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Sample records for facility investigation plan

  1. Quadrant I RCRA Facility Investigation Work Plan

    International Nuclear Information System (INIS)

    1990-01-01

    The objective of this Facility Investigation (FRI) at the Portsmouth Gaseous Diffusion Plant (PORTS) is to acquire, analyze and interpret data which will: (1) characterize the environmental setting including ground water, surface water and sediment, soil and air; (2) define and characterize sources of contamination; (3) characterize the vertical and horizontal extent and degree of contamination of the environment; (4) assess the risk to human health and the environment resulting from possible exposure to contaminants; and, (5) support the Corrective Measures Study (CMS) which will follow the RFI. Investigations to characterize the environmental setting, sources of contamination, and vertical and horizontal extent and degree of contamination will be conducted relative to individual potential sources which have been identified in the Quadrant I Description of Current Conditions. These unit investigations will follow the systematic approach which is outlined below

  2. Final work plan : investigation of potential contamination at the former USDA facility in Powhattan, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2007-02-02

    This Work Plan outlines the scope of work to be conducted to investigate the subsurface contaminant conditions at the property formerly leased by the Commodity Credit Corporation (CCC) in Powhattan, Kansas (Figure 1.1). Data obtained during this event will be used to (1) evaluate potential contaminant source areas on the property; (2) determine the vertical and horizontal extent of potential contamination; and (3) provide recommendations for future action, with the ultimate goal of assigning this site No Further Action status. The planned investigation includes groundwater monitoring requested by the Kansas Department of Health and Environment (KDHE), in accordance with Section V of the Intergovernmental Agreement between the KDHE and the Farm Service Agency of the U.S. Department of Agriculture (USDA). The work is being performed on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. A nonprofit, multidisciplinary research center operated by the University of Chicago for the U.S. Department of Energy, Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at former CCC/USDA grain storage facilities. Argonne issued a Master Work Plan (Argonne 2002) that has been approved by the KDHE. The Master Work Plan describes the general scope of all investigations at former CCC/USDA facilities in Kansas and provides guidance for these investigations. It should be consulted for the complete details of plans for work associated with the former CCC/USDA facility at Powhattan.

  3. Field Investigation Plan for 1301-N and 1325-N Facilities Sampling to Support Remedial Design

    International Nuclear Information System (INIS)

    Weiss, S. G.

    1998-01-01

    This field investigation plan (FIP) provides for the sampling and analysis activities supporting the remedial design planning for the planned removal action for the 1301-N and 1325-N Liquid Waste Disposal Facilities (LWDFs), which are treatment, storage,and disposal (TSD) units (cribs/trenches). The planned removal action involves excavation, transportation, and disposal of contaminated material at the Environmental Restoration Disposal Facility (ERDF).An engineering study (BHI 1997) was performed to develop and evaluate various options that are predominantly influenced by the volume of high- and low-activity contaminated soil requiring removal. The study recommended that additional sampling be performed to supplement historical data for use in the remedial design

  4. Investigation of development and management of treatment planning systems for BNCT at foreign facilities

    International Nuclear Information System (INIS)

    2001-03-01

    A new computational dosimetry system for BNCT: JCDS is developed by JAERI in order to carry out BNCT with epithermal neutron beam at present. The development and management situation of computational dosimetry system, which are developed and are used in BNCT facilities in foreign countries, were investigated in order to accurately grasp functions necessary for preparation of the treatment planning and its future subjects. In present state, 'SERA', which are developed by Idaho National Engineering and Environmental Laboratory (INEEL), is used in many BNCT facilities. Followings are necessary for development and management of the treatment planning system. (1) Reliability confirmation of system performance by verification as comparison examination of calculated value with actual experimental measured value. (2) Confirmation systems such as periodic maintenance for retention of the system quality. (3) The improvement system, which always considered relative merits and demerits with other computational dosimetry system. (4) The development of integrated system with patient setting. (author)

  5. Hanford Facility contingency plan

    International Nuclear Information System (INIS)

    Sutton, L.N.; Miskho, A.G.; Brunke, R.C.

