTMEYER JA

2009-04-29T23:59:59.000Z

276

Performance Assessment Monitoring Plan for the Hanford Site Low-Level Burial Grounds  

SciTech Connect (OSTI)

The U.S. Department of Energy Order 435.1, Radioactive Waste Management, requires a disposal authorization statement authorizing operation (or continued operation) for low-level waste disposal facilities. In fulfillment of these requirements, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area burial grounds and the 200 West Area burial grounds. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area low-level burial grounds be written and approved by the Richland Operations Office. As a result of a record of decision for the Hanford Site Solid Waste Program and acceptance of the Hanford Site Solid Waste Environmental Impact Statement, the use of the low-level burial ground (LLBG) as a disposal facility for low-level and mixed low-level wastes has been restricted to lined trenches and the Navy reactor-compartment trench only. Hence, as of July 2004, only the two lined trenches in burial ground 218-W-5 (trenches 31 and 34, see Appendix A) and the Navy reactor-compartment trench in burial ground 218 E 12B (trench 94) are allowed to receive waste. When the two lined trenches are filled, the LLBG will cease to operate except for reactor compartment disposal at trench 94. Remaining operational lifetime of the LLBG is dependent on waste volume disposal rates. Existing programs for air sampling and analyses and subsidence monitoring are currently adequate for performance assessment at the LLBG. The waste disposal authorization for the Hanford Site is based (in part) on the post-closure performance assessments for the LLBG. In order to maintain a useful link between operational monitoring (e.g., Resource Conservation and Recovery Act [RCRA], Comprehensive Environmental Response, Compensation, and Liability Act, and State Waste Discharge Permits), constituents, monitoring frequencies, and boundaries require regular review and comparison. The annual reports discussed here are the primary sources for these reviews. The pathways of interest are air and groundwater for both operational and post-closure conditions at the LLBG, with groundwater considered to be the most significant long-term exposure pathway. Constituents that contributed at least 0.1% of the total relative hazard were selected as target analytes for monitoring. These are technetium-99, uranium, and iodine-129. Because of its environmental unavailability, carbon 14 was removed from the list of constituents. Given the potential uncertainties in inventories at the 200 Area LLBG and the usefulness of tritium as a contaminant indicator, tritium will be monitored as a constituent of concern at all burial grounds. Preexisting contamination plumes in groundwater beneath low-level waste management areas are attributed to other past-practice liquid waste disposal sites. Groundwater and air will be sampled and analyzed for radiogenic components. Subsidence monitoring will also be performed on a regular basis. The existing near-facility and surveillance air monitoring programs are sufficient to satisfy the performance assessment monitoring. Groundwater monitoring will utilize the existing network of wells at the LLBG, and co-sampling with RCRA groundwater monitoring, to be sampled semiannually. Installation of additional wells is currently underway to replace wells that have gone dry.

None

2006-03-30T23:59:59.000Z

277

Literature Review and Assessment of Plant and Animal Transfer Factors Used in Performance Assessment Modeling  

SciTech Connect (OSTI)

A literature review and assessment was conducted by Pacific Northwest National Laboratory (PNNL) to update information on plant and animal radionuclide transfer factors used in performance-assessment modeling. A group of 15 radionuclides was included in this review and assessment. The review is composed of four main sections, not including the Introduction. Section 2.0 provides a review of the critically important issue of physicochemical speciation and geochemistry of the radionuclides in natural soil-water systems as it relates to the bioavailability of the radionuclides. Section 3.0 provides an updated review of the parameters of importance in the uptake of radionuclides by plants, including root uptake via the soil-groundwater system and foliar uptake due to overhead irrigation. Section 3.0 also provides a compilation of concentration ratios (CRs) for soil-to-plant uptake for the 15 selected radionuclides. Section 4.0 provides an updated review on radionuclide uptake data for animal products related to absorption, homeostatic control, approach to equilibration, chemical and physical form, diet, and age. Compiled transfer coefficients are provided for cow’s milk, sheep’s milk, goat’s milk, beef, goat meat, pork, poultry, and eggs. Section 5.0 discusses the use of transfer coefficients in soil, plant, and animal modeling using regulatory models for evaluating radioactive waste disposal or decommissioned sites. Each section makes specific suggestions for future research in its area.

Robertson, David E.; Cataldo, Dominic A.; Napier, Bruce A.; Krupka, Kenneth M.; Sasser, Lyle B.

2003-07-20T23:59:59.000Z

278

High Performance Lipoprotein Profiling for Cardiovascular Risk Assessment  

E-Print Network [OSTI]

With the severity of cardiovascular disease (CVD) and the related mortality rate to this disease, new methods are necessary for risk assessment and treatment prior to the onset of the disease. The current paradigm in CVD risk assessment has shifted...

Larner, Craig

2012-10-19T23:59:59.000Z

279

An assessment of alternatives and technologies for replacing ozone- depleting substances at DOE facilities  

SciTech Connect (OSTI)

Title VI of the Clean Air Act, as amended, mandates a production phase-out for ozone-depleting substances (ODSs). These requirements will have a significant impact on US Department of Energy (DOE) facilities. Currently, DOE uses ODSs in three major activities: fire suppression (halon), refrigeration and cooling (chlorofluorocarbons [CFCs]), and cleaning that requires solvents (CFCs, methyl chloroform, and carbon tetrachloride). This report provides basic information on methods and strategies to phase out use of ODSs at DOE facilities.

Purcell, C.W.; Miller, K.B.; Friedman, J.R.; Rapoport, R.D.; Conover, D.R.; Hendrickson, P.L. [Pacific Northwest Lab., Richland, WA (United States); Koss, T.C. [USDOE Assistant Secretary for Environment, Safety, and Health, Washington, DC (United States). Office of Environmental Guidance

1992-10-01T23:59:59.000Z

280

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio). Volume 1. Executive summary. Draft report  

SciTech Connect (OSTI)

This report constitutes a comprehensive site-specific risk assessment for the WTI incineration facility located in East Liverpool, OH. Volume I is a description of the components and methodologies used in the risk assessment and provides a summary of the major results from the three components of the assessment.

NONE

1995-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

The Groundwater Performance Assessment Project Quality Assurance Plan  

SciTech Connect (OSTI)

U.S. Department of Energy (DOE) has monitored groundwater on the Hanford Site since the 1940s to help determine what chemical and radiological contaminants have made their way into the groundwater. As regulatory requirements for monitoring increased in the 1980s, there began to be some overlap between various programs. DOE established the Groundwater Performance Assessment Project (groundwater project) in 1996 to ensure protection of the public and the environment while improving the efficiency of monitoring activities. The groundwater project is designed to support all groundwater monitoring needs at the site, eliminate redundant sampling and analysis, and establish a cost-effective hierarchy for groundwater monitoring activities. This document provides the quality assurance guidelines that will be followed by the groundwater project. This QA Plan is based on the QA requirements of DOE Order 414.1C, Quality Assurance, and 10 CFR 830, Subpart A--General Provisions/Quality Assurance Requirements as delineated in Pacific Northwest National Laboratory’s Standards-Based Management System. In addition, the groundwater project is subject to the Environmental Protection Agency (EPA) Requirements for Quality Assurance Project Plans (EPA/240/B-01/003, QA/R-5). The groundwater project has determined that the Hanford Analytical Services Quality Assurance Requirements Documents (HASQARD, DOE/RL-96-68) apply to portions of this project and to the subcontractors. HASQARD requirements are discussed within applicable sections of this plan.

Luttrell, Stuart P.

2006-05-11T23:59:59.000Z

282

Molecular Environmental Science: An Assessment of Research Accomplishments, Available Synchrotron Radiation Facilities, and Needs  

SciTech Connect (OSTI)

Synchrotron-based techniques are fundamental to research in ''Molecular Environmental Science'' (MES), an emerging field that involves molecular-level studies of chemical and biological processes affecting the speciation, properties, and behavior of contaminants, pollutants, and nutrients in the ecosphere. These techniques enable the study of aqueous solute complexes, poorly crystalline materials, solid-liquid interfaces, mineral-aqueous solution interactions, microbial biofilm-heavy metal interactions, heavy metal-plant interactions, complex material microstructures, and nanomaterials, all of which are important components or processes in the environment. Basic understanding of environmental materials and processes at the molecular scale is essential for risk assessment and management, and reduction of environmental pollutants at field, landscape, and global scales. One of the main purposes of this report is to illustrate the role of synchrotron radiation (SR)-based studies in environmental science and related fields and their impact on environmental problems of importance to society. A major driving force for MES research is the need to characterize, treat, and/or dispose of vast quantities of contaminated materials, including groundwater, sediments, and soils, and to process wastes, at an estimated cost exceeding 150 billion dollars through 2070. A major component of this problem derives from high-level nuclear waste. Other significant components come from mining and industrial wastes, atmospheric pollutants derived from fossil fuel consumption, agricultural pesticides and fertilizers, and the pollution problems associated with animal waste run-off, all of which have major impacts on human health and welfare. Addressing these problems requires the development of new characterization and processing technologies--efforts that require information on the chemical speciation of heavy metals, radionuclides, and xenobiotic organic compounds and their reactions with environmental materials. To achieve this goal, both fundamental and targeted studies of complex environmental systems at a molecular level are needed, and examples of both types of studies are presented herein. These examples illustrate the fact that MES SR studies have led to a revolution in our understanding of the fundamental physical and chemical aspects of natural systems. The MES SR user community has continued to experience strong growth at U.S. SR laboratories, with MES researchers comprising up to 15% of the total user base. Further growth and development of the MES community is being hindered by insufficient resources, including support personnel, materials preparation facilities, and available beam time at U.S. SR laboratories. ''EnviroSync'' recommends the following actions, in cooperation with U.S. SR laboratory directors, to meet the MES community's needs.

Brown, G

2004-02-05T23:59:59.000Z

283

Molecular environmental science : an assessment of research accomplishments, available synchrotron radiation facilities, and needs.  

SciTech Connect (OSTI)

Synchrotron-based techniques are fundamental to research in ''Molecular Environmental Science'' (MES), an emerging field that involves molecular-level studies of chemical and biological processes affecting the speciation, properties, and behavior of contaminants, pollutants, and nutrients in the ecosphere. These techniques enable the study of aqueous solute complexes, poorly crystalline materials, solid-liquid interfaces, mineral-aqueous solution interactions, microbial biofilm-heavy metal interactions, heavy metal-plant interactions, complex material microstructures, and nanomaterials, all of which are important components or processes in the environment. Basic understanding of environmental materials and processes at the molecular scale is essential for risk assessment and management, and reduction of environmental pollutants at field, landscape, and global scales. One of the main purposes of this report is to illustrate the role of synchrotron radiation (SR)-based studies in environmental science and related fields and their impact on environmental problems of importance to society. A major driving force for MES research is the need to characterize, treat, and/or dispose of vast quantities of contaminated materials, including groundwater, sediments, and soils, and to process wastes, at an estimated cost exceeding 150 billion dollars through 2070. A major component of this problem derives from high-level nuclear waste. Other significant components come from mining and industrial wastes, atmospheric pollutants derived from fossil fuel consumption, agricultural pesticides and fertilizers, and the pollution problems associated with animal waste run-off, all of which have major impacts on human health and welfare. Addressing these problems requires the development of new characterization and processing technologies--efforts that require information on the chemical speciation of heavy metals, radionuclides, and xenobiotic organic compounds and their reactions with environmental materials. To achieve this goal, both fundamental and targeted studies of complex environmental systems at a molecular level are needed, and examples of both types of studies are presented herein. These examples illustrate the fact that MES SR studies have led to a revolution in our understanding of the fundamental physical and chemical aspects of natural systems. The MES SR user community has continued to experience strong growth at U.S. SR laboratories, with MES researchers comprising up to 15% of the total user base. Further growth and development of the MES community is being hindered by insufficient resources, including support personnel, materials preparation facilities, and available beam time at U.S. SR laboratories. EnviroSync* recommends the following actions, in cooperation with U.S. SR laboratory directors, to meet the MES community's needs.

Brown, G. E., Jr.; Sutton, S. R.; Bargar, J. R.; Shuh, D. K.; Fenter, P. A.; Kemner, K. M.

2004-10-20T23:59:59.000Z

284

Conceptual structure of performance assessments conducted for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being developed by the US Department of Energy as a disposal facility for transuranic waste. In support of this project, Sandia National Laboratories is conducting an ongoing performance assessment (PA) for the WIPP. The ordered triple representation for risk proposed by Kaplan and Garrick is used to provide a clear conceptual structure for this PA. This presentation describes how the preceding representation provides a basis in the WIPP PA for (1) the definition of scenarios and the calculation of scenario probabilities and consequences, (2) the separation of subjective and stochastic uncertainties, (3) the construction of the complementary cumulative distribution functions required in comparisons with the US Environmental Protection Agency`s standard for the geologic disposal of radioactive waste (i.e., 40 CFR Part 191, Subpart B), and (4) the performance of uncertainty and sensitivity studies. Results obtained in a preliminary PA for the WIPP completed in December of 1991 are used for illustration.

Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Marietta, M.G.; Rechard, R.P. [Sandia National Labs., Albuquerque, NM (United States)

1993-04-01T23:59:59.000Z

285

Water resource opportunity assessment: Fort Dix  

SciTech Connect (OSTI)

This report provides the results of the water resource opportunity assessments performed by Pacific Northwest National Laboratory at the Fort Dix facility located in Fort Dix, New Jersey.

Sullivan, G.P.; Hostick, D.J.; Elliott, D.B.; Fitzpatrick, Q.K.; Dahowski, R.T.; Dison, D.R

1996-12-01T23:59:59.000Z

286

1991 Annual performance report for environmental oversight and monitoring at Department of Energy Facilities in New Mexico  

SciTech Connect (OSTI)

On October 22, 1990 an agreement was entered into between the US DOE and the State of New Mexico. The agreement was designed to assure the citizens of New Mexico that the environment is protected and that public health, as related to the environment is also protected. The Agreement reflects the understanding and commitments between the parties regarding environmental oversight, monitoring, remediation and emergency response at the following DOE facilities: the Inhalation Toxicology Research Institute (ITRI); Los Alamos National Laboratory (LANL); Sandia National Laboratory (SNL); and the Waste Isolation Pilot Plant (WIPP). These provision are ongoing through a vigorous program of independent monitoring and oversight; prioritization of clean-up and compliance activities; and new commitments by DOE. While the initial assessment of the quality and effectiveness of the facilities` environmental monitoring and surveillance programs is not yet complete, preliminary findings are presented regarding air quality monitoring, environmental monitoring, and groundwater monitoring.

Not Available

1994-05-01T23:59:59.000Z

287

Assessing the Costs and Benefits of the Superior Energy Performance...  

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

the Costs and Benefits of the Superior Energy Performance Program Presentation Nine companies certified under the U.S. Department of Energy (DOE) Superior Energy Performance...

288

The particpation and performance of students with emotional disturbance on state accountability assessment in reading  

E-Print Network [OSTI]

This study examined the participation rates and performance results of students with emotional disturbance (ED) in a statewide reading assessment. Public school districts in Texas use the Texas Assessment of Knowledge and Skills (TAKS) test...

Carr George, Catherine Elizabeth

2009-05-15T23:59:59.000Z

289

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2007  

SciTech Connect (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP – U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection – Air Emissions. In these NESHAP assessments, potential unabated offsite doses were evaluated for emission locations at buildings that are part of the consolidated laboratory campus of the Pacific Northwest National Laboratory. This report describes the inventory-based methods and provides the results for the NESHAP assessment performed in 2007.

Ballinger, Marcel Y.; Barfuss, Brad C.; Gervais, Todd L.

2008-01-01T23:59:59.000Z

290

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2010  

SciTech Connect (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants ([NESHAP]; U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code 246-247: Radiation Protection - Air Emissions. In these NESHAP assessments, potential unabated off-site doses were evaluated for emission locations at buildings that are part of the consolidated laboratory campus of the Pacific Northwest National Laboratory. This report describes the inventory-based methods and provides the results for the NESHAP assessment performed in 2010.

Ballinger, Marcel Y.; Gervais, Todd L.; Barnett, J. M.

2011-05-13T23:59:59.000Z

291

A Framework for Reliability and Performance Assessment of Wind Energy Conversion Systems  

E-Print Network [OSTI]

1 A Framework for Reliability and Performance Assessment of Wind Energy Conversion Systems proposes a framework for reliability and dynamic performance assessment of wind energy conversion systems--Reliability, Dynamic Performance, Wind Power, Wind Energy Conversion System (WECS), Doubly-Fed Induction Generator

Liberzon, Daniel

292

Assessment and Mitigation of Diagnostic-Generated Electromagnetic Interference at the National Ignition Facility  

SciTech Connect (OSTI)

Electromagnetic interference (EMI) is an ever-present challenge at laser facilities such as the National Ignition Facility (NIF). The major source of EMI at such facilities is laser-target interaction that can generate intense electromagnetic fields within, and outside of, the laser target chamber. In addition, the diagnostics themselves can be a source of EMI, even interfering with themselves. In this paper we describe EMI generated by ARIANE and DIXI, present measurements, and discuss effects of the diagnostic-generated EMI on ARIANE's CCD and on a PMT nearby DIXI. Finally we present some of the efforts we have made to mitigate the effects of diagnostic-generated EMI on NIF diagnostics.

Brown, C G; Ayers, M J; Felker, B; Ferguson, W; Holder, J P; Nagel, S R; Piston, K W; Simanovskaia, N; Throop, A L; Chung, M; Hilsabeck, T

2012-04-20T23:59:59.000Z

293

Environmental Assessment for decontaminating and decommissioning the General Atomics Hot Cell Facility. Final [report  

SciTech Connect (OSTI)

This EA evaluates the proposed action to decontaminate and decommission GA`s hot cell facility in northern San Diego, CA. This facility has been used for DOE and commercial nuclear R&D for > 30 years. About 30,000 cubic feet of decontamination debris and up to 50,000 cubic feet of contaminated soil are to be removed. Low-level radioactive waste would be shipped for disposal. It was determined that the proposal does not constitute a major federal action significantly affecting the human environment according to NEPA; therefore, a finding of no significant impact is made, and an environmental impact statement is not required.

NONE

1995-08-01T23:59:59.000Z

294

E-Print Network 3.0 - assessment performance assessment Sample...  

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

OF ENGINEERING CYBERNETICS AND ROBOTICS, 60 Summary: , 60 2009 Sofia Service Oriented Architecture of Assessment Model1 Adelina Aleksieva... Assessment Model. To achieve...