    1993-10-01

    The Hanford Facility Contingency Plan, together with each TSD unit-specific contingency plan, meets the WAC 173-303 requirements for a contingency plan. This plan includes descriptions of responses to a nonradiological hazardous materials spill or release at Hanford Facility locations not covered by TSD unit-specific contingency plans or building emergency plans. This plan includes descriptions of responses for spills or releases as a result of transportation activities, movement of materials, packaging, and storage of hazardous materials

  6. Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

    Energy Technology Data Exchange (ETDEWEB)

    Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

    1992-12-01

    This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI.

  7. Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

    International Nuclear Information System (INIS)

    Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

    1992-12-01

    This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S ampersand A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S ampersand A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI

  8. Final master work plan : environmental investigations at former CCC/USDA facilities in Kansas, 2002 revision.

    Energy Technology Data Exchange (ETDEWEB)

    Burton, J. C.; Environmental Research

    2003-01-23

    The Commodity Credit Corporation (CCC) of the U.S. Department of Agriculture (USDA) has entered into an interagency agreement with the U.S. Department of Energy (DOE) under which Argonne National Laboratory provides technical assistance for hazardous waste site characterization and remediation for the CCC/USDA. Carbon tetrachloride is the contaminant of primary concern at sites in Kansas where former CCC/USDA grain storage facilities were located. Argonne applies its QuickSite(reg sign) Expedited Site Characterization (ESC) approach to these former facilities. The QuickSite environmental site characterization methodology is Argonne's proprietary implementation of the ESC process (ASTM 1998). Argonne has used this approach at several former CCC/USDA facilities in Kansas, including Agenda, Agra, Everest, and Frankfort. The Argonne ESC approach revolves around a multidisciplinary, team-oriented approach to problem solving. The basic features and steps of the QuickSite methodology are as follows: (1) A team of scientists with diverse expertise and strong field experience is required to make the process work. The Argonne team is composed of geologists, geochemists, geophysicists, hydrogeologists, chemists, biologists, engineers, computer scientists, health and safety personnel, and regulatory staff, as well as technical support staff. Most of the staff scientists are at the Ph.D. level; each has on average, more than 15 years of experience. The technical team works together throughout the process. In other words, the team that plans the program also implements the program in the field and writes the reports. More experienced scientists do not remain in the office while individuals with lesser degrees or experience carry out the field work. (2) The technical team reviews, evaluates, and interprets existing data for the site and the contaminants there to determine which data sets are technically valid and can be used in initially designing the field program. A basic

  9. Horonobe Underground Research Laboratory project. Plans of investigations during shaft and drift excavation (Construction of underground facilities: Phase II)

    International Nuclear Information System (INIS)

    2005-06-01

    Horonobe Underground Research Laboratory Project is planned for over 20 years to establish the scientific and technical basis for the underground disposal of high-level radioactive wastes in Japan. The investigations are conducted by JNC in three phases, from the surface (Phase I), during the construction of the underground facilities (Phase II), and using the facilities (Phase III). This report concerns the investigation plans for Phase II. During excavation of shafts and drifts, detailed geological and borehole investigation will be conducted and the geological model constructed in Phase I is evaluated and revised by newly acquired data of geophysical and geological environment. Detailed in-situ experiments, as well as the effects of shaft excavation, are also done to study long-term changes, rock properties, groundwater flow and chemistry to ensure the reliability of repository technology and establish safety assessment methodology. (S. Ohno)

  10. Comprehensive facilities plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    The Ernest Orlando Lawrence Berkeley National Laboratory`s Comprehensive Facilities Plan (CFP) document provides analysis and policy guidance for the effective use and orderly future development of land and capital assets at the Berkeley Lab site. The CFP directly supports Berkeley Lab`s role as a multiprogram national laboratory operated by the University of California (UC) for the Department of Energy (DOE). The CFP is revised annually on Berkeley Lab`s Facilities Planning Website. Major revisions are consistent with DOE policy and review guidance. Facilities planing is motivated by the need to develop facilities for DOE programmatic needs; to maintain, replace and rehabilitate existing obsolete facilities; to identify sites for anticipated programmatic growth; and to establish a planning framework in recognition of site amenities and the surrounding community. The CFP presents a concise expression of the policy for the future physical development of the Laboratory, based upon anticipated operational needs of research programs and the environmental setting. It is a product of the ongoing planning processes and is a dynamic information source.

  11. RCRA facility investigation/corrective measures study work plan for the 100-DR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations. Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-DR-1 source operable unit Source operable units include facilities and unplanned release sites that are potential sources of contamination

  12. Water quality facility investigation report : final summary of project and evaluation of monitoring plan implementation.

    Science.gov (United States)

    2005-07-05

    The Oregon Department of Transportation (ODOT) has installed several stormwater : treatment facilities throughout the State to improve the quality of runoff discharged from : highways. These facilities include a variety of both above ground and below...

  13. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    International Nuclear Information System (INIS)

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations

  14. RCRA facility investigation/corrective measures study work plan for the 100-HR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US. Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-1 source operable unit. Source operable units include facilities and unplanned release sites that are potential sources of contamination. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Separate work plans have been initiated for the 100-HR-3 groundwater operable unit (DOE-RL 1992a) and the 100-DR-1 (DOE-RL 1992b) source operable units

  15. RCRA facility investigation/corrective measures study work plan for the 100-HR-3 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-3 operable unit. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Source operable units include facilities and unplanned release sites that are potential sources of contamination. Separate work plans have been initiated for the 100-DR-1 (DOE-RL 1992a) and 100-HR-1 (DOE-RL 1992b) source operable units

  16. Final work plan : supplemental upward vapor intrusion investigation at the former CCC/USDA grain storage facility in Hanover, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2008-12-15

    The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride (below the maximum contaminant level [MCL] of 5.0 {micro}g/L) were detected in two private wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In 2007, the CCC/USDA conducted near-surface soil sampling at 61 locations and also sampled indoor air at nine residences on or adjacent to its former Hanover facility to address the residents concerns regarding vapor intrusion. Low levels of carbon tetrachloride were detected at four of the nine homes. The results were submitted to the KDHE in October 2007 (Argonne 2007). On the basis of the results, the KDHE requested sub-slab sampling and/or indoor air sampling (KDHE 2007). This Work Plan describes, in detail, the proposed additional scope of work requested by the KDHE and has been developed as a supplement to the comprehensive site investigation work plan that is pending (Argonne 2008). Indoor air samples collected previously from four homes at Hanover were shown to contain the carbon tetrachloride at low concentrations (Table 2.1). It cannot be concluded from these previous data that the source of the detected carbon tetrachloride is vapor intrusion attributable to former grain storage operations of the CCC/USDA at Hanover. The technical objective of the vapor intrusion investigation described here is to assess the risk to human health due to the potential for upward migration of carbon tetrachloride and

  17. Grout Facilities standby plan

    Energy Technology Data Exchange (ETDEWEB)

    Claghorn, R.D.; Kison, P.F.; Nunamaker, D.R.; Yoakum, A.K.

    1994-09-29

    This plan defines how the Grout Facilities will be deactivated to meet the intent of the recently renegotiated Tri-Party Agreement (TPA). The TPA calls for the use of the grout process as an emergency option only in the event that tank space is not available to resolve tank safety issues. The availability of new tanks is expected by 1997. Since a grout startup effort would take an estimated two years, a complete termination of the Grout Disposal Program is expected in December 1995. The former Tank Waste Remediation (TWRS) Strategy, adopted in 1988, called for the contents of Hanford`s 28 newer double-shell waste tanks to be separated into high-level radioactive material to be vitrified and disposed of in a geologic repository; low-level wastes were to be sent to the Grout Facility to be made into a cement-like-mixture and poured into underground vaults at Hanford for disposal. The waste in the 149 older single-shell tanks (SST) were to undergo further study and analysis before a disposal decision was made.

  18. Grout Facilities standby plan

    International Nuclear Information System (INIS)

    Claghorn, R.D.; Kison, P.F.; Nunamaker, D.R.; Yoakum, A.K.

    1994-01-01

    This plan defines how the Grout Facilities will be deactivated to meet the intent of the recently renegotiated Tri-Party Agreement (TPA). The TPA calls for the use of the grout process as an emergency option only in the event that tank space is not available to resolve tank safety issues. The availability of new tanks is expected by 1997. Since a grout startup effort would take an estimated two years, a complete termination of the Grout Disposal Program is expected in December 1995. The former Tank Waste Remediation (TWRS) Strategy, adopted in 1988, called for the contents of Hanford's 28 newer double-shell waste tanks to be separated into high-level radioactive material to be vitrified and disposed of in a geologic repository; low-level wastes were to be sent to the Grout Facility to be made into a cement-like-mixture and poured into underground vaults at Hanford for disposal. The waste in the 149 older single-shell tanks (SST) were to undergo further study and analysis before a disposal decision was made

  19. Facility planning and site development

    International Nuclear Information System (INIS)

    Reisman, R.C.; Handmaker, H.