295

DISTORTIONS IN STATE LEVEL PERFORMANCE OUTCOMES ON HIGH STAKES ASSESSMENTS  

E-Print Network [OSTI]

effective focus on the state assessment, at the expense of the NAEP. The third scenario, both the state assessment and NAEP scores fall, with the NAEP scores falling faster indicates a state struggling to do anything well. The second research question...

Hornback, Joseph Edward

2013-05-31T23:59:59.000Z

296

Utah Department of Health Bureau of Health Facility Licensing, Certification and Resident Assessment  

E-Print Network [OSTI]

Utah Department of Health Bureau of Health Facility Licensing, Certification and Resident of Utah Rule R432-31 (http://health.utah.gov/hflcra/forms.php) This is a physician order sheet based be effectively managed at current setting. ___ Limited additional interventions: Includes care above. May also

Tipple, Brett

297

Operation of N Reactor and Fuels Fabrication Facilities, Hanford Reservation, Richland, Benton County, Washington: Environmental assessment  

SciTech Connect (OSTI)

Environmental data, calculations and analyses show no significant adverse radiological or nonradiological impacts from current or projected future operations resulting from N Reactor, Fuels Fabrication and Spent Fuel Storage Facilities. Nonoccupational radiation exposures resulting from 1978 N Reactor operations are summarized and compared to allowable exposure limits.

Not Available

1980-08-01T23:59:59.000Z

298

Advancing Performance Assessment for Disposal of Depleted Uranium at Clive Utah - 12493  

SciTech Connect (OSTI)

A Performance Assessment (PA) for disposal of depleted uranium (DU) waste has recently been completed for a potential disposal facility at Clive in northwestern Utah. For the purposes of this PA, 'DU waste' includes uranium oxides of all naturally-occurring isotopes, though depleted in U-235, varying quantities of other radionuclides introduced to the uranium enrichment process in the form of used nuclear reactor fuel (reactor returns), and decay products of all of these radionuclides. The PA will be used by the State of Utah to inform an approval decision for disposal of DU waste at the facility, and will be available to federal regulators as they revisit rulemaking for the disposal of DU. The specific performance objectives of the Clive DU PA relate to annual individual radiation dose within a 10,000-year performance period, groundwater concentrations of specific radionuclides within a 500-year compliance period, and site stability in the longer term. Fate and transport processes that underlie the PA model include radioactive decay and ingrowth, diffusion in gaseous and water phases, water advection in unsaturated and saturated zones, transport caused by plant and animal activity, cover naturalization, natural and anthropogenic erosion, and air dispersion. Fate and transport models were used to support the dose assessment and the evaluation of groundwater concentrations. Exposure assessment was based on site-specific scenarios, since the traditional human exposure scenarios suggested by DOE and NRC guidance are unrealistic for this site. Because the U-238 in DU waste reaches peak radioactivity (secular equilibrium) after 2 million years (My) following its separation, the PA must also evaluate the impact of climate change cycles, including the return of pluvial lakes such as Lake Bonneville. The first draft of the PA has been submitted to the State of Utah for review. The results of this preliminary analysis indicate that doses are very low for the site-specific receptors for the 10,000-year compliance period. This is primarily because DU waste is not highly radioactive within this time frame, the DU waste is assumed to be buried beneath zones exposed by erosion, groundwater concentrations of DU waste constituents do not exceed groundwater protection limits with in the 500-year compliance period, and the first deep lake occurrence will disperse DU waste across a large area, and will ultimately be covered by lake-derived sediment. A probabilistic PA model was constructed that considered DU waste and decay product doses to site-specific receptors for a 10,000-yr performance period, as well as deep-time effects. The quantitative results are summarized in Table VII. Doses (as TEDE) are always less than 5 mSv in a year, and doses to the offsite receptors are always much less than 0.25 mSv in a year. Groundwater concentrations of Tc-99 are always less than its GWPL except when the Tc-99 contaminated waste is disposed below grade. Even in this case, the median groundwater concentration is only 4.18 Bq/L (113 pCi/L), which is more than one order of magnitude less than the GWPL for Tc-99. The results overall suggest that there are disposal configurations that can be used to dispose of the proposed quantities of DU waste that are adequately protective of human health. (authors)

Black, Paul; Tauxe, John; Perona, Ralph; Lee, Robert; Catlett, Kate; Balshi, Mike; Fitzgerald, Mark; McDermott, Greg [Neptune and Company, Inc., Los Alamos, New Mexico 87544 (United States); Shrum, Dan; McCandless, Sean; Sobocinski, Robert; Rogers, Vern [EnergySolutions, LLC, Salt Lake City, Utah 84101 (United States)

2012-07-01T23:59:59.000Z

299

annual performance assessment: Topics by E-print Network  

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

Symposium, June 4-7, 2006 ASSESSMENT OF SHOULDER-BED, INVASION, AND LAMINATION Fossil Fuels Websites Summary: Annual Logging Symposium held in Veracruz, Mexico, June 4-7, 2006....

300

Environmental assessment for the Strategic Petroleum Reserve Big Hill facility storage of commercial crude oil project, Jefferson County, Texas  

SciTech Connect (OSTI)

The Big Hill SPR facility located in Jefferson County, Texas has been a permitted operating crude oil storage site since 1986 with benign environmental impacts. However, Congress has not authorized crude oil purchases for the SPR since 1990, and six storage caverns at Big Hill are underutilized with 70 million barrels of available storage capacity. On February 17, 1999, the Secretary of Energy offered the 70 million barrels of available storage at Big Hill for commercial use. Interested commercial users would enter into storage contracts with DOE, and DOE would receive crude oil in lieu of dollars as rental fees. The site could potentially began to receive commercial oil in May 1999. This Environmental Assessment identified environmental changes that potentially would affect water usage, power usage, and air emissions. However, as the assessment indicates, changes would not occur to a major degree affecting the environment and no long-term short-term, cumulative or irreversible impacts have been identified.

NONE

1999-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design  

SciTech Connect (OSTI)

FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

Coles, Garill A.; Gitau, Ernest TN; Hockert, John; Zentner, Michael D.

2012-11-09T23:59:59.000Z

302

Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design  

SciTech Connect (OSTI)

FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

Coles, Garill A.; Hockert, John; Gitau, Ernest TN; Zentner, Michael D.

2013-01-26T23:59:59.000Z

303

Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)  

SciTech Connect (OSTI)

Under the Tritium Facility Modernization {ampersand} Consolidation (TFM{ampersand}C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM{ampersand}C Project also provides for a new replacement R&D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H.

Hsu, R.H. [Westinghouse Savannah River Company, AIKEN, SC (United States); Oji, L.N.

1997-11-14T23:59:59.000Z

304

Geochemical Data Package for Performance Assessment Calculations Related to the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site disposes of certain types of radioactive waste within subsurface-engineered facilities. One of the tools used to establish the capacity of a given site to safely store radioactive waste (i.e., that a site does not exceed its Waste Acceptance Criteria) is the Performance Assessment (PA). The objective of this document is to provide the geochemical values for the PA calculations. This work is being conducted as part of the on-going maintenance program that permits the PA to periodically update existing calculations when new data becomes available. Because application of values without full understanding of their original purpose may lead to misuse, this document also provides the geochemical conceptual model, approach used for selecting the values, the justification for selecting data, and the assumptions made to assure that the conceptual and numerical geochemical models are reasonably conservative (i.e., reflect conditions that will tend to predict the maximum risk to the hypothetical recipient). The geochemical parameters describe transport processes for 38 elements (>90 radioisotopes) potentially occurring within eight disposal units (Slit Trenches, Engineered Trenches, Low Activity Waste (LAW) Vault, Intermediate Level (ILV) Vaults, TRU-Pad-1, Naval Reactor Waste Pads, Components-in-Grout Trenches, and Saltstone Facility). This work builds upon well-documented work from previous PA calculations (McDowell-Boyer et al. 2000). The new geochemical concepts introduced in this data package are: (1) In the past, solubility products were used only in a few conditions (element existing in a specific environmental setting). This has been expanded to >100 conditions. (2) Radionuclide chemistry in cementitious environments is described through the use of both the Kd and apparent solubility concentration limit. Furthermore, the solid phase is assumed to age during the assessment period (thousands of years), resulting in three main types of controlling solid phases, each possessing a unique set of radionuclide sorption parameters (Kd and solubility concentration limit). (3) A large amount of recent site-specific sorption research has been conducted since the last PA (McDowell-Boyer et al. 2000). These new data have replaced previous Kd values derived from literature values, thus reducing uncertainty and improving accuracy. Finally, because this document will be used by future PA calculations and external acceptance of the document will eventually be required, this document was extensively reviewed. The review process, including the internal review, site review, and external review process is described.

Kaplan, D

2006-02-28T23:59:59.000Z

305

Initial Single-Shell Tank System Performance Assessment for the Hanford Site  

SciTech Connect (OSTI)

The Initial Single-Shell Tank System Performance Assessment for the Hanford Site (SST PA) presents the analysis of the long-term impacts of residual wastes assumed to remain after retrieval of tank wastes and closure of the SST farms at the U.S. Department of Energy (DOE) Hanford Site. The SST PA supports key elements of the closure process agreed upon in 2004 by DOE, the Washington State Department of Ecology (Ecology), and the U.S. Environmental Protection Agency (EPA). The SST PA element is defined in Appendix I of the Hanford Federal Facility Agreement and Consent Order (HFFACO) (Ecology et al. 1989), the document that establishes the overall closure process for the SST and double-shell tank (DST) systems. The approach incorporated in the SST PA integrates substantive features of both hazardous and radioactive waste management regulations into a single analysis. The defense-in-depth approach used in this analysis defined two major engineering barriers (a surface barrier and the grouted tank structure) and one natural barrier (the vadose zone) that will be relied on to control waste release into the accessible environment and attain expected performance metrics. The analysis evaluates specific barrier characteristics and other site features that influence contaminant migration by the various pathways. A 'reference' case and a suite of sensitivity/uncertainty cases are considered. The 'reference case' evaluates environmental impacts assuming central tendency estimates of site conditions. 'Reference' case analysis results show residual tank waste impacts on nearby groundwater, air resources; or inadvertent intruders to be well below most important performance objectives. Conversely, past releases to the soil, from previous tank farm operations, are shown to have groundwater impacts that are significantly above most performance objectives. Sensitivity/uncertainty cases examine single and multiple parameter variability along with plausible alternatives to 'reference' cases to judge how well the proposed closure system performs when changes to important assumptions are made to the hydrogeologic and engineered systems. The estimated impacts from these cases are generally consistent with 'reference' case results (i.e., performance objectives are exceeded by contaminants from past releases but not tank residuals). This document and its future iterations will play a critical role in the decision making process for the closure of the Hanford Tank Farms. It will support interim decisions related to tank retrievals and interim corrective measures, in addition to supporting the major closure decisions of tanks and tank farms. Hence, it is imperative that the review process of this document is inclusive of the decision makers as well as the Hanford Stakeholders. (authors)

Jaraysi, M.N.; Kristofzski, J.G.; Connelly, M.P. [CH2M HILL Hanford Group, Inc., Richland, WA (United States); Wood, M.I. [Fluor Hanford Inc., Richland WA (United States); Knepp, A.J. [YAHSGS LLC, Richland WA (United States); Quintero, R.A. [Office of River Protection, United States Department of Energy, Richland, WA (United States)

2007-07-01T23:59:59.000Z

306

INITIAL SINGLE SHELL TANK (SST) SYSTEM PERFORMANCE ASSESSMENT OF THE HANFORD SITE  

SciTech Connect (OSTI)

The ''Initial Single-Shell Tank System Performance Assessment for the Hanford Site [1] (SST PA) presents the analysis of the long-term impacts of residual wastes assumed to remain after retrieval of tank waste and closure of the SST farms at the US Department of Energy (DOE) Hanford Site. The SST PA supports key elements of the closure process agreed upon in 2004 by DOE, the Washington State Department of Ecology (Ecology), and the US Environmental Protection Agency (EPA). The SST PA element is defined in Appendix I of the ''Hanford Federal Facility Agreement and Consent Order'' (HFFACO) (Ecology et al. 1989) [2], the document that establishes the overall closure process for the SST and double-shell tank (DST) systems. The approach incorporated in the SST PA integrates substantive features of both hazardous and radioactive waste management regulations into a single analysis. The defense-in-depth approach used in this analysis defined two major engineering barriers (a surface barrier and the grouted tank structure) and one natural barrier (the vadose zone) that will be relied on to control waste release into the accessible environment and attain expected performance metrics. The analysis evaluates specific barrier characteristics and other site features that influence contaminant migration by the various pathways. A ''reference'' case and a suite of sensitivity/uncertainty cases are considered. The ''reference case'' evaluates environmental impacts assuming central tendency estimates of site conditions. ''Reference'' case analysis results show residual tank waste impacts on nearby groundwater, air resources; or inadvertent intruders to be well below most important performance objectives. Conversely, past releases to the soil, from previous tank farm operations, are shown to have groundwater impacts that re significantly above most performance objectives. Sensitivity/uncertainty cases examine single and multiple parameter variability along with plausible alternatives to ''reference'' cases to judge how the proposed closure system performs when changes to important assumptions are made to the hydrogeologic and engineered systems. The estimated impacts from these cases are generally consistent with ''reference'' case results (i.e., performance objectives are exceeded by contaminants from past releases but not tank residuals). This document and its future iterations will play a critical role in the decision making process for the closure of the Hanford Tank Farms. It will support interim decisions related to tank retrievals and interim corrective measures, in addition to supporting the major closure decisions of tanks and tank farms. Hence, it is imperative that the review process of this document is inclusive of the decision makers as well as the Hanford Stakeholders.

JARAYSI, M.N.

2007-01-08T23:59:59.000Z

307

CEMENTITIOUS BARRIERS MODELING FOR PERFORMANCE ASSESSMENTS OF SHALLOW LAND BURIAL OF LOW LEVEL RADIOACTIVE WASTE - 9243  

SciTech Connect (OSTI)

The Cementitious Barriers Partnership (CBP) was created to develop predictive capabilities for the aging of cementitious barriers over long timeframes. The CBP is a multi-agency, multi-national consortium working under a U.S. Department of Energy (DOE) Environmental Management (EM-21) funded Cooperative Research and Development Agreement (CRADA) with the Savannah River National Laboratory (SRNL) as the lead laboratory. Members of the CBP are SRNL, Vanderbilt University, the U.S. Nuclear Regulatory Commission (USNRC), National Institute of Standards and Technology (NIST), SIMCO Technologies, Inc. (Canada), and the Energy Research Centre of the Netherlands (ECN). A first step in developing advanced tools is to determine the current state-of-the-art. A review has been undertaken to assess the treatment of cementitious barriers in Performance Assessments (PA). Representatives of US DOE sites which have PAs for their low level waste disposal facilities were contacted. These sites are the Idaho National Laboratory, Oak Ridge National Laboratory, Los Alamos National Laboratory, Nevada Test Site, and Hanford. Several of the more arid sites did not employ cementitious barriers. Of those sites which do employ cementitious barriers, a wide range of treatment of the barriers in a PA was present. Some sites used conservative, simplistic models that even though conservative still showed compliance with disposal limits. Other sites used much more detailed models to demonstrate compliance. These more detailed models tend to be correlation-based rather than mechanistically-based. With the US DOE's Low Level Waste Disposal Federal Review Group (LFRG) moving towards embracing a risk-based, best estimate with an uncertainties type of analysis, the conservative treatment of the cementitious barriers seems to be obviated. The CBP is creating a tool that adheres to the LFRG chairman's paradigm of continuous improvement.

Taylor, G

2009-01-09T23:59:59.000Z

308

Assessment of humidity management effects on PEM fuel cell performance.  

E-Print Network [OSTI]

?? The electrical energy output and the performance of a PEM fuel cell is dependent on the ion transfer in the fuel cell. The ion… (more)

Osamudiamen Ose Micah, Ose Micah

2011-01-01T23:59:59.000Z

309

West Valley Demonstration Project Phase I Decommissioning - Facility Disposition Partnering Performance Agreement  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomen Owned SmallOf The 2012NuclearBradleyBudgetFurnacesLES'Nuclear Facility Coalition

310

MONTE CARLO SIMULATION OF RADIONUCLIDE MIGRATION IN FRACTURED ROCK FOR THE PERFORMANCE ASSESSMENT OF RADIOACTIVE WASTE  

E-Print Network [OSTI]

OF RADIOACTIVE WASTE REPOSITORIES F. Cadini1 , J. De Sanctis1 , I. Bertoli1 , E. Zio1,2 1 Dipartimento di Energia is a fundamental task in any performance assessment aimed at verifying the protection offered by radioactive waste for chemical or low-level radioactive wastes, or the Performance Assessment (PA) of geological repositories

Paris-Sud XI, Université de

311

Performance Assessment of PID Control Loops based on IMC Tuning Rule  

E-Print Network [OSTI]

Performance Assessment of PID Control Loops based on IMC Tuning Rule Zhenpeng Yu Jiandong Wang ,1, and controllers are usually restricted to the PID form. This paper establishes the lower bounds of integrated is proposed to assess the performance of PID controllers. Numerical and experimental examples, as well

Wang, Jiandong

312

Addressing Facility Needs for Concrete Assessment Using Ultrasonic Testing: Mid-year Report  

SciTech Connect (OSTI)

The UFD Gap Analysis to Support Extended Storage of Used Nuclear Fuel (June 30, 2011) emphasizes the need for the development of monitoring techniques and technologies for dry storage cask materials. A high priority is given to the development of 'systems for early detection of confinement boundary degradation.' This requires both new techniques for monitoring and inspection, as well as new measurable parameters to quantify mechanical degradation. The use of Nonlinear Elastic Wave Spectroscopy (NEWS) has been shown to provide sensitive parameters correlating to mechanical degradation in a wide variety of materials. Herein we report upon recent research performed to address the high priority of concrete degradation using a selection of these techniques and compare to a ASTM standard ultrasonic technique. Also reported are the near term plans to continue this research in the remaining FY and into the coming years. This research was conducted at Los Alamos National Laboratory (LANL) in the Acoustics Lab of the Geophysics group in the Earth and Environmental Sciences division, and in collaboration with the Laboratory for Nondestructive Evaluation at the University of the Mediterranean (Aix en Provence, France) and the Electrical Power Research Institute (EPRI). The objective of this research project was to determine the feasibility of using an NDE technique based on non-linear ultrasound for determining the depth and degree of microcracking in the near surface of concrete and to assess the degree of sensitivity of such technique. This objective is reached by the means of combining linear and nonlinear measurements, associated with numerical simulation. We first study the global effect of thermal damage on concrete's linear and nonlinear properties by resonance inspection techniques. We show that standard pulse wave speed techniques are not relevant to extract mechanical properties of concrete. The high sensitivity of measured nonlinearity is shown and serves as a validation tool for the rest of the study, i.e., probing the material nonlinearity at various depths through the use of Time Reversal Elastic Nonlinearity Diagnostic (TREND). The basic idea of probing the material nonlinearity at various depths by changing the frequency is validated by exhibiting a similar trend as nonlinear resonance measurements. We address at the end of this report, the potentialities of applying these procedures to real concrete structures.

Ulrich, Timothy J. II [Los Alamos National Laboratory; Payan, Cedric [EES-17: GEOPHYSICS, Visitor; Roberts, Peter M. [Los Alamos National Laboratory

2012-03-28T23:59:59.000Z

313

Los Alamos low-level waste performance assessment status  

SciTech Connect (OSTI)

This report reviews the documented Los Alamos studies done to assess the containment of buried hazardous wastes. Five sections logically present the environmental studies, operational source terms, transport pathways, environmental dosimetry, and computer model development and use. This review gives a general picture of the Los Alamos solid waste disposal and liquid effluent sites and is intended for technical readers with waste management and environmental science backgrounds but without a detailed familiarization with Los Alamos. The review begins with a wide perspective on environmental studies at Los Alamos. Hydrology, geology, and meteorology are described for the site and region. The ongoing Laboratory-wide environmental surveillance and waste management environmental studies are presented. The next section describes the waste disposal sites and summarizes the current source terms for these sites. Hazardous chemical wastes and liquid effluents are also addressed by describing the sites and canyons that are impacted. The review then focuses on the transport pathways addressed mainly in reports by Healy and Formerly Utilized Sites Remedial Action Program. Once the source terms and potential transport pathways are described, the dose assessment methods are addressed. Three major studies, the waste alternatives, Hansen and Rogers, and the Pantex Environmental Impact Statement, contributed to the current Los Alamos dose assessment methodology. Finally, the current Los Alamos groundwater, surface water, and environmental assessment models for these mesa top and canyon sites are described.

Wenzel, W.J.; Purtymun, W.D.; Dewart, J.M.; Rodgers, J.E. (comps.)

1986-06-01T23:59:59.000Z

314

Hybrid wing-body aircraft noise and performance assessment  

E-Print Network [OSTI]

Hybrid wing-body aircraft noise generation and boundary layer ingestion (BLI) performance trends with increased fan face Mach number inlet designs are investigated. The presented topics are in support of the NASA subsonic ...

Weed, Philip Andrew

2010-01-01T23:59:59.000Z

315

The power balance method For aerodynamic performance assessment  

E-Print Network [OSTI]

This thesis describes the use of the power balance method for performance estimation of aircraft configurations. In this method, mechanical power production and mechanical power consumption of the aircraft are balanced, ...

Sato, Sho, Ph. D. Massachusetts Institute of Technology

2012-01-01T23:59:59.000Z

316

Project OPTEX: Field study at a petrochemical facility to assess optical remote sensing and dispersion modeling techniques  

SciTech Connect (OSTI)

The American Petroleum Inst. has conducted a field study at a petrochemical facility for the purpose of (1) testing the ability of optical remote sensing (ORS) techniques to characterize fugitive emissions, and (2) assembling ambient and tracer sampler data for evaluating air dispersion models. The study, referred to as the OPTEX (Operational Petrochemical Tracer Experiment) Project, took place during October 1996 at a Texas petrochemical facility. This paper reports on the design of the field study and summarizes the measurements that were obtained in the field. Several aspects of the field study are described in the paper: the types and locations of the emission releases and tracer gases that were used, the deployment of tracer samplers at various downwind distances, the use of open-path FTIR (OP-FTIR) equipment at the site to quantify tracer gas emissions, special short-term tracer gas emissions designed to test the ability of the ORS systems to detect accidental releases, and the use of a Doppler sodar to evaluate vertical profiles of wind and turbulence upwind and downwind of the facility. The data base for this study, as well as that from an earlier field study that took place at the Duke Forest green field site in North Carolina, will be used for evaluating air dispersion model performance and the ability of ORS measurements to quantify fugitive emissions.

Paien, R.J. [ENSR Corp., Acton, MA (United States); Zwicker, J.O. [Remote Sensing Air, Inc., St. Louis, MO (United States); Feldman, H. [American Petroleum Inst., Washington, DC (United States)

1997-12-31T23:59:59.000Z

317

Environmentally based siting assessment for synthetic-liquid-fuels facilities. Final report  

SciTech Connect (OSTI)

A detailed assessment of the major environmental constraints to siting a synthetic fuels industry and the results of that assessment are used to determine on a regional basis the potential for development of such an industry with minimal environmental conflicts. Secondly, the ability to mitigate some of the constraining impacts through alternative institutional arrangements, especially in areas that are judged to have a low development potential is also assessed. Limitations of the study are delineated, but specifically, the study is limited geographically to well-defined boundaries that include the prime coal and oil shale resource areas. The critical factors used in developing the framework are air quality, water availability, socioeconomic capacity, ecological sensitivity, environmental health, and the management of Federally owned lands. (MCW)

None

1980-01-01T23:59:59.000Z

318

NERSC 2011: High Performance Computing Facility Operational Assessment for the National Energy Research Scientific Computing Center  

E-Print Network [OSTI]

deposited on a flat metal- carbide surface. The tube startsduring SWCNT synthesis on metal carbide surface substrates.

Antypas, Katie

2013-01-01T23:59:59.000Z

319

NERSC 2011: High Performance Computing Facility Operational Assessment for the National Energy Research Scientific Computing Center  

E-Print Network [OSTI]

Tape System Reliability High Owner: Jason Hick, Systems Storage Group Lead Med X Low Low Med High Impact Trigger: Tape errors exceed observed

Antypas, Katie

2013-01-01T23:59:59.000Z

320

Using performance assessment for radioactive waste disposal decision making -- implementation of the methodology into the third performance assessment iteration of the Greater Confinement Disposal site  

SciTech Connect (OSTI)

The US Department of Energy is responsible for the disposal of a variety of radioactive wastes. Some of these wastes are prohibited from shallow land burial and also do not meet the waste acceptance criteria for proposed waste repositories at the Waste Isolation Pilot Plant (WIPP) and Yucca Mountain. These have been termed ``special-case`` waste and require an alternative disposal method. From 1984 to 1989, the Department of Energy disposed of a small quantity of special-case transuranic wastes at the Greater Confinement Disposal (GCD) site at the Nevada Test Site. In this paper, an iterative performance assessment is demonstrated as a useful decision making tool in the overall compliance assessment process for waste disposal. The GCD site has been used as the real-site implementation and test of the performance assessment approach. Through the first two performance assessment iterations for the GCD site, and the transition into the third, we demonstrate how the performance assessment methodology uses probabilistic risk concepts to guide affective decisions about site characterization activities and how it can be used as a powerful tool in bringing compliance decisions to closure.

Gallegos, D.P.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (United States); Baer, T.A. [GRAM, Inc., Albuquerque, NM (United States)

1993-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Preliminary assessment of radiological doses in alternative waste management systems without an MRS facility  

SciTech Connect (OSTI)

This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the reference study system, the radiological doses to the public and to the occupational workers are low, about 170 person-rem/1000 metric ton of uranium (MTU) handled with 70% of the fuel transported by rail and 30% by truck. The radiological doses to the public are almost entirely from transportation, whereas the doses to the occupational workers are highest at the reactors and the repository. Operating alternatives examined included using larger transportation casks, marshaling rail cars into multicar dedicated trains, consolidating spent fuel at the reactors, and wet or dry transfer options of spent fuel from dry storage casks. The largest contribution to radiological doses per unit of spent fuel for both the public and occupational workers would result from use of truck transportation casks, which are smaller than rail casks. Thus, reducing the number of shipments by increasing cask sizes and capacities (which also would reduce the number of casks to be handled at the terminals) would reduce the radiological doses in all cases. Consolidating spent fuel at the reactors would reduce the radiological doses to the public but would increase the doses to the occupational workers at the reactors.

Schneider, K.J.; Pelto, P.J.; Daling, P.M.; Lavender, J.C.; Fecht, B.A.

1986-06-01T23:59:59.000Z

322

CRAD, Performance-Based Inspection - August 19, 2010 | Department...  

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

Performance-Based Inspection - November 29, 2011 CRAD, Nuclear Facility Construction - Piping and Pipe Supports Inspection - March 29, 2012 CRAD, Assessment of the Site - February...

323

DOE's New Checklist Helps Plants Assess Energy Management Activities...  

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

simple checklist can help a facility assess whether Superior Energy Performance (SEP) or ISO 50001 are practical next steps, or if foundational energy management activities...

324

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incineration facility (East Liverpool, Ohio). Volume 6. Screening ecological risk assessment  

SciTech Connect (OSTI)

The Screening Ecological Risk Assessment (SERA) includes an evaluation of available biotic information from the site vicinity to provide a preliminary description of potential ecological receptors (e.g., rare, threatened and endangered species; migratory birds; and important game species), and important ecological habitats (e.g., wetland areas). A conceptual site model is developed that describe show stressors associated with the WTI facility might affect the ecological components in the surrounding environment through the development and evaluation of specific ecological endpoints. Finally, an estimate of the potential for current and/or future adverse impacts to the biotic component of the environment is provided, based on the integration of potential exposures of ecological receptors to WTI emissions and toxicological threshold values.

NONE

1997-05-01T23:59:59.000Z

325

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio). Volume 5. Human health risk assessment (HHRA): Evaluation of potential risks from multipathway exposure to emissions. Draft report  

SciTech Connect (OSTI)

The Human Health Risk Assessment (HHRA) portion of the WTI Risk Assessment involves the integration of information about the facility with site-specific data for the surrounding region and population to characterize the potential human health risks due to emissions from the facility. The estimation of human health risks is comprised of the following general steps: (1) identification of substances of potential concern; (2) estimation of the nature and magnitude of chemical releases from the WTI facility; (3) prediction of the atmospheric transport of the emitted contaminants; (4) determination of the types of adverse effects associated with exposure to the substances of potential concern (referred to as hazard identification), and the relationship between the level of exposure and the severity of any health effect (referred to as dose-response assessment); (5) estimation of the magnitude of exposure (referred to as exposure assessment); and (6) characterization of the health risks associated with exposure (referred to as risk characterization).

NONE

1995-11-01T23:59:59.000Z

326

Models used to assess the performance of photovoltaic systems.  

SciTech Connect (OSTI)

This report documents the various photovoltaic (PV) performance models and software developed and utilized by researchers at Sandia National Laboratories (SNL) in support of the Photovoltaics and Grid Integration Department. In addition to PV performance models, hybrid system and battery storage models are discussed. A hybrid system using other distributed sources and energy storage can help reduce the variability inherent in PV generation, and due to the complexity of combining multiple generation sources and system loads, these models are invaluable for system design and optimization. Energy storage plays an important role in reducing PV intermittency and battery storage models are used to understand the best configurations and technologies to store PV generated electricity. Other researcher's models used by SNL are discussed including some widely known models that incorporate algorithms developed at SNL. There are other models included in the discussion that are not used by or were not adopted from SNL research but may provide some benefit to researchers working on PV array performance, hybrid system models and energy storage. The paper is organized into three sections to describe the different software models as applied to photovoltaic performance, hybrid systems, and battery storage. For each model, there is a description which includes where to find the model, whether it is currently maintained and any references that may be available. Modeling improvements underway at SNL include quantifying the uncertainty of individual system components, the overall uncertainty in modeled vs. measured results and modeling large PV systems. SNL is also conducting research into the overall reliability of PV systems.

Stein, Joshua S.; Klise, Geoffrey T.

2009-12-01T23:59:59.000Z

327

Privatising national oil companies: Assessing the impact on firm performance  

E-Print Network [OSTI]

government having to cede majority control. Key words Privatisation, ownership, corporate performance, anticipation, oil and gas industry JEL Classifications: C23, G32, L33, L71, M20, Q40 2 I. Introduction The impact of ownership... privatisation date, accrue over time, and level off after the initial ownership change rather than accelerate. Details of residual government ownership, control transfer, and size and timing of follow-on offerings provide limited incremental explanatory power...

Wolf, C; Pollitt, Michael G.

328

Assessment of operating parameter variation on electrostatic precipitator performance  

E-Print Network [OSTI]

lignite coal were collected and resistivity analysis performed for varying conditions of temperature and humidity. As a result of the laboratory analysis, it was determined that moisture and temperature conditioning of Texas lignite coal fly ash... results. I 5. Sample 8 moisturi ed test results. 57 64 66 69 77 LIST OF FIGURES Figure Lignite coal deposit formations in East Texas. Z. The electrostatic precipitator system 3. Electrostatic precipitator in operation. 4. Electrostatic...

Gunn, Roam Anthony

1974-01-01T23:59:59.000Z

329

Theoretical analysis of the subcritical experiments performed in the IPEN/MB-01 research reactor facility  

SciTech Connect (OSTI)

The theoretical analysis of the subcritical experiments performed at the IPEN/MB-01 reactor employing the coupled NJOY/AMPX-II/TORT systems was successfully accomplished. All the analysis was performed employing ENDF/B-VII.0. The theoretical approach follows all the steps of the subcritical model of Gandini and Salvatores. The theory/experiment comparison reveals that the calculated subcritical reactivity is in a very good agreement to the experimental values. The subcritical index ({xi}) shows some discrepancies although in this particular case some work still have to be made to model in a better way the neutron source present in the experiments. (authors)

Lee, S. M.; Dos Santos, A. [Inst. de Pesquisas Energeticas e Nucleares, Cidade Universitaria, Av. Lineu Prestes, 2242, 05508-000 Sao Paulo - SP (Brazil)

2012-07-01T23:59:59.000Z

330

Performance Confirmation Strategies for the Waste Isolation Pilot Plant - A Historical Perspective from an Operating Disposal Facility - 12248  

SciTech Connect (OSTI)

Performance confirmation is an important element of the Waste Isolation Pilot Plant (WIPP) program. Performance confirmation was first used during the early WIPP site characterization phase to focus experimental activities that address the development of probabilistic repository performance models and to address stakeholder assurance needs. The program is currently used to analyze the conditions of the repository and its surroundings to ensure that the basis for the repository's long-term radioactive waste containment predictions is valid. This basis is related to the parameters, assumptions, conceptual and numerical models that are used to predict or validate the potential radioactive waste containment performance of the system. The concept of performance confirmation for the WIPP is one that has evolved since the first repository work was initiated decades ago and plays an important role in assuring adequate repository performance both now and in the long-term. The WIPP mission has progressed from a pilot project to an operational disposal facility and will progress to eventual site closure when disposal operations are completed. Performance confirmation is an important part of each of these progressions. The concept of disposing radioactive waste in a geologic repository today involves a complete understanding of many technical, political, regulatory, societal and economic elements. Many of these elements overlap and solving all relevant issues necessary to site, operate and decommission a disposal facility should be done with knowledge of each element's requirements and impacts. Performance confirmation is one tool that can help to coordinate many of these elements into a program that actively investigates what is thought to be adequately understood about the system and what information is lacking. A performance confirmation program is used to determine ways to challenge and verify those areas that are thought to be understood and to find ways to understand those areas that are not well understood. Performance confirmation programs have been used twice at WIPP, first during site characterization and PA development and later in a Compliance Monitoring program. At first, only certain technical aspects of the system were deemed important because it was a scientifically-based, government project. Early site characterization work was design to gather information about the geology and hydrology of the area and the mechanical properties of the natural barrier. The information would be used in a PA to determine the long-term containment performance of the disposal system. A performance confirmation element was used to identify the sensitive elements of the system that were certain, well understood or justified and those that were not. It identified experimental and analytical programs that could be used to reduce uncertainty, confirm sensitive assumptions and provide useful data. This performance confirmation program provided data to justify the adequacy of the information used in PA to demonstrate compliance with EPA's containment requirements. Performance confirmation will continue to be used in the post-closure period for at least 30 years and likely up to the end of the 100-year institutional controls period. As the technical basis for the repository matures throughout the operational period, the currently planned post-closure monitoring program will need to be reassessed prior to implementation. However, the intent of the program will be the same as it was for the previous programs, to ensure the ultimate goal of the repository. This goal is to safely isolate waste from the accessible environment and ensure public and environmental safety. (authors)

Wagner, Steve [John Hart and Associate for Sandia National Laboratories, Carlsbad, New Mexico 88220 (United States)

2012-07-01T23:59:59.000Z

331

Residential commissioning to assess envelope and HVAC system performance  

SciTech Connect (OSTI)

Houses do not perform optimally or even as many codes and forecasts predict. For example, Walker et al. (1998a) found large variations in thermal distribution system efficiency, as much as a factor of two even between side-by-side houses with the same system design and installation crew. This and other studies (e.g., Jump et al. 1996) indicate that duct leakage testing and sealing can readily achieve a 25 to 30% reduction in installed cooling capacity and energy consumption. As another example, consider that the building industry has recognized for at least 20 years the substantial impact that envelope airtightness has on thermal loads, energy use, comfort, and indoor air quality. However, Walker et al. (1998a) found 50% variances in airtightness for houses with the same design and construction crews, within the same subdivision. A substantial reason for these problems is that few houses are now built or retrofitted using formal design procedures, most are field assembled from a large number of components, and there is no consistent process to identify problems or to correct them. Solving the problems requires field performance evaluations of houses using appropriate and agreed upon procedures. Many procedural elements already exist in a fragmented environment; some are ready now to be integrated into a new process called residential commissioning (Wray et al. 2000). For example, California's Title 24 energy code already provides some commissioning elements for evaluating the energy performance of new houses. A house consists of components and systems that need to be commissioned, such as building envelopes, air distribution systems, cooling equipment, heat pumps, combustion appliances, controls, and other electrical appliances. For simplicity and practicality, these components and systems are usually evaluated individually, but we need to bear in mind that many of them interact. Therefore, commissioning must not only identify the energy and non-energy benefits associated with improving the performance of a component, it must also indicate how individual components interact in the complete building system. For this paper, we limit our discussion to diagnostics in areas of particular concern with significant interactions: envelope and HVAC systems. These areas include insulation quality, windows, airtightness, envelope moisture, fan and duct system airflows, duct leakage, cooling equipment charge, and combustion appliance backdrafting with spillage. The remainder of this paper first describes what residential commissioning is, its characteristic elements, and how one might structure its process. Subsequent sections describe a consolidated set of practical diagnostics that the building industry can use now. Where possible, we also discuss the accuracy and usability of these diagnostics, based on recent laboratory work and field studies. We conclude by describing areas in need of research and development, such as practical field diagnostics for envelope thermal conductance and combustion safety. There are several potential benefits for builders, consumers, code officials, utilities, and energy planners of commissioning houses using a consistent set of validated methods. Builders and/or commissioning agents will be able to optimize system performance and reduce consumer costs associated with building energy use. Consumers will be more likely to get what they paid for and builders can show they delivered what was expected. Code officials will be better able to enforce existing and future energy codes. As energy reduction measures are more effectively incorporated into the housing stock, utilities and energy planners will benefit through greater confidence in predicting demand and greater assurance that demand reductions will actually occur. Performance improvements will also reduce emissions from electricity generating plants and residential combustion equipment. Research to characterize these benefits is underway.