    1986-01-01

    Planning for a magnetic resonance imaging (MRI) facility should provide for the efficient operation of current and future MRI devices and must also take into consideration a broad range of general planning principles. Control of budgeted facility costs and construction schedules is of increasing importance due to the magnitude of expense of MRI facility development as well as the need to protect institutional or entrepreneurial investment. In a competitive environment facility costs may be the determining factor in a project's success

  20. 105-C Facility characterization plan

    International Nuclear Information System (INIS)

    Miller, R.L.

    1997-01-01

    This facility characterization plan is a site-specific document that describes how quantification and qualification of the radiological sources and the radioactive contamination in the 105-C Building will be accomplished. Characterization of hazardous materials will be addressed in a separate plan. This plan was developed from review of video tapes, photographs, and records. The purpose of this characterization plan is to provide an efficient and cost-effective method for determining the distribution of radioactive contamination at the 105-C Facility

  1. PUREX facility preclosure work plan

    International Nuclear Information System (INIS)

    Engelmann, R.H.

    1997-01-01

    This preclosure work plan presents a description of the PUREX Facility, the history of the waste managed, and addresses transition phase activities that position the PUREX Facility into a safe and environmentally secure configuration. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels (DOE/RL-90/24). Information concerning solid waste management units is discussed in the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Appendix 2D)

  2. Nuclear Station Facilities Improvement Planning

    International Nuclear Information System (INIS)

    Hooks, R. W.; Lunardini, A. L.; Zaben, O.

    1991-01-01

    An effective facilities improvement program will include a plan for the temporary relocation of personnel during the construction of an adjoining service building addition. Since the smooth continuation of plant operation is of paramount importance, the phasing plan is established to minimize the disruptions in day-to-day station operation and administration. This plan should consider the final occupancy arrangements and the transition to the new structure; for example, computer hookup and phase-in should be considered. The nuclear industry is placing more emphasis on safety and reliability of nuclear power plants. In order to do this, more emphasis is placed on operations and maintenance. This results in increased size of managerial, technical and maintenance staffs. This in turn requires improved office and service facilities. The facilities that require improvement may include training areas, rad waste processing and storage facilities, and maintenance facilities. This paper discusses an approach for developing an effective program to plan and implement these projects. These improvement projects can range in magnitude from modifying a simple system to building a new structure to allocating space for a future project. This paper addresses the planning required for the new structures with emphasis on site location, space allocation, and internal layout. Since facility planning has recently been completed by Sargent and Leyden at six U. S. nuclear stations, specific examples from some of those plants are presented. Site planning and the establishment of long-range goals are of the utmost importance when undertaking a facilities improvement program for a nuclear station. A plan that considers the total site usage will enhance the value of both the new and existing facilities. Proper planning at the beginning of the program can minimize costs and maximize the benefits of the program

  3. Hanford Surplus Facilities Program plan

    International Nuclear Information System (INIS)

    Hughes, M.C.; Wahlen, R.K.; Winship, R.A.

    1989-09-01

    The Hanford Surplus Facilities Program is responsible for the safe and cost-effective surveillance, maintenance, and decommissioning of surplus facilities at the Hanford Site. The management of these facilities requires a surveillance and maintenance program to keep them in a safe condition and development of a plan for ultimate disposition. Criteria used to evaluate each factor relative to decommissioning are based on the guidelines presented by the US Department of Energy-Richland Operations Office, Defense Facilities Decommissioning Program Office, and are consistent with the Westinghouse Hanford Company commitment to decommission the Hanford Site retired facilities in the safest and most cost-effective way achievable. This document outlines the plan for managing these facilities to the end of disposition

  4. Integrated Facilities and Infrastructure Plan.

    Energy Technology Data Exchange (ETDEWEB)