Wray, Craig P.; Sherman, Max H.

2001-08-31T23:59:59.000Z

332

Evaluating the effects of the number of caverns on the performance of underground oil storage facilities  

SciTech Connect (OSTI)

Three dimensional finite element calculations were performed to investigate the effect field size, in terms of the number of caverns, on the performance of SPR oil storage caverns leached in domal salt (interms of surface subsidence, storage losses, and cavern integrity). The calculations were performed for cavern fields containing 1, 7, 19, and an infinite number of caverns. The magnitude and volume of subsidence was significantly affected by increasing the number of caverns (nearly an order of magnitude increase was predicted for each increase in field size), while the extent of subsidence (approximately 2000 m fromthe center of the field) and storage loss were not. Furthermore, the percentage of storage loss volume manifested as surface subsidence increased as the cavern field was enlarged. This was attributed to elasticvolumetric dilatation of overlying strata. The multiple cavern calculations demonstrate that storage losses are greater for caverns farther from the center of the caverns field. Based on an accumulated strain stability criteria, the larger cavern fields are predicted to have a shorter life. This criteria also indicates that caverns on the periphery of a field may show signs of instability before the inner caverns. The West Hackberry site (containing 22 caverns) subsidence data closely agrees with the 19 cavern model subsidence predictions, providing confidence in the calculations. Even a 19 cavern field, substantially large by SPR standards, does not approach the behavior predicted by infinite cavern models (which are frequently used because they are economical). This demonstrates that 3D modeling is required to accurately investigate the performance of a multi-cavern array. Although based on a typical SPR cavern design, the results of this study describe mechanics common to all multi-cavern fields and should, in general, be useful tocavern engineers and architects.

Hoffman, E.L.; Ehgartner, B.L.

1992-01-01T23:59:59.000Z

333

Nuclear power plant performance assessment pertaining to plant aging in France and the United States  

E-Print Network [OSTI]

The effect of aging on nuclear power plant performance has come under increased scrutiny in recent years. The approaches used to make an assessment of this effect strongly influence the economics of nuclear power plant ...

Guyer, Brittany (Brittany Leigh)

2013-01-01T23:59:59.000Z

334

Assessment of durability performance of "Early-Opening-to-Traffic" Portland Cement Concrete pavement and patches  

E-Print Network [OSTI]

This study relates the assessment of durability to ''early-opening-to-traffic'' (EOT) portland cement concrete (PCC). Several factors were identified relative to the performance of EOT PCC. Each of these factors was considered in terms of freeze...

Shrestha, Pradhumna Babu

1999-01-01T23:59:59.000Z

335

Hydronic radiant cooling: Overview and preliminary performance assessment  

SciTech Connect (OSTI)

A significant amount of electrical energy used to cool non-residential buildings is drawn by the fans used to transport the cool air through the thermal distribution system. Hydronic systems reduce the amount of air transported through the building by separating ventilation and thermal conditioning. Due to the physical properties of water, hydronic distribution systems can transport a given amount of thermal energy using less than 5% of the otherwise necessary fan energy. This savings alone significantly reduces the energy consumption and especially the peak power requirement This survey clearly shows advantages for radiant cooling in combination with hydronic thermal distribution systems in comparison with the All-Air Systems commonly used in California. The report describes a literature survey on the system's development, thermal comfort issues, and cooling performance. The cooling power potential and the cooling power requirement are investigated for several California climates. Peak-power requirement is compared for hydronic radiant cooling and conventional All-Air-Systems.

Feustel, H.E.

1993-05-01T23:59:59.000Z

336

Assessment of performing an MST strike in Tank 21H  

SciTech Connect (OSTI)

Previous Savannah River National Laboratory (SRNL) tank mixing studies performed for the Small Column Ion Exchange (SCIX) project have shown that 3 Submersible Mixer Pumps (SMPs) installed in Tank 41 are sufficient to support actinide removal by MST sorption as well as subsequent resuspension and removal of settled solids. Savannah River Remediation (SRR) is pursuing MST addition into Tank 21 as part of the Large Tank Strike (LTS) project. The preliminary scope for LTS involves the use of three standard slurry pumps (installed in N, SE, and SW risers) in a Type IV tank. Due to the differences in tank size, internal interferences, and pump design, a separate mixing evaluation is required to determine if the proposed configuration will allow for MST suspension and strontium and actinide sorption. The author performed the analysis by reviewing drawings for Tank 21 [W231023] and determining the required cleaning radius or zone of influence for the pumps. This requirement was compared with previous pilot-scale MST suspension data collected for SCIX that determined the cleaning radius, or zone of influence, as a function of pump operating parameters. The author also reviewed a previous Tank 50 mixing analysis that examined the ability of standard slurry pumps to suspend sludge particles. Based on a review of the pilot-scale SCIX mixing tests and Tank 50 pump operating experience, three standard slurry pumps should be able to suspend sludge and MST to effectively sorb strontium and actinides onto the MST. Using the SCIX data requires an assumption about the impact of cooling coils on slurry pump mixing. The basis for this assumption is described in this report. Using the Tank 50 operating experience shows three standard slurry pumps should be able to suspend solids if the shear strength of the settled solids is less than 160 Pa. Because Tank 21 does not contain cooling coils, the shear strength could be larger.

Poirier, Michael R.

2014-09-29T23:59:59.000Z

337

Integrating natural resource damage assessment and environmental restoration activities at DOE facilities  

SciTech Connect (OSTI)

Environmental restoration activities are currently under way at many U.S. Department of Energy (DOE) sites under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. DOE is the CERCLA lead response agency for these activities. Section 120 of CERCLA also could subject DOE to liability for natural resource damages resulting from hazardous substance releases at its sites. A Natural Resource Damage Assessment (NRDA) process is used to determine whether natural resources have been injured and to calculate compensatory monetary damages to be used to restore the natural resources. In addition to restoration costs, damages may include costs of conducting the damage assessment and compensation for interim losses of natural resource services that occur before resource restoration is complete. Natural resource damages represent a potentially significant source of additional monetary claims under CERCLA, but are not well known or understood by many DOE staff and contractors involved in environmental restoration activities. This report describes the requirements and procedures of NRDA in order to make DOE managers aware of what the process is designed to do. It also explains how to integrate the NRDA and CERCLA Remedial Investigation/Feasibility Study processes, showing how the technical and cost analysis concepts of NRDA can be borrowed at strategic points in the CERCLA process to improve decisionmaking and more quickly restore natural resource services at the lowest total cost to the public.

NONE

1993-10-01T23:59:59.000Z

338

Integrating Natural Resource Damage Assessment and environmental restoration activities at DOE facilities  

SciTech Connect (OSTI)

Environmental restoration activities are currently under way at many US Department of Energy (DOE) sites under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). DOE is the CERCLA lead response agency for these activities. Section 120 of CERCLA also could subject DOE to liability for natural resource damages resulting from hazardous substance releases at its sites. A Natural Resource Damage Assessment (NRDA) process is used to determine whether natural resources have been injured and to calculate compensatory monetary damages to be used to restore the natural resources. In addition to restoration costs, damages may include costs of conducting the damage assessment and compensation for interim losses of natural resource services that occur before resource restoration is complete. Natural resource damages represent a potentially significant source of additional monetary claims under CERCLA, but are not well known or understood by many DOE staff and contractors involved in environmental restoration activities. This report describes the requirements and procedures of NRDA in order to make DOE managers aware of what the process is designed to do. It also explains how to integrate the NRDA and CERCLA Remedial Investigation/Feasibility Study processes, showing how the technical and cost analysis concepts of NRDA can be borrowed at strategic points in the CERCLA process to improve decisionmaking and more quickly restore natural resource services at the lowest total cost to the public.

Not Available

1993-10-01T23:59:59.000Z

339

Integrating Natural Resource Damage Assessment and environmental restoration activities at DOE facilities  

SciTech Connect (OSTI)

Environmental restoration activities are currently under way at several sites owned by the US Department of Energy (DOE) under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. DOE is the CERCLA lead response agency for these activities. Section 120(a) of the Superfund Amendments and Reauthorization Act also subjects DOE to liability under Section 107 of CERCLA for natural resource damages resulting from hazardous substance releases at its sites. The Natural Resource Damage Assessment (NRDA) process, by which natural resource injuries are determined and compensatory monetary damages are calculated, is not well known or understood by DOE staff and contractors involved in environmental restoration activities. Nevertheless, natural resource liabilities are potentially a significant source of additional monetary claims for CERCLA hazardous substance releases. This paper describes the requirements of NRDA and explains how to integrate the NRDA and CERCLA Remedial Investigation/Feasibility Study processes, in order to more quickly restore environmental services at the lowest total cost to the public. The first section of the paper explains the statutory and regulatory mandates for the NRDA process. The second section briefly describes the four phases of the NRDA process, while the third section examines the three steps in the assessment phase in considerable detail. Finally, the last section focuses on the integration of the CERCLA and NRDA processes.

Bascietto, J.J. [Dept. of Energy, Washington, DC (US). RCRA/CERCLA Div.; Dunford, R.W. [Research Triangle Inst., Research Triangle Park, NC (US); Sharples, F.E.; Suter, G.W. II [Oak Ridge National Lab., TN (US)

1993-06-01T23:59:59.000Z

340

Assessment of radiation exposure for materials in the LANSCE Spallation Irradiation Facility  

SciTech Connect (OSTI)

Materials samples were irradiated in the Los Alamos Radiation Effects Facility (LASREF) at the Los Alamos Neutron Science Center (LANSCE) to provide data for the Accelerator Production of Tritium (APT) project on the changes in mechanical and physical properties of materials in a spallation target environment. The targets were configured to expose samples to a variety of radiation environments including high-energy protons, mixed protons and neutrons, and predominantly neutrons. The irradiation was driven by an 800 MeV 1 mA proton beam with a circular Gaussian shape of approximately 2{sigma} = 3.5 cm. Two irradiation campaigns were conducted in which samples were exposed for approximately six months and two months, respectively. At the end of this period, the samples were extracted and tested. Activation foils that had been placed in proximity to the materials samples were used to quantify the fluences in various locations. The STAYSL2 code was used to estimate the fluences by combining the activation foil data with calculated data from the LAHET Code System (LCS) and MCNPX. The exposure for each sample was determined from the estimated fluences using interpolation based on a mathematical fitting to the fluence results. The final results included displacement damage (dpa) and gas (H, He) production for each sample from the irradiation. Based on the activation foil analysis, samples from several locations in both irradiation campaigns were characterized. The radiation damage to each sample was highly dependent upon location and varied from 0.023 to 13 dpa and was accompanied by high levels of H and He production.

James, M. R. (Michael R.); Maloy, S. A. (Stuart A.); Sommer, W. F. (Walter F.), Jr.; Fowler, Malcolm M.; Dry, D. E. (Donald E.); Ferguson, P. D. (Phillip D.); Corzine, R. K. (R. Karen); Mueller, G. E. (Gary E.)

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Data used in preliminary performance assessment of the Waste Isolation Pilot Plant (1990)  

SciTech Connect (OSTI)

This report documents the data available as of August 1990 and used by the Performance Assessment Division of Sandia National Laboratories in its December 1990 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Parameter values are presented in table form for the geologic subsystem, engineered barriers, borehole flow properties, climate variability, and intrusion characteristics. Sources for the data and a brief discussion of each parameter are provided. 101 refs., 72 figs., 21 tabs.

Rechard, R.P (Sandia National Labs., Albuquerque, NM (USA)); Luzzolino, H. (Geo-Centers, Inc., Albuquerque, NM (USA)); Sandha, J.S. (Science Applications International Corp., Albuquerque, NM (USA))

1990-12-01T23:59:59.000Z

342

Environmental assessment of the brine pipeline replacement for the Strategic Petroleum Reserve Bryan Mound Facility in Brazoria County, Texas  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0804, for the proposed replacement of a deteriorated brine disposal pipeline from the Strategic Petroleum Reserve (SPR) Bryan Mound storage facility in Brazoria County, Texas, into the Gulf of Mexico. In addition, the ocean discharge outfall would be moved shoreward by locating the brine diffuser at the end of the pipeline 3.5 miles offshore at a minimum depth of 30 feet. The action would occur in a floodplain and wetlands; therefore, a floodplain/wetlands assessment has been prepared in conjunction with this EA. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969 (42 USC. 4321, et seg.). Therefore, the preparation of an Environmental Impact Statement (EIS) is not required, and the Department is issuing this Finding of No Significant Impact (FONSI). This FONSI also includes a Floodplain Statement of Findings in accordance with 10 CFR Part 1022.

Not Available

1993-09-01T23:59:59.000Z

343

Performance assessment of the PNM Prosperity electricity storage project :  

SciTech Connect (OSTI)

The purpose of this study is to characterize the technical performance of the PNM Prosperity electricity storage project, and to identify lessons learned that can be used to improve similar projects in the future. The PNM Prosperity electricity storage project consists of a 500 kW/350 kWh advanced lead-acid battery with integrated supercapacitor (for energy smoothing) and a 250 kW/1 MWh advanced lead-acid battery (for energy shifting), and is co-located with a 500 kW solar photovoltaic (PV) resource. The project received American Reinvestment and Recovery Act (ARRA) funding. The smoothing system is e ective in smoothing intermittent PV output. The shifting system exhibits good round-trip efficiencies, though the AC-to-AC annual average efficiency is lower than one might hope. Given the current utilization of the smoothing system, there is an opportunity to incorporate additional control algorithms in order to increase the value of the energy storage system.

Roberson, Dakota; Ellison, James F.; Bhatnagar, Dhruv; Schoenwald, David A.

2014-05-01T23:59:59.000Z

344

Hydronic radiant cooling: Overview and preliminary performance assessment  

SciTech Connect (OSTI)

A significant amount of electrical energy used to cool non-residential buildings is drawn by the fans used to transport the cool air through the thermal distribution system. Hydronic systems reduce the amount of air transported through the building by separating ventilation and thermal conditioning. Due to the physical properties of water, hydronic distribution systems can transport a given amount of thermal energy using less than 5% of the otherwise necessary fan energy. This savings alone significantly reduces the energy consumption and especially the peak power requirement This survey clearly shows advantages for radiant cooling in combination with hydronic thermal distribution systems in comparison with the All-Air Systems commonly used in California. The report describes a literature survey on the system`s development, thermal comfort issues, and cooling performance. The cooling power potential and the cooling power requirement are investigated for several California climates. Peak-power requirement is compared for hydronic radiant cooling and conventional All-Air-Systems.

Feustel, H.E.

1993-05-01T23:59:59.000Z

345

Environmental Assessment for the Proposed Increase in the Facility Capacity and Petroleum Inventory at the Strategic Petroleum Reserve's Bryan Mound Storage Facility, Texas  

SciTech Connect (OSTI)

The DOE proposes that the authorized capacity of the BM facility and, upon Administration authorization, the petroleum inventory be increased by 3.5 million m{sup 3} (22 MMB). The proposed action may be subdivided into two distinct actions, the action to increase the facility capacity and the action to increase the facility's petroleum inventory, which is conditioned upon future authorization by the Administration. A portion of the proposed increase in facility capacity would be obtained via modification of the existing internal cavern infrastructure. Specifically, of the proposed increase in cavern capacity, up to 1.4 million m{sup 3} (8.8 MMB) would result from adjustment of the suspended casing of 10 caverns, thereby increasing the working cavern volumes without changing the cavern dimensions. The balance of the proposed increase to facility capacity, 2.1 million m{sup 3} (13.2 MMB), would result from administrative activities including the return of cavern 112 to service at its full capacity [approximately 1.9 million m{sup 3} (12 MMB)] and volume upgrades of at least 0.19 million m{sup 3} (1.2 MMB) based on new information obtained during sonar investigation of caverns.

N /A

2004-11-24T23:59:59.000Z

346

An appraisal of the 1992 preliminary performance assessment for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The purpose of the New Mexico Environmental Evaluation Group is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The Environmental Evaluation Group (EEG) has reviewed the WIPP 1992 Performance Assessment (Sandia WIPP Performance Assessment Department, 1992). Although this performance assessment was released after the October 1992 passage of the WIPP Land Withdrawal Act (PL 102-579), the work preceded the Act. For individual and ground-water protection, calculations have been done for 1000 years post closure, whereas the US Environmental Protection Agency`s Standards (40 CFR 191) issued in 1993 require calculations for 10,000 years. The 1992 Performance Assessment continues to assimilate improved understanding of the geology and hydrogeology of the site, and evolving conceptual models of natural barriers. Progress has been made towards assessing WIPP`s compliance with the US Environmental Protection Agency`s Standards (40 CFR 191). The 1992 Performance Assessment has addressed several items of major concern to EEG, outlined in the July 1992 review of the 1991 performance assessment (Neill et al., 1992). In particular, the authors are pleased that some key results in this performance assessment deal with sensitivity of the calculated complementary cumulative distribution functions (CCDF) to alterative conceptual models proposed by EEG -- that flow in the Culebra be treated as single-porosity fracture-flow; with no sorption retardation unless substantiated by experimental data.

Lee, W.W.L.; Chaturvedi, L.; Silva, M.K.; Weiner, R.; Neill, R.H. [Environmental Evaluation Group, Albuquerque, NM (United States)]|[Environmental Evaluation Group, Carlsbad, NM (United States)

1994-09-01T23:59:59.000Z

347

Composite analysis E-area vaults and saltstone disposal facilities  

SciTech Connect (OSTI)

This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

Cook, J.R.

1997-09-01T23:59:59.000Z

348

Models for source term, flow, transport and dose assessment in NRC`s Iterative Performance Assessment, Phase 2  

SciTech Connect (OSTI)

The core consequence modules for the recently completed Phase 2 Iterative Performance Assessment (IPA) of the Yucca Mountain repository for high-level nuclear waste depend on models for releases from the engineered barrier system (source term), flow of liquid and gas, transport of radionuclides in the geosphere and assessment of dose to target populations. The source term model includes temperature and moisture phenomena in the near-field environment, general, pitting and crevice corrosion, contact of the waste form by water, dissolution and oxidation of the waste form, and transport of dissolved and gaseous radionuclides from the waste package by advection and diffusion. The liquid flow and transport models describe water flow through fractures and matrix in both the unsaturated and saturated zones. Models for flow of gas and transport of {sup 14}CO{sub 2} released from the engineered barrier system to the atmosphere take into account repository heat and the geothermal gradient. The dose assessment model calculates doses to a regional population and a farm family for an assumed reference biosphere in the vicinity of the repository. The Phase 2 IPA led to a number of suggestions for model improvement: (1) improve the ability of the models to include spatial and temporal variability in the parameters; (2) improve the coupling among processes, especially the effects of changing environments in the waste packages; (3) develop more mechanistic models, but abstracted for use in total system performance assessment; and (4) use more site specific parameters, especially for the dose assessments.

McCartin, T.; Codell, R.; Neel, R.; Ford, W.; Wescott, R.; Bradbury, J. [Nuclear Regulatory Commission, Washington, DC (United States); Sagar, B.; Walton, J. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX (United States)

1994-12-31T23:59:59.000Z

349

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incinerator facility (east Liverpool, Ohio). Volume 4. Atmospheric dispersion and deposition modeling of emissions. Draft report  

SciTech Connect (OSTI)

The report constitutes a comprehensive site-specific risk assessment for the WTI incineration facility located in East Liverpool, OH. Volume IV describes the air dispersion model used to estimate air concentrations and particle deposition, as well as the results of the modeling exercise.

NONE

1995-11-01T23:59:59.000Z

350

Durability Assessment of an Arch Dam using Inverse Analysis with Neural Networks and High Performance Computing.  

E-Print Network [OSTI]

the viscoelastic parameters; 3D FEM analysis using High Performance Computing (parallel and vector features) to run Performance Computing. E. M. R. Fairbairn, E. Goulart, A. L. G. A. Coutinho, N. F. F. Ebecken COPPEDurability Assessment of an Arch Dam using Inverse Analysis with Neural Networks and High

Coutinho, Alvaro L. G. A.

351

IEA-SHC Task 27: Environmental Performance Assessment of glazing and windows: context, overview, main concerns  

E-Print Network [OSTI]

IEA-SHC Task 27: Environmental Performance Assessment of glazing and windows: context, overview and objectives, and most often of limited use in other contexts. A short review of the studies already performed the work undertaken within the programme of IEA/SHCP/Task 27, which will be presented in the third part

352

Data Packages for the Hanford Immobilized Low Activity Tank Waste Performance Assessment 2001 Version [SEC 1 THRU 5  

SciTech Connect (OSTI)

Data package supporting the 2001 Immobilized Low-Activity Waste Performance Analysis. Geology, hydrology, geochemistry, facility, waste form, and dosimetry data based on recent investigation are provided. Verification and benchmarking packages for selected software codes are provided.

MANN, F.M.

2000-03-02T23:59:59.000Z

353

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

SciTech Connect (OSTI)

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

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

1993-07-01T23:59:59.000Z

354

Transmittal of the Calculation Package that Supports the Analysis of Performance of the Environmental Management Waste Management Facility Oak Ridge, Tennessee (Based 5-Cell Design Issued 8/14/09)  

SciTech Connect (OSTI)

This document presents the results of an assessment of the performance of a build-out of the Environmental Management Waste Management Facility (EMWMF). The EMWMF configuration that was assessed includes the as-constructed Cells 1 through 4, with a groundwater underdrain that was installed beneath Cell 3 during the winter of 2003-2004, and Cell 5, whose proposed design is an Addendum to Remedial Design Report for the Disposal of Oak Ridge Reservation Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Waste, Oak Ridge, Tennessee, DOE/OR/01-1873&D2/A5/R1. The total capacity of the EMWMF with 5 cells is about 1.7 million cubic yards. This assessment was conducted to determine the conditions under which the approved Waste Acceptance Criteria (WAC) for the EMWMF found in the Attainment Plan for Risk/Toxicity-Based Waste Acceptance Criteria at the Oak Ridge Reservation, Oak Ridge, Tennessee [U.S. Department of Energy (DOE) 2001a], as revised for constituents added up to October 2008, would remain protective of public health and safety for a five-cell disposal facility. For consistency, the methods of analyses and the exposure scenario used to predict the performance of a five-cell disposal facility were identical to those used in the Remedial Investigation and Feasibility Study (RI/FS) and its addendum (DOE 1998a, DOE 1998b) to develop the approved WAC. To take advantage of new information and design changes departing from the conceptual design, the modeling domain and model calibration were upaded from those used in the RI/FS and its addendum. It should be noted that this analysis is not intended to justify or propose a change in the approved WAC.

Williams M.J.

2009-09-14T23:59:59.000Z

355

Use of international data sets to evaluate and validate pathway assessment models applicable to exposure and dose reconstruction at DOE facilities. Progress report, March--May 1994  

SciTech Connect (OSTI)

The project described in this report was the result of a Memorandum of Cooperation between the US and the former-USSR following the accident at the Chernobyl Nuclear Power Plant Unit 4. A joint program was established to improve the safety of nuclear power plants and to understand the implications of environmental releases. The task of Working Group 7 was ``to develop jointly methods to project rapidly the health effects of any future nuclear reactor accident.`` The current objective of this project is to evaluate and validate pathway-assessment models applicable to exposure and dose reconstruction at DOE facilities through use of international data sets. This project incorporates data used for the prediction of radionuclide transfer through agricultural and aquatic systems to humans. It also includes participation in two multinational studies, BIOMOVS (Biospheric Model Validation Study) with the Swedish National Institute for Radiation Protection and VAMP (Validation of Model Predictions) with the International Atomic Energy Agency, that address testing the performance of models of radionuclide transport through foodchains. In the future, this project will be considered separately from the Chernobyl Studies Project and the essential activities of former Task 7.1D will be folded within the broader umbrella of the BIOMOVS and VAMP projects. The Working Group Leader of Task 7.1D will continue to provide oversight for this project.

Anspaugh, L.R.; Hendrickson, S.M. [eds.] [Lawrence Livermore National Lab., CA (United States); Hoffman, F.O. [Senes Oak Ridge, Inc., TN (United States). Center for Risk Analysis

1994-06-01T23:59:59.000Z

356

COMPLETION OF THE TRANSURANIC GREATER CONFINEMENT DISPOSAL BOREHOLE PERFORMANCE ASSESSMENT FOR THE NEVADA TEST SITE  

SciTech Connect (OSTI)

Classified transuranic material that cannot be shipped to the Waste Isolation Pilot Plant in New Mexico is stored in Greater Confinement Disposal boreholes in the Area 5 Radioactive Waste Management Site on the Nevada Test Site. A performance assessment was completed for the transuranic inventory in the boreholes and submitted to the Transuranic Waste Disposal Federal Review Group. The performance assessment was prepared by Sandia National Laboratories on behalf of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office using an iterative methodology that assessed radiological releases from the intermediate depth disposal configuration against the regulatory requirements of the 1985 version of 40 CFR 191 of the U.S. Environmental Protection Agency. The transuranic materials are stored at 21 to 37 m depth (70 to 120 ft) in large diameter boreholes constructed in the unsaturated alluvial deposits of Frenchman Flat. Hydrologic processes that affect long- term isolation of the radionuclides are dominated by extremely slow upward rates of liquid/vapor advection and diffusion; there is no downward pathway under current climatic conditions and there is no recharge to groundwater under future ''glacial'' climatic conditions. A Federal Review Team appointed by the Transuranic Waste Disposal Federal Review Group reviewed the Greater Confinement Disposal performance assessment and found that the site met the majority of the regulatory criteria of the 1985 and portions of the 1993 versions of 40 CFR 191. A number of technical and procedural issues required development of supplemental information that was incorporated into a final revision of the performance assessment. These issues include inclusion of radiological releases into the complementary cumulative distribution function for the containment requirements associated with drill cuttings from inadvertent human intrusion, verification of mathematical models used in the performance assessment, inclusion of dose calculations from collocated low-level waste in the boreholes for the individual protection requirements, further assessments of engineered barriers and conditions associated with the assurance requirements, and expansion of documentation provided for assessing the groundwater protection requirements. The Transuranic Waste Disposal Federal Review Group approved the performance assessment for Greater Confinement Disposal boreholes in 2001 and did not approve the Application of the Assurance Requirements. Remaining issues concerned with engineered barriers and the multiple aspects of the Assurance Requirements will be resolved at the time of closure of the Area 5 Radioactive Waste Management Site. This is the first completion and acceptance of a performance assessment for transuranic materials under the U.S. Department of Energy self-regulation. The Greater Confinement Disposal boreholes are only the second waste disposal configuration to meet the safety regulatory requirements of 40 CFR 191.

Colarusso, Angela; Crowe, Bruce; Cochran, John R.

2003-02-27T23:59:59.000Z

357

Performance Assessment Analyses Unique to Department of Energy Spent Nuclear Fuel  

SciTech Connect (OSTI)

This paper describes the iterative process of grouping and performance assessment that has led to the current grouping of the U.S. Department of Energy (DOE) spent nuclear fuel (SNF). The unique sensitivity analyses that form the basis for incorporating DOE fuel into the total system performance assessment (TSPA) base case model are described. In addition, the chemistry that results from dissolution of DOE fuel and high level waste (HLW) glass in a failed co-disposal package, and the effects of disposal of selected DOE SNF in high integrity cans are presented.

Loo, Henry Hung Yiu; Duguid, J. O.

2000-06-01T23:59:59.000Z

358

In-Situ Testing and Performance Assessment of a Redesigned WIPP Panel Closure - 13192  

SciTech Connect (OSTI)

There are two primary regulatory requirements for Panel Closures at the Waste Isolation Pilot Plant (WIPP), the nation's only deep geologic repository for defense related Transuranic (TRU) and Mixed TRU waste. The Federal requirement is through 40 CFR 191 and 194, promulgated by the U.S. Environmental Protection Agency (EPA). The state requirement is regulated through the authority of the Secretary of the New Mexico Environment Department (NMED) under the New Mexico Hazardous Waste Act (HWA), New Mexico Statutes Annotated (NMSA) 1978, chap. 74-4-1 through 74-4-14, in accordance with the New Mexico Hazardous Waste Management Regulations (HWMR), 20.4.1 New Mexico Annotated Code (NMAC). The state regulations are implemented for the operational period of waste emplacement plus 30 years whereas the federal requirements are implemented from the operational period through 10,000 years. The 10,000 year federal requirement is related to the adequate representation of the panel closures in determining long-term performance of the repository. In Condition 1 of the Final Certification Rulemaking for 40 CFR Part 194, the EPA required a specific design for the panel closure system. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) has requested, through the Planned Change Request (PCR) process, that the EPA modify Condition 1 via its rulemaking process. The DOE has also requested, through the Permit Modification Request (PMR) process, that the NMED modify the approved panel closure system specified in Permit Attachment G1. The WIPP facility is carved out of a bedded salt formation 655 meters below the surface of southeast New Mexico. Condition 1 of the Final Certification Rulemaking specifies that the waste panels be closed using Option D which is a combination of a Salado mass concrete (SMC) monolith and an isolation/explosion block wall. The Option D design was also accepted as the panel closure of choice by the NMED. After twelve years of waste handling operations and a greater understanding of the waste and the behavior of the underground salt formation, the DOE has established a revised panel closure design. This revised design meets both the short-term NMED Permit requirements for the operational period, and also the Federal requirements for long-term repository performance. This new design is simpler, easier to construct and has less of an adverse impact on waste disposal operations than the originally approved Option D design. The Panel Closure Redesign is based on: (1) the results of in-situ constructability testing performed to determine run-of-mine salt reconsolidation parameters and how the characteristics of the bedded salt formation affect these parameters and, (2) the results of air flow analysis of the new design to determine that the limit for the migration of Volatile Organic Compounds (VOCs) will be met at the compliance point. Waste panel closures comprise a repository feature that has been represented in WIPP performance assessment (PA) since the original Compliance Certification Application of 1996. Panel closures are included in WIPP PA models principally because they are a part of the disposal system, not because they play a substantive role in inhibiting the release of radionuclides to the outside environment. The 1998 rulemaking that certified WIPP to receive transuranic waste placed conditions on the panel closure design to be implemented in the repository. The revised panel closure design, termed the Run-of-Mine (ROM) Panel Closure System (ROMPCS), is comprised of 30.48 meters of ROM salt with barriers at each end. The ROM salt is generated from ongoing mining operations at the WIPP and may be compacted and/or moistened as it is emplaced in a panel entry. The barriers consist of bulkheads, similar to those currently used in the panels as room closures. A WIPP performance assessment has been completed that incorporates the ROMPCS design into the representation of the repository, and compares repository performance to that achieved with the approved Option D design. Several key physical process

Klein, Thomas [URS-Professional Solutions, 4021 National Parks Highway Carlsbad, NM 88220 (United States)] [URS-Professional Solutions, 4021 National Parks Highway Carlsbad, NM 88220 (United States); Patterson, Russell [Department of Energy-Carlsbad Field Office, 4021 National Parks Highway Carlsbad, NM 88220 (United States)] [Department of Energy-Carlsbad Field Office, 4021 National Parks Highway Carlsbad, NM 88220 (United States); Camphouse, Chris; Herrick, Courtney; Kirchner, Thomas; Malama, Bwalya; Zeitler, Todd [Sandia National Laboratories-Carlsbad, 4100 National Parks Highway Carlsbad, NM 88220 (United States)] [Sandia National Laboratories-Carlsbad, 4100 National Parks Highway Carlsbad, NM 88220 (United States); Kicker, Dwayne [SM Stoller Corporation-Carlsbad, 4100 National Parks Highway Carlsbad, NM (United States)] [SM Stoller Corporation-Carlsbad, 4100 National Parks Highway Carlsbad, NM (United States)

2013-07-01T23:59:59.000Z

359

Facility Safeguardability Assessment Report  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77Nuclear SecurityFAPAC-NM | NationalFY

360

Environmental Assessment for the Strategic Petroleum Reserve West Hackberry Facility Raw Water Intake Pipeline Replacement Cameron and Calcasieu Parishes, Louisiana  

SciTech Connect (OSTI)

The proposed action and three alternatives, including a No Build alternative, were evaluated along the existing RWIPL alignment to accommodate the placement of the proposed RWIPL. Construction feasibility, reasonableness and potential environmental impacts were considered during the evaluation of the four actions (and action alternatives) for the proposed RWIPL activities. Reasonable actions were identified as those actions which were considered to be supported by common sense and sound technical principles. Feasible actions were those actions which were considered to be capable of being accomplished, practicable and non-excessive in terms of cost. The evaluation process considered the following design specifications, which were determined to be important to the feasibility of the overall project. The proposed RWIPL replacement project must therefore: (1) Comply with the existing design basis and criteria, (2) Maintain continuity of operation of the facility during construction, (3)Provide the required service life, (4) Be cost effective, (5)Improve the operation and maintenance of the pipeline, and (6) Maintain minimal environmental impact while meeting the performance requirements. Sizing of the pipe, piping construction materials, construction method (e.g., open-cut trench, directional drilling, etc.) and the acquisition of new Right-of-Way (ROW) were additionally evaluated in the preliminary alternative identification, selection and screening process.

N /A

2004-08-31T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Strategies for Assessment of the Biological Performance and Design of Hydroturbines  

SciTech Connect (OSTI)

The biological response of fish to turbine passage has been of concern for several decades and emphasized recently by consideration of hydro as a 'green' power source. The current state-of-the-art of hydro-turbine biological performance assessment, while still inadequate, has advanced considerably the past 10 years. For example, the importance of assessment of exposure to pressure changes during turbine passage has been emphasized by findings of laboratory studies of rapid decompression. It is now very clear that hydroturbine biological assessment must consider the physiological state and behavior of fish at turbine entry and changes in physiological state that drive aspects of behavior during tailrace passage. Such considerations are in addition to concerns about exposure of fish to mechanical and pressure sources of injury during turbine passage. Experimental designs and assessment tools have evolved for acclimation of test fish, observation of test fish behavior at approach and upon exit from the turbine environment, and precise estimation of turbine passage mortality. Fish condition assessment continues to improve permitting better classification of observed injuries to injury mechanisms. Computational fluid dynamics (CFD) models and other computer models permit detailed investigation of the turbine passage environment and development of hypotheses that can be tested in field studies using live fish. Risk assessment techniques permit synthesis of laboratory and in-field study findings and estimation of population level effects over a wide range of turbine operation scenarios. Risk assessment is also evolving to provide input to turbine runner design. These developments, and others, have resulted in more productive biological performance assessment studies and will continue to evolve and improve the quantity and quality of information obtained from costly live fish hydroturbine passage studies. This paper reviews the history of hydro-turbine biological assessment, presents the current state-of-the-art, and identify areas needing improvement.

Carlson, Thomas J.; Richmond, Marshall C.

2011-05-05T23:59:59.000Z

362

Performing Energy Security Assessments - A How-To Guide for Federal  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department ofT ib l L d F SSalesOE0000652Grow YourPerformanceFacility Managers | Department

363

Automated Performance Assessment for Service-Oriented Middleware: a Case Study on BPEL Engines  

E-Print Network [OSTI]

Automated Performance Assessment for Service-Oriented Middleware: a Case Study on BPEL Engines Middleware for Web service compositions, such as BPEL engines, provides the execution environment of service-oriented middleware components. From an engineer- ing point of view, one of the key activities

Binder, Walter

364

Methodology for assessing system performance loss within a proactive maintenance framework  

E-Print Network [OSTI]

role, the practices are required to move from corrective maintenance to preventive and even proactiveMethodology for assessing system performance loss within a proactive maintenance framework P,alexandre.voisin,eric.levrat,benoit.iung}@cran.uhp-nancy.fr) Abstract: Maintenance plays now a critical role

Boyer, Edmond

365

A Method for Impact Assessment of Faults on the Performance of Field-Oriented Control Drives  

E-Print Network [OSTI]

, reliability of a motor drive can be explored via the emerging field of thermo- electrical analysis [3A Method for Impact Assessment of Faults on the Performance of Field-Oriented Control Drives Grainger Center for Electric Machinery and Electromechanics Department of Electrical and Computer

Liberzon, Daniel

366

POST-EPS WINDSCATTEROMETER CONCEPT TRADE-OFFS AND WIND RETRIEVAL PERFORMANCE ASSESSMENT  

E-Print Network [OSTI]

POST-EPS WINDSCATTEROMETER CONCEPT TRADE-OFFS AND WIND RETRIEVAL PERFORMANCE ASSESSMENT C.C. Lin1 GK De Bilt, The Netherlands Abstract The Post-EPS (or EPS-Second Generation) mission will be deployed in the 2018 ­ 2020 timeframe in order to ensure continuity of the EUMETSAT Polar System (EPS) observation

Haak, Hein

367

Attack Injection for Performance and Dependability Assessment of Ad hoc Networks  

E-Print Network [OSTI]

Attack Injection for Performance and Dependability Assessment of Ad hoc Networks Jes´us Friginal, ddandres, pgil}@disca.upv.es Abstract Ad hoc networks are wireless, self-configuring and self- maintaining in this domain has been based on simulation, thus obviating aspects influencing the behav- ior of real ad hoc

Paris-Sud XI, Université de

368

Total System Performance Assessment, 1993: An evaluation of the potential Yucca Mountain repository  

SciTech Connect (OSTI)

Total System Performance Assessments are an important component in the evaluation of the suitability of Yucca Mountain, Nevada as a potential site for a mined geologic repository for the permanent disposal of high-level radioactive wastes in the United States. The Total System Performance Assessments are conducted iteratively during site characterization to identify issues which should be addressed by the characterization and design activities as well as providing input to regulatory/licensing and programmatic decisions. During fiscal years 1991 and 1992, the first iteration of Total System Performance Assessment (hereafter referred to as TSPA 1991) was completed by Sandia National Laboratories and Pacific Northwest Laboratory. Beginning in fiscal year 1993, the Civilian Radioactive Waste Management System Management and Operating Contractor was assigned the responsibility to plan, coordinate, and contribute to the second iteration of Total System Performance Assessment (hereafter referred to as TSPA 1993). This document presents the objectives, approach, assumptions, input, results, conclusions, and recommendations associated with the Management and Operating Contractor contribution to TSPA 1993. The new information incorporated in TSPA 1993 includes (1) revised estimates of radionuclide solubilities (and their thermal and geochemical dependency), (2) thermal and geochemical dependency of spent fuel waste alteration and glass dissolution rates, (3) new distribution coefficient (k{sub d}) estimates, (4) revised estimates of gas-phase velocities and travel times, and (5) revised hydrologic modeling of the saturated zone which provides updated estimates of the advective flux through the saturated zone.