    Reisz Westlund, Jennifer Jill

    2017-03-01

    Our facilities and infrastructure are a key element of our capability-based science and engineering foundation. The focus of the Integrated Facilities and Infrastructure Plan is the development and implementation of a comprehensive plan to sustain the capabilities necessary to meet national research, design, and fabrication needs for Sandia National Laboratories’ (Sandia’s) comprehensive national security missions both now and into the future. A number of Sandia’s facilities have reached the end of their useful lives and many others are not suitable for today’s mission needs. Due to the continued aging and surge in utilization of Sandia’s facilities, deferred maintenance has continued to increase. As part of our planning focus, Sandia is committed to halting the growth of deferred maintenance across its sites through demolition, replacement, and dedicated funding to reduce the backlog of maintenance needs. Sandia will become more agile in adapting existing space and changing how space is utilized in response to the changing requirements. This Integrated Facilities & Infrastructure (F&I) Plan supports the Sandia Strategic Plan’s strategic objectives, specifically Strategic Objective 2: Strengthen our Laboratories’ foundation to maximize mission impact, and Strategic Objective 3: Advance an exceptional work environment that enables and inspires our people in service to our nation. The Integrated F&I Plan is developed through a planning process model to understand the F&I needs, analyze solution options, plan the actions and funding, and then execute projects.

  5. Final work plan : investigation of potential contamination at the former CCC/USDA grain storage facility in Hanover, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2008-11-19

    The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride (below the maximum contaminant level [MCL] of 5.0 {micro}g/L) were detected in two private wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In April 2007, the CCC/USDA collected near-surface soil samples at 1.8-2 ft BGL (below ground level) at 61 locations across the former CCC/USDA facility. All soil samples were analyzed by the rigorous gas chromatograph-mass spectrometer analytical method (purge-and-trap method). No contamination was found in soil samples above the reporting limit of 10 {micro}g/kg. In July 2007, the CCC/USDA sampled indoor air at nine residences on or adjacent to its former facility to address the residents concerns regarding vapor intrusion. Low levels of carbon tetrachloride were detected at four of the nine homes. Because carbon tetrachloride found in private wells and indoor air at the site might be linked to historical use of fumigants containing carbon tetrachloride at its former grain storage facility, the CCC/USDA is proposing to conduct an investigation to determine the source and extent of the carbon tetrachloride contamination associated with the former facility. This investigation will be conducted in accordance with the intergovernmental agreement between the KDHE and the Farm Service Agency (FSA) of the USDA. The investigation at Hanover will be performed, on behalf of the CCC/USDA, by the Environmental Science

  6. 340 Facility maintenance implementation plan

    International Nuclear Information System (INIS)

    1995-03-01

    This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the 340 Facility. This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4B, Maintenance Management Program (DOE 1994), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying Westinghouse Hanford Company (WHC) conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at the 340 Facility. Primary responsibility for the performance and oversight of maintenance activities at the 340 Facility resides with Westinghouse Hanford Company (WHC). Maintenance at the 340 Facility is performed by ICF-Kaiser Hanford (ICF-KH) South Programmatic Services crafts persons. This 340 Facility MIP provides interface requirements and responsibilities as they apply specifically to the 340 Facility. This document provides an implementation schedule which has been developed for items considered to be deficient or in need of improvement. The discussion sections, as applied to implementation at the 340 Facility, have been developed from a review of programs and practices utilizing the graded approach. Biennial review and additional reviews are conducted as significant programmatic and mission changes are made. This document is revised as necessary to maintain compliance with DOE requirements

  7. 340 Facility maintenance implementation plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the 340 Facility. This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4B, Maintenance Management Program (DOE 1994), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying Westinghouse Hanford Company (WHC) conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at the 340 Facility. Primary responsibility for the performance and oversight of maintenance activities at the 340 Facility resides with Westinghouse Hanford Company (WHC). Maintenance at the 340 Facility is performed by ICF-Kaiser Hanford (ICF-KH) South Programmatic Services crafts persons. This 340 Facility MIP provides interface requirements and responsibilities as they apply specifically to the 340 Facility. This document provides an implementation schedule which has been developed for items considered to be deficient or in need of improvement. The discussion sections, as applied to implementation at the 340 Facility, have been developed from a review of programs and practices utilizing the graded approach. Biennial review and additional reviews are conducted as significant programmatic and mission changes are made. This document is revised as necessary to maintain compliance with DOE requirements.