Andrews, R.W.; Dale, T.F.; McNeish, J.A.

1994-03-01T23:59:59.000Z

369

Hydrodynamic Modeling, Optimization and Performance Assessment for Ducted and Non-ducted Tidal Turbines  

E-Print Network [OSTI]

Turbines by Michael Robert Shives B.Eng., Carleton University, 2008 A Thesis Submitted in Partial Hydrodynamic Modeling, Optimization and Performance Assessment for Ducted and Non-ducted Tidal Turbines examines methods for designing and analyzing kinetic turbines based on blade element momentum (BEM) theory

Victoria, University of

370

Hydrodynamic Modeling, Optimization and Performance Assessment for Ducted and Non-ducted Tidal Turbines  

E-Print Network [OSTI]

Turbines by Michael Robert Shives B.Eng., Carleton University, 2008 A Dissertation Submitted in Partial Hydrodynamic Modeling, Optimization and Performance Assessment for Ducted and Non-ducted Tidal Turbines) #12;iii ABSTRACT This thesis examines methods for designing and analyzing kinetic turbines based

Pedersen, Tom

371

Fusion Engineering and Design 80 (2006) 99110 Nuclear performance assessment of ARIES-AT  

E-Print Network [OSTI]

Fusion Engineering and Design 80 (2006) 99­110 Nuclear performance assessment of ARIES-AT L.A. El-Guebaly, The ARIES Team Fusion Technology Institute, University of Wisconsin-Madison, 1500 Engineering Drive, Madison ARIES design always involves a significant change in the engineering system with emphasis on high

California at San Diego, University of

372

Comprehensive Self-Assessment and Upgrade Program (CSAUP) performance objectives and criteria  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has placed strong emphasis on a new way of doing business patterned on the lessons learned in the nuclear power industry after the accident at Three Mile Island Unit 2. The new way relies on strict adherence to policies and procedures, a greatly expanded training program, and much more rigor and formality in operations. Another key element is more visible oversight by upper management and auditability by DOE. Although the Chemical Technology Division (Chem Tech) has functioned in a safe manner since its beginning, the policies and methods of the past are no longer appropriate. Therefore, in accordance with these directives, Chem Tech is improving its operational performance by making a transition to greater formality in the observance of policies and procedures and a more deliberate consideration of the interrelationships between organizations at ORNL. This transition to formality is vitally important because both our staff and our facilities are changing with time. For example, some of the inventors and developers of the processes and facilities in use are now passing the torch'' to the next generation of Chem Tech staff. Our facilities have also served us well for many years, but the newest of these are now over 20 years old All have increasing needs of refurbishment and repair, and some of the older ones need to be replaced. This procedure, based on the lessons learned in the nuclear industry, will enhance Chem Tech's operational performance in some important ways, while maintaining the special factors that have allowed the Chem Tech staff to be creative and successful in the RD D activities.

Not Available

1990-05-01T23:59:59.000Z

373

Uncertainty and Sensitivity Analysis in Performance Assessment for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is under development by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. This development has been supported by a sequence of performance assessments (PAs) carried out by Sandla National Laboratories (SNL) to assess what is known about the WIPP and to provide .tidance for future DOE research and development activities. Uncertainty and sensitivity analysis procedures based on Latin hypercube sampling and regression techniques play an important role in these PAs by providing an assessment of the uncertainty in important analysis outcomes and identi~ing the sources of thk uncertainty. Performance assessments for the WIPP are conceptually and computational] y interesting due to regulatory requirements to assess and display the effects of both stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, where stochastic uncertainty arises from the possible disruptions that could occur over the 10,000 yr regulatory period associated with the WIPP and subjective uncertainty arises from an inability to unambi-aously characterize the many models and associated parameters required in a PA for the WIPP. The interplay between uncertainty analysis, sensitivity analysis, stochastic uncertainty and subjective uncertainty are discussed and illustrated in the context of a recent PA carried out by SNL to support an application by the DOE to the U.S. Environmental Protection Agency for the certification of the WIPP for the disposal of TRU waste.

Helton, J.C.

1998-12-17T23:59:59.000Z

374

CRAD, Facility Safety- Nuclear Facility Safety Basis  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

375

Facility effluent monitoring plan for 242-A evaporator facility  

SciTech Connect (OSTI)

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

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

1995-02-01T23:59:59.000Z

376

Facility effluent monitoring plan for WESF  

SciTech Connect (OSTI)

The FEMP for the Waste Encapsulation and Storage Facility (WESF) provides sufficient information on the WESF effluent characteristics and the effluent monitoring systems so that a compliance assessment against applicable requirements may be performed. Radioactive and hazardous material source terms are related to specific effluent streams that are in turn, related to discharge points and, finally are compared to the effluent monitoring system capability.

SIMMONS, F.M.

1999-09-01T23:59:59.000Z

377

Review and perspectives on spallings release models in the 1996 performance assessment for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant was licensed for disposal of transuranic wastes generated by the US Department of Energy. The facility consists of a repository mined in a bedded salt formation, approximately 650 m below the surface. Regulations promulgated by the US Environmental Protection Agency require that performance assessment calculations for the repository include the possibility that an exploratory drilling operation could penetrate the waste disposal areas at some time in the future. Release of contaminated solids could reach the surface during a drilling intrusion. One of the mechanisms for release, known as spallings, can occur if gas pressures in the repository exceed the hydrostatic pressure of a column of drilling mud. Calculation of solids releases for spallings depends critically on the conceptual models for the waste, for the spallings process, and assumptions regarding driller parameters and practices. The paper presents a review of the evolution of these models during regulatory review of the Compliance Certification Application for the repository. A summary and perspectives on the implementation of conservative assumptions in model development are also provided.

Knowles, M.K; Hansen, F.D.; Thompson, T.W.; Schatz, J.F.; Gross, M.

2000-05-22T23:59:59.000Z

378

Thermal hydraulic performance testing of printed circuit heat exchangers in a high-temperature helium test facility  

SciTech Connect (OSTI)

In high-temperature gas-cooled reactors, such as a very high temperature reactor (VHTR), an intermediate heat exchanger (IHX) is required to efficiently transfer the core thermal output to a secondary fluid for electricity generation with an indirect power cycle and/or process heat applications. Currently, there is no proven high-temperature (750–800 °C or higher) compact heat exchanger technology for high-temperature reactor design concepts. In this study, printed circuit heat exchanger (PCHE), a potential IHX concept for high-temperature applications, has been investigated for their heat transfer and pressure drop characteristics under high operating temperatures and pressures. Two PCHEs, each having 10 hot and 10 cold plates with 12 channels (semicircular cross-section) in each plate are fabricated using Alloy 617 plates and tested for their performance in a high-temperature helium test facility (HTHF). The PCHE inlet temperature and pressure were varied from 85 to 390 °C/1.0–2.7 MPa for the cold side and 208–790 °C/1.0–2.7 MPa for the hot side, respectively, while the mass flow rate of helium was varied from 15 to 49 kg/h. This range of mass flow rates corresponds to PCHE channel Reynolds numbers of 950 to 4100 for the cold side and 900 to 3900 for the hot side (corresponding to the laminar and laminar-to-turbulent transition flow regimes). The obtained experimental data have been analyzed for the pressure drop and heat transfer characteristics of the heat transfer surface of the PCHEs and compared with the available models and correlations in the literature. In addition, a numerical treatment of hydrodynamically developing and hydrodynamically fully-developed laminar flow through a semicircular duct is presented. Relations developed for determining the hydrodynamic entrance length in a semicircular duct and the friction factor (or pressure drop) in the hydrodynamic entry length region for laminar flow through a semicircular duct are given. Various hydrodynamic entrance region parameters, such as incremental pressure drop number, apparent Fanning friction factor, and hydrodynamic entrance length in a semicircular duct have been numerically estimated.

Sai K. Mylavarapu; Xiaodong Sun; Richard E. Glosup; Richard N. Christensen; Michael W. Patterson

2014-04-01T23:59:59.000Z

379

1993 Annual performance report for Environmental Oversight and Monitoring at Department of Energy facilities in New Mexico  

SciTech Connect (OSTI)

In October of 1990, the New Mexico Environment Department entered into an agreement with the US Department of Energy (DOE) to create the Department of Energy Oversight and Monitoring Program. This program is designed to create an avenue for the State to ensure DOE facilities are in compliance with applicable environmental regulations, to allow the State oversight and monitoring independent of the DOE, to allow the State valuable input into remediation decision making, and to protect the environment and the public health and safety of New Mexicans concerning DOE facility activities. This agreement, called the Agreement in Principle (AIP), includes all four of New Mexico`s DOE facilities: Los Alamos National Laboratory in Los Alamos; Sandia National Laboratories and the Inhalation Toxicology Research Institute on Kirtland Air Force Base in Albuquerque; and the Waste Isolation Pilot Plant near Carlsbad.

Not Available

1993-12-31T23:59:59.000Z

380

High Pressure Water Jet System Performance Assessment Project A-2A  

SciTech Connect (OSTI)

Performance assessment for canister cleaning system in the KE Basin. Information obtained from this assessment will be used to design any additional equipment used to clean canisters. After thorough review of the design, maintenance history and operational characteristics of the 105 K East (KE) canister cleaning system, Bartlett recommends that the high pressure water jet system (HPWJS) be modified as outlined in section 5.0, and retained for future use. Further, it is recommended that Spent Nuclear Fuel (SNF) Project consider use of a graded approach for canister cleaning, based on individual canister type and characteristics. This approach would allow a simple method to be used on canisters not needing the more rigorous, high-pressure method. Justification is provided in section 5.0. Although Bartlett has provided some preliminary cost estimates, it is recommended that SNF Project perform a detailed cost-benefit analysis to weigh the alternatives presented.

FARWICK, C.C.

1999-12-03T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Log quality enhancement: A systematic assessment of logging company wellsite performance and log quality  

SciTech Connect (OSTI)

To improve the monitoring of logging company performance, computer programs were developed to assess information en masse from log quality check lists completed on wellsite by the service company engineer and Phillips representative. A study of all logging jobs performed by different service companies for Phillips in Oklahoma (panhandle excepted) during 1982 enabled several pertinent and beneficial interpretations to be made. Company A provided the best tool and crew service. Company B incurred an excessive amount of lost time related to tool failure, in particular the neutron-density tool combination. Company C, although used only three times, incurred no lost time. With a reasonable data base valid conclusions were made pertaining, for example, to repeated tool malfunctions. The actual logs were then assessed for quality.

Farnan, R.A.; Mc Hattie, C.M.

1984-01-01T23:59:59.000Z

382

Implementing an Energy Management System at TOTAL Prot Arthur Refinery: The process to improving and sustaining energy efficiency performance at a facility.  

E-Print Network [OSTI]

PROPRIETARY INFORMATION? 2011 KBC Advanced Technologies plc. All Rights Reserved. Implementing an Energy Management System at TOTAL Port Arthur Refinery: The process to improving and sustaining energy efficiency performance at a facility May... Improvements ? Cost-savings initiatives ? Increasing environmental awareness ? Increasing throughput by debottlenecking processes ? Increasing government mandates 2May 2013 Energy Costs for a 200kBPD Complex refinery Typically, energy efficiency programs...

Hoyle, A.

2013-01-01T23:59:59.000Z

383

Performance Assessment Modeling and Sensitivity Analyses of Generic Disposal System Concepts.  

SciTech Connect (OSTI)

directly, rather than through simplified abstractions. It also a llows for complex representations of the source term, e.g., the explicit representation of many individual waste packages (i.e., meter - scale detail of an entire waste emplacement drift). This report fulfills the Generic Disposal System Analysis Work Packa ge Level 3 Milestone - Performance Assessment Modeling and Sensitivity Analyses of Generic Disposal System Concepts (M 3 FT - 1 4 SN08080 3 2 ).

Sevougian, S. David; Freeze, Geoffrey A. [Sandia National Laboratories, Albuquerque, NM; Gardner, William Payton [Sandia National Laboratories, Albuquerque, NM; Hammond, Glenn Edward [Sandia National Laboratories, Albuquerque, NM; Mariner, Paul [Sandia National Laboratories, Albuquerque, NM

2014-09-01T23:59:59.000Z

384

Compilation of Quality Assurance Documentation for Analyses Performed for the Resumption of Transient Testing Environmental Assessment  

SciTech Connect (OSTI)

This is a companion document to the analyses performed in support of the environmental assessment for the Resumption of Transient Fuels and Materials Testing. It is provided to allow transparency of the supporting calculations. It provides computer code input and output. The basis for the calculations is documented separately in INL (2013) and is referenced, as appropriate. Spreadsheets used to manipulate the code output are not provided.

Annette L. Schafer; A. Jeffrey Sondrup

2013-11-01T23:59:59.000Z

385

Existing Facilities Program  

Broader source: Energy.gov [DOE]

The NYSERDA Existing Facilities program merges the former Peak Load Reduction and Enhanced Commercial and Industrial Performance programs. The new program offers a broad array of different...

386

A method for the assessment of site-specific economic impacts of commercial and industrial biomass energy facilities. A handbook and computer model  

SciTech Connect (OSTI)

A handbook on ``A Method for the Assessment of Site-specific Econoomic Impacts of Industrial and Commercial Biomass Energy Facilities`` has been prepared by Resource Systems Group Inc. under contract to the Southeastern Regional Biomass Energy Program (SERBEP). The handbook includes a user-friendly Lotus 123 spreadsheet which calculates the economic impacts of biomass energy facilities. The analysis uses a hybrid approach, combining direct site-specific data provided by the user, with indirect impact multipliers from the US Forest Service IMPLAN input/output model for each state. Direct economic impacts are determined primarily from site-specific data and indirect impacts are determined from the IMPLAN multipliers. The economic impacts are given in terms of income, employment, and state and federal taxes generated directly by the specific facility and by the indirect economic activity associated with each project. A worksheet is provided which guides the user in identifying and entering the appropriate financial data on the plant to be evaluated. The WLAN multipliers for each state are included in a database within the program. The multipliers are applied automatically after the user has entered the site-specific data and the state in which the facility is located. Output from the analysis includes a summary of direct and indirect income, employment and taxes. Case studies of large and small wood energy facilities and an ethanol plant are provided as examples to demonstrate the method. Although the handbook and program are intended for use by those with no previous experience in economic impact analysis, suggestions are given for the more experienced user who may wish to modify the analysis techniques.

Not Available

1994-10-01T23:59:59.000Z

387

Environmental assessment operation of the HB-Line facility and frame waste recovery process for production of Pu-238 oxide at the Savannah River Site  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0948, addressing future operations of the HB-Line facility and the Frame Waste Recovery process at the Savannah River Site (SRS), near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, DOE has concluded that, the preparation of an environmental impact statement is not required, and is issuing this Finding of No Significant Impact.

NONE

1995-04-01T23:59:59.000Z

388

SUMO, System performance assessment for a high-level nuclear waste repository: Mathematical models  

SciTech Connect (OSTI)

Following completion of the preliminary risk assessment of the potential Yucca Mountain Site by Pacific Northwest Laboratory (PNL) in 1988, the Office of Civilian Radioactive Waste Management (OCRWM) of the US Department of Energy (DOE) requested the Performance Assessment Scientific Support (PASS) Program at PNL to develop an integrated system model and computer code that provides performance and risk assessment analysis capabilities for a potential high-level nuclear waste repository. The system model that has been developed addresses the cumulative radionuclide release criteria established by the US Environmental Protection Agency (EPA) and estimates population risks in terms of dose to humans. The system model embodied in the SUMO (System Unsaturated Model) code will also allow benchmarking of other models being developed for the Yucca Mountain Project. The system model has three natural divisions: (1) source term, (2) far-field transport, and (3) dose to humans. This document gives a detailed description of the mathematics of each of these three divisions. Each of the governing equations employed is based on modeling assumptions that are widely accepted within the scientific community.

Eslinger, P.W.; Miley, T.B.; Engel, D.W.; Chamberlain, P.J. II

1992-09-01T23:59:59.000Z

389

Modeling and Quantification of Team Performance in Human Reliability Analysis for Probabilistic Risk Assessment  

SciTech Connect (OSTI)

Probabilistic Risk Assessment (PRA) and Human Reliability Assessment (HRA) are important technical contributors to the United States (U.S.) Nuclear Regulatory Commission’s (NRC) risk-informed and performance based approach to regulating U.S. commercial nuclear activities. Furthermore, all currently operating commercial NPPs in the U.S. are required by federal regulation to be staffed with crews of operators. Yet, aspects of team performance are underspecified in most HRA methods that are widely used in the nuclear industry. There are a variety of "emergent" team cognition and teamwork errors (e.g., communication errors) that are 1) distinct from individual human errors, and 2) important to understand from a PRA perspective. The lack of robust models or quantification of team performance is an issue that affects the accuracy and validity of HRA methods and models, leading to significant uncertainty in estimating HEPs. This paper describes research that has the objective to model and quantify team dynamics and teamwork within NPP control room crews for risk informed applications, thereby improving the technical basis of HRA, which improves the risk-informed approach the NRC uses to regulate the U.S. commercial nuclear industry.

Jeffrey C. JOe; Ronald L. Boring

2014-06-01T23:59:59.000Z

390

Summary environmental site assessment report for the U.S. Department of Energy Oxnard Facility, Oxnard, California  

SciTech Connect (OSTI)

This report summarizes the investigations conducted by Rust Geotech at the U.S. Department of Energy (DOE) Oxnard facility, 1235 East Wooley Road, Oxnard, California. These investigations were designed to locate, identify, and characterize any regulated contaminated media on the site. The effort included site visits; research of ownership, historical uses of the Oxnard facility and adjacent properties, incidences of and investigations for contaminants on adjacent properties, and the physical setting of the site; sampling and analysis; and reporting. These investigations identified two friable asbestos gaskets on the site, which were removed, and nonfriable asbestos, which will be managed through the implementation of an asbestos management plan. The California primary drinking water standards were exceeded for aluminum on two groundwater samples and for lead in one sample collected from the shallow aquifer underlying the site; remediation of the groundwater in this aquifer is not warranted because it is not used. Treated water is available from a municipal water system. Three sludge samples indicated elevated heavy metals concentrations; the sludge must be handled as a hazardous waste if disposed. Polychlorinated biphenyls (PCBs) were detected at concentrations below remediation criteria in facility soils at two locations. In accordance with U.S. Environmental Protection Agency (EPA) and State of California guidance, remediation of the PCBs is not required. No other hazardous substances were detected in concentrations exceeding regulatory limits.

NONE

1996-02-01T23:59:59.000Z

391

Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the NTS  

SciTech Connect (OSTI)

U.S. Department of Energy (DOE) Manual M 435.1-1 requires that performance assessments (PAs) and composite analyses (CAs) for low-level waste (LLW) disposal facilities be maintained by the field offices. This plan describes the activities performed to maintain the PA and the CA for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). This plan supersedes the Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (DOE/NV/11718--491-REV 1, dated September 2002). The plan is based on U.S. Department of Energy (DOE) Order 435.1 (DOE, 1999a), DOE Manual M 435.1-1 (DOE, 1999b), the DOE M 435.1-1 Implementation Guide DOE G 435.1-1 (DOE, 1999c), and the Maintenance Guide for PAs and CAs (DOE, 1999d). The plan includes a current update on PA/CA documentation, a revised schedule, and a section on Quality Assurance.

Vefa Yucel

2007-01-03T23:59:59.000Z

392

Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 3, Model parameters: Sandia WIPP Project  

SciTech Connect (OSTI)

This volume documents model parameters chosen as of July 1992 that were used by the Performance Assessment Department of Sandia National Laboratories in its 1992 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Ranges and distributions for about 300 modeling parameters in the current secondary data base are presented in tables for the geologic and engineered barriers, global materials (e.g., fluid properties), and agents that act upon the WIPP disposal system such as climate variability and human-intrusion boreholes. The 49 parameters sampled in the 1992 Preliminary Performance Assessment are given special emphasis with tables and graphics that provide insight and sources of data for each parameter.

Not Available

1992-12-29T23:59:59.000Z

393

Finding of No Significant Impact for the Environmental Assessment for the Strategic Petroleum Reserve West Hackberry Facility Raw Water Intake Pipeline Replacement Cameron and Calcasieu Parishes, Louisiana  

SciTech Connect (OSTI)

DOE has prepared an Environmental Assessment (EA), DOE/EA-1497, for the proposed replacement of the existing 107 centimeter (cm) [42 inch (in)] 6.87 kilometer (km) [4.27 mile (mi)] raw water intake pipeline (RWIPL). This action is necessary to allow for continued, optimum operations at the West Hackberry facility (main site/facility). The EA described the proposed action (including action alternatives) and three alternatives to the proposed action. The EA evaluated only the potential environmental consequences of the proposed action (one action alternative), and Alternative 3, which consisted of the No Build Action that is required by 10 CFR 1021.321(c). Based on the analysis in DOE/EA-1497, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting humans or the natural environment within the meaning of the National Environmental Policy Act of 1969 (NEPA), 42 USC 4321 et seq. Therefore, an Environmental Impact Statement (EIS) is not required, and DOE is issuing this Finding of No Significant Impact (FONSI). To further minimize impacts to environmental media, the DOE will also implement a Mitigation Action Plan (MAP) for this action. The MAP is included as Appendix F of this EA, which is appended to this FONSI. The Energy Policy and Conservation Act of 1975 (EPCA), as amended, authorizes the creation of the Strategic Petroleum Reserve (SPR) to store crude oil to reduce the United States' vulnerability to energy supply disruptions. Crude oil is stored in geologic formations, or salt domes, located under these facilities. The purpose of this proposed project is to construct a new RWIPL at the main site to replace the existing RWIPL which services this facility.

N /A

2004-08-31T23:59:59.000Z

394

Radioactive Waste Management Complex low-level waste radiological performance assessment  

SciTech Connect (OSTI)

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01T23:59:59.000Z

395

1992 Annual performance report for Environmental Monitoring and Oversight at Department of Energy facilities in New Mexico  

SciTech Connect (OSTI)

In October 1990 an Agreement-in-Principle (AIP) was entered into between the US Department of Energy (DOE) and the State of New Mexico for the purpose of supporting State oversight activities at DOE facilities in New Mexico. The State`s lead agency for the Agreement is the New Mexico Environment Department (NMED). DOE has agreed to provide the State with resources over a five year period to support State activities in environmental oversight, monitoring, access and emergency response to ensure compliance with applicable federal, state, and local laws at Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), the Waste Isolation Pilot Plant (WIPP), and the Inhalation Toxicology Research Institute (ITRI). The Agreement is designed to assure the citizens of New Mexico that public health, safety and the environment are being protected through existing programs; DOE is in compliance with applicable laws and regulations; DOE has made substantial new commitments; cleanup and compliance activities have been prioritized; and a vigorous program of independent monitoring and oversight by the State is underway. This report relates the quality and effectiveness of the facilities` environmental monitoring and surveillance programs. This report satisfies that requirement for the January--December 1992 time frame.

Not Available

1992-12-31T23:59:59.000Z

396

A methodology for assessing alternative water acquisition and use strategies for energy facilities in the American West  

E-Print Network [OSTI]

This report develops a method for assessing alternative strategies for acquiring and using water at western energy plants. The method has been tested in a case study of cooling water use for a hypothetical steam electric ...

Shaw, John J.

1981-01-01T23:59:59.000Z

397

Performance Assessment of a Desiccant Cooling System in a CHP Application with an IC Engine  

SciTech Connect (OSTI)

Performance of a desiccant cooling system was evaluated in the context of combined heat and power (CHP). The baseline system incorporated a desiccant dehumidifier, a heat exchanger, an indirect evaporative cooler, and a direct evaporative cooler. The desiccant unit was regenerated through heat recovery from a gas-fired reciprocating internal combustion engine. The system offered sufficient sensible and latent cooling capacities for a wide range of climatic conditions, while allowing influx of outside air in excess of what is typically required for commercial buildings. Energy and water efficiencies of the desiccant cooling system were also evaluated and compared with those of a conventional system. The results of parametric assessments revealed the importance of using a heat exchanger for concurrent desiccant post cooling and regeneration air preheating. These functions resulted in enhancement of both the cooling performance and the thermal efficiency, which are essential for fuel utilization improvement. Two approaches for mixing of the return air and outside air were examined, and their impact on the system cooling performance and thermal efficiency was demonstrated. The scope of the parametric analyses also encompassed the impact of improving the indirect evaporative cooling effectiveness on the overall cooling system performance.

Jalalzadeh-Azar, A. A.; Slayzak, S.; Judkoff, R.; Schaffhauser, T.; DeBlasio, R.

2005-04-01T23:59:59.000Z

398

Incorporating long-term climate change in performance assessment for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The United States Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico for the disposal of transuranic wastes generated by defense programs. Applicable regulations (40 CFR 191) require the DOE to evaluate disposal-system performance for 10,000 yr. Climatic changes may affect performance by altering groundwater flow. Paleoclimatic data from southeastern New Mexico and the surrounding area indicate that the wettest and coolest Quaternary climate at the site can be represented by that at the last glacial maximum, when mean annual precipitation was approximately twice that of the present. The hottest and driest climates have been similar to that of the present. The regularity of global glacial cycles during the late Pleistocene confirms that the climate of the last glacial maximum is suitable for use as a cooler and wetter bound for variability during the next 10,000 yr. Climate variability is incorporated into groundwater-flow modeling for WIPP PA by causing hydraulic head in a portion of the model-domain boundary to rise to the ground surface with hypothetical increases in precipitation during the next 10,000 yr. Variability in modeled disposal-system performance introduced by allowing had values to vary over this range is insignificant compared to variability resulting from other causes, including incomplete understanding of transport processes. Preliminary performance assessments suggest that climate variability will not affect regulatory compliance.

Swift, P.N. [Sandia National Labs., Albuquerque, NM (United States); Baker, B.L. [Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States); Economy, K. [Ecodynamics Research Associates, Albuquerque, NM (United States); Garner, J.W. [Applied Physics, Inc., Albuquerque, NM (United States); Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Rudeen, D.K. [New Mexico Engineering Research Institute, Albuquerque, NM (United States)

1994-03-01T23:59:59.000Z

399

The Application of Performance Assessment to Make Regulatory and Operational Changes in an Operating Nuclear Waste Repository  

SciTech Connect (OSTI)

This paper describes how performance assessment (PA) is used to support changes to the regulatory basis of the Waste Isolation Pilot Plant (WIPP). The WIPP, located near Carlsbad, New Mexico is operated by the U.S. Department of Energy (DOE) as the nation's only deep geologic repository for the disposal of transuranic nuclear waste. In 1998, the Environmental Protection Agency (EPA) certified that the WIPP met the performance requirements of 40 CFR Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes. A PA analysis of long term (10,000 year) repository performance successfully demonstrated that the probability and consequences of potential long-term releases of radionuclides to the accessible environment would be well below the established limits. These results were key in obtaining WIPP's initial certification, allowing the first shipment and disposal of nuclear waste in March of 1999. As disposal operations have taken place over the last eight years, changes have been identified in the regulatory and operational realms of the facility that would enhance waste disposal efficiency. Such changes, however, cannot be made without prior consent of the EPA. Therefore, changes planned by the DOE must be thoroughly described and supported by varying degrees of the same type of analyses that were conducted to demonstrate the WIPP's containment capabilities as presented in the initial compliance application submitted to EPA in 1996. Such analyses are used to identify the impacts or benefits of implementing the planned change. The DOE has successfully used performance assessment analyses for the approval of changes such as: 1) the disposal of super-compacted waste forms, and; 2) the adoption of new parameters and modeling assumptions In some cases the planned changes are simpler in nature than those listed above, and therefore only require targeted or simplified PA analyses to demonstrate the effect on performance. Targeted analyses have been used to successfully gain approval of the following: 1) a reduction in the amount of magnesium oxide (MgO) chemical buffer backfill that must be emplaced in the repository 2) a change in the repository mining/disposal horizon In addition to these approved changes, the DOE has used PA analyses to support the following planned change requests that await EPA's approval: 1) panel closure redesign 2) further reduction in the MgO-to-waste ratio Finally, this paper will discuss some of the changes that the DOE is currently preparing and plans to submit to the EPA for approval in the near future. This paper will describe how a set of analytical tools initially used to open the WIPP continues to have a role in making the repository more efficient and adaptable as variations in waste streams, operational demands, and other dynamic forces change the operating environment over time. (authors)

Patterson, R. [Department of Energy, Carlsbad Field Office, Carlsbad, NM (United States); Kirkes, R. [John Hart and Associates, P.A., Albuquerque, NM (United States)

2008-07-01T23:59:59.000Z

400

Risk assessment for the Waste Technologies Industries (WTI) hazardous waste incineration facility (East Liverpool, Ohio). Volume 7. Accident analysis; selection and assessment of potential release scenarios  

SciTech Connect (OSTI)

In this part of the assessment, several accident scenarios are identified that could result in significant releases of chemicals into the environment. These scenarios include ruptures of storage tanks, large magnitude on-site spills, mixing of incompatible wastes, and off-site releases caused by tranpsortation accidents. In evaluating these scenarios, both probability and consequence are assessed, so that likelihood of occurrence is coupled with magnitude of effect in characterizing short term risks.

NONE

1997-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility performance assessments" 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

Direct releases to the surface and associated complementary cumulative distribution functions in the 1996 performance assessment for the Waste Isolation Pilot Plant: Cuttings, cavings and spallings  

SciTech Connect (OSTI)

The following topics related to the treatment of cuttings, cavings and spallings releases to the surface environment in the 1996 performance assessment for the Waste Isolation Pilot Plant (WIPP) are presented: (1) mathematical description of models. (2) uncertainty and sensitivity analysis results arising from subjective (i.e., epistemic) uncertainty for individual releases, (3) construction of complementary cumulative distribution functions (CCDFs) arising from stochastic (i.e., aleatory) uncertainty, and (4) uncertainty and sensitivity analysis results for CCDFs. The presented results indicate that direct releases due to cuttings, cavings and spallings do not constitute a serious threat to the effectiveness of the WIPP as a disposal facility for transuranic waste. Even when the effects of uncertain analysis inputs are taken into account, the CCDFs for cuttings, cavings and spallings releases fall substantially to the left of the boundary line specified in the US Environmental Protection Agency standard for the geologic disposal of radioactive waste (40 CFR 191, 40 CFR 194).

BERGLUND,J.W.; GARNER,J.W.; HELTON,JON CRAIG; JOHNSON,J.D.; SMITH,L.N.; ANDERSON,R.P.

2000-05-22T23:59:59.000Z

402

Direct releases to the surface and associated complementary cumulative distribution functions in the 1996 performance assessments for the Waste Isolation Pilot Plant: Direct brine release  

SciTech Connect (OSTI)

The following topics related to the treatment of direct brine releases to the surface environment in the 1996 performance assessment for the Waste Isolation Pilot Plant (WIPP) are presented (1) mathematical description of models, (2) uncertainty and sensitivity analysis results arising from subjective (i.e., epistemic) uncertainty for individual releases, (3) construction of complementary cumulative distribution functions (CCDFs) arising from stochastic (i.e., aleatory) uncertainty, and (4) uncertainty and sensitivity analysis results for CCDFs. The presented analyses indicate that direct brine releases do not constitute a serious threat to the effectiveness of the WIPP as a disposal facility for transuranic waste. Even when the effects of uncertain analysis inputs are taken into account, the CCDFs for direct brine releases fall substantially to the left of the boundary line specified in the US Environmental Protection Agency's standard for the geologic disposal of radioactive waste (4O CFR 191.40 CFR 194).

STOELZEL,D.M.; O'BRIEN,D.G.; GARNER,J.W.; HELTON,JON CRAIG; JOHNSON,J.D.; SCOTT,L.N.

2000-05-19T23:59:59.000Z

403

Measurement of Exterior Foundation Insulation to Assess Durability in Energy-Saving Performance  

SciTech Connect (OSTI)

The foundation of a house is a sometimes ignored component of the building because of its low visibility. It is increasingly evident, however, that attention to good foundation design and construction significantly benefits the homeowner and the builder by mitigating future problems. Good foundation design and construction practice involves not only insulating to save energy but also providing effective structural design as well as moisture, termite, and radon control techniques as appropriate. Energy efficiency in housing is augmented by use of exterior slab and basement insulation, but high moisture content in the insulation material has led to concerns about its durability. The activity under this task was to extract six different exterior insulation systems that were characterized at installation and have been in the ground for 9 months to 15 years. R-value and moisture content were measured and inspections conducted for evidence of termite intrusion or deterioration. Based on the results, the durability of the various systems has been documented and assessments made of which systems appear to be best practice. Heat flux and temperature measurement data had been archived for some of the exterior insulation tests, thereby providing a unique opportunity to assess energy-saving performance and durability over the long term. The results show that the durability of foundation insulation systems depends on insulation type as well as on foundation type and local boundary conditions, the latter of which may have a marked influence on the durability of energy-saving performance.

Kehrer, Manfred [ORNL; Christian, Jeff [Oak Ridge National Laboratory (ORNL)

2012-04-01T23:59:59.000Z

404

A comparative application of the Repository Integration Program (RIP) to Total System Performance Assessment, 1991  

SciTech Connect (OSTI)

During Fiscal Year (FY) 1991 and FY 1992, Sandia National Laboratory and Battelle Pacific Northwest Laboratory were assigned the responsibility to generate initial Total System Performance Assessments (TSPAs) of the Yucca Mountain site. The analyses performed by these organizations (called TSPA-1991) are reported in Barnard et al(1992) and Eslinger et al. (1993). During this same time period, Golder Associates Inc. was assigned the task of generating a model capable of analyzing the total system performance of a high-level radioactive waste repository. The developed model, called Repository Integration Program (RIP), is documented in Kossik and Hachey (1993), Miller et al. (1993), and Golder Associates Inc. (1993). In FY 1993, the Civilian Radioactive Waste Management System Contractor was assigned the responsibility to plan, coordinate, and contribute to the second iteration of TSPA-2. Prior to initiating the next TSPA iteration, it was decided that it would be valuable to evaluate the applicability of RIP for use in this iteration. Therefore, analyses were conducted to compare the results generated by RIP to those reported in TSPA-1991. In particular, the aim was to generate a RIP input data set as equivalent as possible to that documented in Barnard et al. (1992) and to analyze the total system performance (as well as the performance of the individual subsystem components of the waste package/Engineered Barrier System (EBS), unsaturated gaseous flow and transport, unsaturated aqueous flow and transport, saturated flow and transport, and disruptive processes/events). The performance measure for comparison with the results of TSPA-1991 is the cumulative release of radionuclides to the accessible environment over a 10,000-year period following closure normalized to the US Environmental Protection Agency (EPA) release limits specified in 40 CFR 191.

NONE

1993-07-16T23:59:59.000Z

405

High level waste storage tanks 242-A evaporator S/RID phase II assessment report  

SciTech Connect (OSTI)

This document, the Standards/Requirements Identification Document (S/RID) Phase 2 Assessment Report for the subject facility, represents the results of a Performance Assessment to determine whether procedures containing S/RID requirements are fully implemented by field personnel in the field. It contains a summary report and three attachments; an assessment schedule, performance objectives, and assessments for selected functional areas.

Biebesheimer, E.