  8. Facility effluent monitoring plan determinations for the 400 Area facilities

    International Nuclear Information System (INIS)

    Nickels, J.M.

    1991-09-01

    This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs

  9. RCRA facility investigation/corrective measures study work plan for the 200-UP-2 Operable Unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1993-06-01

    The 200-UP-2 Operable Unit is one of two source operable units at the U Plant Aggregate Area at the Hanford Site. Source operable units include waste management units and unplanned release sites that are potential sources of radioactive and/or hazardous substance contamination. This work plan, while maintaining the title RFI/CMS, presents the background and direction for conducting a limited field investigation in the 200-UP-2 Operable Unit, which is the first part of the process leading to final remedy selection. This report discusses the background, prior recommendations, goals, organization, and quality assurance for the 200-UP-2 Operable Unit Work Plan. The discussion begins with a summary of the regulatory framework and the role of the work plan. The specific recommendations leading into the work plan are then addressed. Next, the goals and organization of the report are discussed. Finally, the quality assurance and supporting documentation are presented

  10. European facilities and plans

    International Nuclear Information System (INIS)

    Ellis, J.

    1984-01-01

    The capabilities and time schedules of present and planned accelerators in Europe are reviewed. The history of the Large Hadron Collider (LHC) project is recalled, and the results of machine feasibility studies are summarized. It seems possible to build in the LEP tunnel a pp collider with √s = 10 to 18 TeV and a luminosity of 10 33 cm -2 sec - . Results from the Lausanne Workshop on LHC physics are reviewed, and some aspects of Higgs and supersymmetric particle production are discussed

  11. 304 Concretion facility closure plan

    International Nuclear Information System (INIS)

    1990-04-01

    The Hanford Site, located northwest of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium Zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/Zircaloy-2 alloy, and Zircaloy-2 chips and fines were secured in concrete billets in the 304 Concretion Facility, located in the 300 Area. The beryllium/Zircaloy-2 alloy and Zircaloy-2 chips and fines are designated as low-level radioactive mixed waste (LLRMW) with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Concretion Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act of 1976 (RCRA). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 304 Concretion Facility (304 Facility). Clean closure of the 304 Facility is the proposed method for closure of the facility. Justification for this proposal is presented. 15 refs., 22 figs., 4 tabs

  12. 304 Concretion Facility Closure Plan

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Site, located northwest of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with Zircaloy-2 and copper silicon allo , uranium-titanium alloy, beryllium/Zircaloy-2 alloy, and Zircaloy-2 chips and fines were secured in concrete billets (7.5-gal containers) in the 304 Concretion Facility (304 Facility), located in the 300 Area. The beryllium/Zircaloy-2 alloy and Zircaloy-2 chips and fines are designated as low-level radioactive mixed waste (LLRMW) with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Concretion Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act of 1976 (RCRA) and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040 (Ecology 1991). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 304 Facility. The strategy for closure of the 304 Facility is presented in Section 6.0

  13. WIPP facility representative program plan

    International Nuclear Information System (INIS)

    1994-01-01

    This plan describes the Department of Energy (DOE), Carlsbad Area Office (CAO) facility representative (FR) program at the Waste Isolation Pilot Plant (WIPP). It provides the following information: (1) FR and support organization authorities and responsibilities; (2) FR program requirements; and (3) FR training and qualification requirements

  14. Developing standardized facility contingency plans

    International Nuclear Information System (INIS)

    Davidson, D.A.

    1993-01-01

    Texaco consists of several operating departments that are, in effect, independent companies. Each of these departments is responsible for complying with all environmental laws and regulations. This includes the preparation by each facility to respond to an oil spill at that location. For larger spills, however, management of the response will rest with corporate regional response teams. Personnel from all departments make up the regional teams. In 1990, Congress passed the Oil Pollution Act. In 1991, the US Coast Guard began developing oil spill response contingency plan regulations, which they are still working on. Meanwhile, four of the five west coast states have also passed laws requiring contingency plans. (Only Hawaii has chosen to wait and see what the federal regulations will entail). Three of the states have already adopted regulations. Given these laws and regulations, along with its corporate structure, Texaco addressed the need to standardize local facility plans as well as its response organization. This paper discusses how, by working together, the Texaco corporate international oil spill response staff and the Texaco western region on-scene commander developed: A standard contingency plan format crossing corporate boundaries and meeting federal and state requirements. A response organization applicable to any size facility or spill. A strategy to sell the standard contingency plan and response organization to the operating units

  15. Facility effluent monitoring plan determinations for the 200 Area facilities

    International Nuclear Information System (INIS)

    Nickels, J.M.