1996-09-27T23:59:59.000Z

406

Performance Evaluation of HYCOM-GOM for Hydrokinetic Resource Assessment in the Florida Strait  

SciTech Connect (OSTI)

The U.S. Department of Energy (DoE) is assessing and mapping the potential off-shore ocean current hydrokinetic energy resources along the U.S. coastline, excluding tidal currents, to facilitate market penetration of water power technologies. This resource assessment includes information on the temporal and three-dimensional spatial distribution of the daily averaged power density, and the overall theoretical hydrokinetic energy production, based on modeled historical simulations spanning a 7-year period of record using HYCOM-GOM, an ocean current observation assimilation model that generates a spatially distributed three-dimensional representation of daily averaged horizontal current magnitude and direction time series from which power density time series and their statistics can be derived. This study ascertains the deviation of HYCOM-GOM outputs, including transport (flow) and power density, from outputs based on three independent observation sources to evaluate HYCOM-GOM performance. The three independent data sources include NOAA s submarine cable data of transport, ADCP data at a high power density location, and HF radar data in the high power density region of the Florida Strait. Comparisons with these three independent observation sets indicate discrepancies with HYCOM model outputs, but overall indicate that the HYCOM-GOM model can provide an adequate assessment of the ocean current hydrokinetic resource in high power density regions like the Florida Strait. Additional independent observational data, in particular stationary ADCP measurements, would be useful for expanding this model performance evaluation study. ADCP measurements are rare in ocean environments not influenced by tides, and limited to one location in the Florida Strait. HF radar data, although providing great spatial coverage, is limited to surface currents only.

Neary, Vincent S [ORNL; Gunawan, Budi [ORNL; Ryou, Albert S [ORNL

2012-06-01T23:59:59.000Z

407

Midtemperature solar systems test facility predictions for thermal performance of the Acurex solar collector with FEK 244 reflector surface  

SciTech Connect (OSTI)

Thermal performance predictions are presented for the Acurex solar collector, with FEK 244 reflector surface, for three output temperatures at five cities in the United States.

Harrison, T.D.

1981-01-01T23:59:59.000Z

408

Result Summary for the Area 5 Radioactive Waste Management Site Performance Assessment Model Version 4.113  

SciTech Connect (OSTI)

Preliminary results for Version 4.113 of the Nevada National Security Site Area 5 Radioactive Waste Management Site performance assessment model are summarized. Version 4.113 includes the Fiscal Year 2011 inventory estimate.

Shott, G. J.

2012-04-15T23:59:59.000Z

409

Assessment of the Performance of the Chilbolton 3-GHz Advanced Meteorological Radar for Cloud-Top-Height Retrieval  

E-Print Network [OSTI]

. The potential for this radar to make useful measurements of low-altitude liquid water cloud structure is investigated. To assess the cloud-height assignment capabilities of the 3-GHz radar, low-level cloudAssessment of the Performance of the Chilbolton 3-GHz Advanced Meteorological Radar for Cloud

410

Midtemperature solar systems test facility predictions for thermal performance based on test data: Sun-Heet nontracking solar collector  

SciTech Connect (OSTI)

Sandia National Laboratories, Albuquerque (SNLA), is currently conducting a program to predict the performance and measure the characteristics of commercially available solar collectors that have the potential for use in industrial process heat and enhanced oil recovery applications. The thermal performance predictions for the Sun-Heet nontracking, line-focusing parabolic trough collector at five cities in the US are presented. (WHK)

Harrison, T.D.

1981-03-01T23:59:59.000Z

411

Qualitative and Quantitative Assessment of Nuclear Materials Contained in High-Activity Waste Arising from the Operations at the 'SHELTER' Facility  

SciTech Connect (OSTI)

As a result of the nuclear accident at the Chernobyl NPP in 1986, the explosion dispeesed nuclear materials contained in the nuclear fuel of the reactor core over the destroyed facilities at Unit No. 4 and over the territory immediately adjacent to the destroyed unit. The debris was buried under the Cascade Wall. Nuclear materials at the SHELTER can be characterized as spent nuclear fuel, fresh fuel assemblies (including fuel assemblies with damaged geometry and integrity, and individual fuel elements), core fragments of the Chernobyl NPP Unit No. 4, finely-dispersed fuel (powder/dust), uranium and plutonium compounds in water solutions, and lava-like nuclear fuel-containing masses. The new safe confinement (NSC) is a facility designed to enclose the Chernobyl NPP Unit No. 4 destroyed by the accident. Construction of the NSC involves excavating operations, which are continuously monitored including for the level of radiation. The findings of such monitoring at the SHELTER site will allow us to characterize the recovered radioactive waste. When a process material categorized as high activity waste (HAW) is detected the following HLW management operations should be involved: HLW collection; HLW fragmentation (if appropriate); loading HAW into the primary package KT-0.2; loading the primary package filled with HAW into the transportation cask KTZV-0.2; and storing the cask in temporary storage facilities for high-level solid waste. The CDAS system is a system of 3He tubes for neutron coincidence counting, and is designed to measure the percentage ratio of specific nuclear materials in a 200-liter drum containing nuclear material intermixed with a matrix. The CDAS consists of panels with helium counter tubes and a polyethylene moderator. The panels are configured to allow one to position a waste-containing drum and a drum manipulator. The system operates on the ‘add a source’ basis using a small Cf-252 source to identify irregularities in the matrix during an assay. The platform with the source is placed under the measurement chamber. The platform with the source material is moved under the measurement chamber. The design allows one to move the platform with the source in and out, thus moving the drum. The CDAS system and radioactive waste containers have been built. For each drum filled with waste two individual measurements (passive/active) will be made. This paper briefly describes the work carried out to assess qualitatively and quantitatively the nuclear materials contained in high-level waste at the SHELTER facility. These efforts substantially increased nuclear safety and security at the facility.

Cherkas, Dmytro

2011-10-01T23:59:59.000Z

412

Kennecott Utah Copper Corporation: Facility Utilizes Energy Assessments to Identify $930,000 in Potential Annual Savings  

SciTech Connect (OSTI)

Kennecott Utah Copper Corporation (KUCC) used targeted energy assessments in the smelter and refinery at its Bingham Canyon Mine, near Salt Lake City, Utah. The assessment focused mainly on the energy-intensive processes of copper smelting and refining. By implementing the projects identified, KUCC could realize annual cost savings of $930,000 and annual energy savings of 452,000 MMBtu. The projects would also reduce maintenance, repair costs, waste, and environmental emissions. One project would use methane gas from an adjacent municipal dump to replace natural gas currently used to heat the refinery electrolyte.

Not Available

2004-07-01T23:59:59.000Z

413

Performance Assessment Uncertainty Analysis for Japan's HLW Program Feasibility Study (H12)  

SciTech Connect (OSTI)

Most HLW programs in the world recognize that any estimate of long-term radiological performance must be couched in terms of the uncertainties derived from natural variation, changes through time and lack of knowledge about the essential processes. The Japan Nuclear Cycle Development Institute followed a relatively standard procedure to address two major categories of uncertainty. First, a FEatures, Events and Processes (FEPs) listing, screening and grouping activity was pursued in order to define the range of uncertainty in system processes as well as possible variations in engineering design. A reference and many alternative cases representing various groups of FEPs were defined and individual numerical simulations performed for each to quantify the range of conceptual uncertainty. Second, parameter distributions were developed for the reference case to represent the uncertainty in the strength of these processes, the sequencing of activities and geometric variations. Both point estimates using high and low values for individual parameters as well as a probabilistic analysis were performed to estimate parameter uncertainty. A brief description of the conceptual model uncertainty analysis is presented. This paper focuses on presenting the details of the probabilistic parameter uncertainty assessment.

BABA,T.; ISHIGURO,K.; ISHIHARA,Y.; SAWADA,A.; UMEKI,H.; WAKASUGI,K.; WEBB,ERIK K.

1999-08-30T23:59:59.000Z

414

Performance Assessment of Prediction In Dynamic Environments (PRIDE) in Manufacturing Environments  

SciTech Connect (OSTI)

This paper describes PRIDE (Prediction in Dynamic Environments), a multi-resolution and hierarchical framework. PRIDE was developed as a test bed to assess the performance of autonomous vehicles in the presence of moving objects in a simulated environment. By simulating scenarios in which moving objects are prevalent, a designer of an autonomous vehicle can test the performance of their path planning and collision avoidance algorithms without having to immerse the vehicle in the physical world. This framework supports the prediction of the future location of moving objects at various levels of resolution, thus providing prediction information at the frequency and level of abstraction necessary for planners at different levels within the hierarchy. Previous works have demonstrated the reliability of PRIDE to simulate on-road traffic situations with multiple vehicles. To provide realistic scenarios, PRIDE integrates a level of situation awareness of how other vehicles in the environment are expected to behave considering the situation in which the vehicles find themselves in. In recent efforts, the PRIDE framework has been extended to consider production logistics in dynamic manufacturing environment while focusing on the scheduling of material transportation system. To demonstrate the characteristics of the PRIDE framework, this paper illustrates real-time navigation of Automated Guided Vehicles (AGVs) at different locations in a dynamic manufacturing environment. Moreover, using the high-fidelity physics?based framework for the Unified System for Automation and Robot Simulation (USARSim), this paper analyzes the performance of the PRIDE framework on a set of realistic scenarios.

Kootbally, Zeid [National Institute of Standards and Technology (NIST)] [National Institute of Standards and Technology (NIST); Schlenoff, Craig [National Institute of Standards and Technology (NIST)] [National Institute of Standards and Technology (NIST); Madhavan, Raj [ORNL] [ORNL

2009-01-01T23:59:59.000Z

415

Performance Assessment of Single Electrode-Supported Solid Oxide Cells Operating in the Steam Electrolysis Mode  

SciTech Connect (OSTI)

An experimental study is under way to assess the performance of electrode-supported solid-oxide cells operating in the steam electrolysis mode for hydrogen production. Results presented in this paper were obtained from single cells, with an active area of 16 cm{sup 2} per cell. The electrolysis cells are electrode-supported, with yttria-stabilized zirconia (YSZ) electrolytes ({approx}10 {mu}m thick), nickel-YSZ steam/hydrogen electrodes ({approx}1400 {mu}m thick), and modified LSM or LSCF air-side electrodes ({approx}90 {mu}m thick). The purpose of the present study is to document and compare the performance and degradation rates of these cells in the fuel cell mode and in the electrolysis mode under various operating conditions. Initial performance was documented through a series of voltage-current (VI) sweeps and AC impedance spectroscopy measurements. Degradation was determined through long-term testing, first in the fuel cell mode, then in the electrolysis mode. Results generally indicate accelerated degradation rates in the electrolysis mode compared to the fuel cell mode, possibly due to electrode delamination. The paper also includes details of an improved single-cell test apparatus developed specifically for these experiments.

X. Zhang; J. E. O'Brien; R. C. O'Brien; N. Petigny

2011-11-01T23:59:59.000Z

416

Midtemperature Solar Systems Test Facility Program for predicting thermal performance of line-focusing, concentrating solar collectors  

SciTech Connect (OSTI)

The program at Sandia National Laboratories, Albuquerque, for predicting the performance of line-focusing solar collectors in industrial process heat applications is described. The qualifications of the laboratories selected to do the testing and the procedure for selecting commercial collectors for testing are given. The testing program is outlined. The computer program for performance predictions is described. An error estimate for the predictions and a sample of outputs from the program are included.

Harrison, T.D.

1980-11-01T23:59:59.000Z

417

2008 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses  

SciTech Connect (OSTI)

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs) for each of the facilities, with the results submitted annually to U.S. Department of Energy (DOE) Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan. The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) performed an annual review in fiscal year (FY) 2008 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs. This annual summary report presents data and conclusions from the FY 2008 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

NSTec Environmental Management

2009-03-30T23:59:59.000Z

418

Performance of corrosion inhibiting admixtures for structural concrete -- assessment methods and predictive modeling  

SciTech Connect (OSTI)

During the past fifteen years corrosion inhibiting admixtures (CIAs) have become increasingly popular for protection of reinforced components of highway bridges and other structures from damage induced by chlorides. However, there remains considerable debate about the benefits of CIAs in concrete. A variety of testing methods to assess the performance of CIA have been reported in the literature, ranging from tests in simulated pore solutions to long-term exposures of concrete slabs. The paper reviews the published techniques and recommends the methods which would make up a comprehensive CIA effectiveness testing program. The results of this set of tests would provide the data which can be used to rank the presently commercially available CIA and future candidate formulations utilizing a proposed predictive model. The model is based on relatively short-term laboratory testing and considers several phases of a service life of a structure (corrosion initiation, corrosion propagation without damage, and damage to the structure).

Yunovich, M.; Thompson, N.G. [CC Technologies Labs., Inc., Dublin, OH (United States)

1998-12-31T23:59:59.000Z

419

Characterization of subjective uncertainty in the 1996 performance assessment for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The 1996 performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) maintains a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, with stochastic uncertainty arising from the possible disruptions that could occur at the WIPP over the 10,000 yr regulatory period specified by the US Environmental Protection Agency (40 CFR 191,40 CFR 194) and subjective uncertainty arising from an inability to uniquely characterize many of the inputs required in the 1996 WIPP PA. The characterization of subjective uncertainty is discussed, including assignment of distributions, uncertain variables selected for inclusion in analysis, correlation control, sample size, statistical confidence on mean complementary cumulative distribution functions, generation of Latin hypercube samples, sensitivity analysis techniques, and scenarios involving stochastic and subjective uncertainty.

HELTON,JON CRAIG; MARTELL,MARY-ALENA; TIERNEY,MARTIN S.

2000-05-18T23:59:59.000Z

420

Facile synthesis of novel Ag/AgI/BiOI composites with highly enhanced visible light photocatalytic performances  

SciTech Connect (OSTI)

Novel Ag/AgI/BiOI composites were controllably synthesized via a facile ion-exchange followed by photoreduction strategy by using hierarchical BiOI microflower as substrate. The as-prepared Ag/AgI/BiOI composites were studied by X-ray powder diffractometer (XRD), scanning electron microscopy (SEM), high-resolution transmission electron microscopy (HRTEM), X-ray photoelectron spectroscopy (XPS), Brunauer–Emmett–Teller (BET) surface area analyzer and UV–vis diffuse reflectance spectroscopy (DRS). Under visible light (?>420 nm), Ag/AgI/BiOI displayed highly enhanced photocatalytic activities for degradation of methyl orange (MO) compared to the pure hierarchical BiOI, which was mainly ascribed to the highly efficient separation of electrons and holes through the closely contacted interfaces in the Ag/AgI/BiOI ternary system. - Graphical abstract: Ag/AgI/BiOI displayed excellent photocatalytic activities for methyl orange degradation under visible light, which was mainly ascribed to the highly efficient separation of electrons and holes through Z-scheme pathway. Display Omitted - Highlights: • Novel Ag/AgI/BiOI composites were successfully synthesized. • Ag/AgI/BiOI displayed higher visible light activities than those of pure BiOI and AgI. • ·O{sub 2}{sup ?} and h{sup +}, especially ·O{sub 2}{sup ?}, dominated the photodegradation process of MO. • A Z-scheme pattern was adopted for Ag/AgI/BiOI activity enhancement.

Cao, Jing, E-mail: caojing@mail.ipc.ac.cn [College of Chemistry and Materials Science, Huaibei Normal University, Huaibei 235000, Anhui (China); State Key Laboratory of Crystal Materials, Shandong University, Jinan 250100 (China); Zhao, Yijie; Lin, Haili; Xu, Benyan [College of Chemistry and Materials Science, Huaibei Normal University, Huaibei 235000, Anhui (China); Chen, Shifu, E-mail: chshifu@chnu.edu.cn [College of Chemistry and Materials Science, Huaibei Normal University, Huaibei 235000, Anhui (China)

2013-10-15T23:59:59.000Z

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421

Performance studies of the parallel VIM code  

SciTech Connect (OSTI)

In this paper, we evaluate the performance of the parallel version of the VIM Monte Carlo code on the IBM SPx at the High Performance Computing Research Facility at Argonne National Laboratory. Three test problems with contrasting computational characteristics were used to assess effects in performance. A statistical method for estimating the inefficiencies due to load imbalance and communication is also introduced.

Shi, B.; Blomquist, R.N. [Argonne National Laboratory, IL (United States)

1996-12-31T23:59:59.000Z

422

Assessing the prospects for achieving double-shell ignition on the National Ignition Facility using vacuum hohlraums  

SciTech Connect (OSTI)

The goal of demonstrating ignition on the National Ignition Facility [J. D. Lindl et al., Phys. Plasmas 11, 339 (2003)] has motivated a revisit of double-shell (DS) targets as a complementary path to the cryogenic baseline approach. Expected benefits of DS ignition targets include noncryogenic deuterium-tritium (DT) fuel preparation, minimal hohlraum-plasma-mediated laser backscatter, low threshold-ignition temperatures ({approx_equal}4 keV) for relaxed hohlraum x-ray flux asymmetry tolerances, and minimal (two-) shock timing requirements. On the other hand, DS ignition presents several formidable challenges, encompassing room-temperature containment of high-pressure DT ({approx_equal}790 atm) in the inner shell, strict concentricity requirements on the two shells (<3 {mu}m), development of nanoporous (<100 nm cell size) low-density (<100 mg/cc) metallic foams for structural support of the inner shell and hydrodynamic instability mitigation, and effective control of hydrodynamic instabilities on the high-Atwood-number interface between the DT fuel and the high-Z inner shell. Recent progress in DS ignition designs and required materials science advances at the nanoscale are described herein. Two new ignition designs that use rugby-shaped vacuum hohlraums are presented that utilize either 1 or 2 MJ of laser energy at 3{omega}. The capability of the National Ignition Facility to generate the requested 2 MJ reverse-ramp pulse shape for DS ignition is expected to be comparable to the planned high-contrast ({approx_equal}100) pulse shape at 1.8 MJ for the baseline cryogenic target. Nanocrystalline, high-strength, Au-Cu alloy inner shells are under development using electrochemical deposition over a glass mandrel, exhibiting tensile strengths well in excess of 790 atm. Novel, low-density (85 mg/cc) copper foams have recently been demonstrated using 10 mg/cc SiO{sub 2} nanoporous aerogels with suspended Cu particles. A prototype demonstration of an ignition DS is planned for 2008, incorporating the needed novel nanomaterials science developments and the required fabrication tolerances for a realistic ignition attempt after 2010.

Amendt, Peter; Cerjan, C.; Hamza, A.; Hinkel, D. E.; Milovich, J. L.; Robey, H. F. [Lawrence Livermore National Laboratory, University of California, Livermore, California 94551 (United States)

2007-05-15T23:59:59.000Z