    1991-11-01

    The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

  16. LAMI - a planned Brazilian facility to investigate the mechanical and physical properties of structural materials under irradiation

    International Nuclear Information System (INIS)

    Andrade, Arnaldo H.P.; Lobo, Raquel M.

    2011-01-01

    The LAMI (Laboratorio de Materiais Irradiados) is a hot laboratory designed to the characterization of irradiated structural material and will constitute one of the main installations of the Brazilian Multipurpose Reactor (RMB). The strong points of LAMI are: to contribute, through theoretical and experimental investigations, to the development of knowledge in materials science in order to be able to predict the evolution of the physical and mechanical material properties under service conditions (irradiation, thermomechanical solicitation, influence of the environment, etc); to characterize the properties of the materials used in the nuclear industry in order to determine their performance and to be able to predict their life expectancy; to establish, maintain and make use of the database generated by these data and to provide expertise on industrial components, in particular to investigate strain or rupture mechanisms. The test materials can be irradiated or not, and originate from surveillance programs, experimental neutron irradiations or simulated irradiation with charged particles. The main line of LAMI will have 10 shielded hot cells. The building also will have an area dedicated to micro and nano structural materials analysis. The mechanical characterization to be carried out within LAMI includes mechanical tests on irradiated materials, comprehension of behavior and damage processes and the incorporation of the test data results in a data bank for capitalization of test results. Planned materials to be tested are going to be metallic alloys used in industrial and experimental reactor: pressure vessel steels, internal stainless steels, austeno-ferritic steels, zirconium alloys and aluminum alloys. (author)

  17. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    International Nuclear Information System (INIS)

    Nickels, J.M.

    1991-06-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the Facility Monitoring Plans of the overall site-wide environmental monitoring plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of individual Facility Effluent Monitoring Plans. This document is intended to be a basic road map to the Facility Effluent Monitoring Plan documents (i.e., the guidance document for preparing Facility Effluent Monitoring Plans, Facility Effluent Monitoring Plan determinations, management plan, and Facility Effluent Monitoring Plans). The implementing procedures, plans, and instructions are appropriate for the control of effluent monitoring plans requiring compliance with US Department of Energy, US Environmental Protection Agency, state, and local requirements. This Quality Assurance Project Plan contains a matrix of organizational responsibilities, procedural resources from facility or site manuals used in the Facility Effluent Monitoring Plans, and a list of the analytes of interest and analytical methods for each facility preparing a Facility Effluent Monitoring Plan. 44 refs., 1 figs., 2 tabs

  18. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    International Nuclear Information System (INIS)

    Frazier, T.P.

    1994-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the Facility Effluent Monitoring Plans, which are part of the overall Hanford Site Environmental Protection Plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of the individual Facility Effluent Monitoring Plans

  19. Final work plan : Phase I investigation of potential contamination at the former CCC/USDA grain storage facility in Savannah, Missouri.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2007-10-12

    . This work will be performed in accord with the Intergovernmental Agreement established between the Farm Service Agency of the USDA and MoDNR, to address carbon tetrachloride contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The investigative activities at Savannah will be conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by UChicago Argonne, LLC, for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an agreement with the DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. The site characterization at Savannah will take place in phases. This approach is recommended by the CCC/USDA and Argonne, so that information obtained and interpretations developed during each incremental stage of the investigation can be used most effectively to guide subsequent phases of the program. This site-specific Work Plan outlines the specific technical objectives and scope of work proposed for Phase I of the Savannah investigation. This Work Plan also includes the community relations plan to be followed throughout the CCC/USDA program at the Savannah site. Argonne is developing a Master Work Plan specific to operations in the state of Missouri. In the meantime, Argonne will issue a Provisional Master Work Plan (PMWP; Argonne 2007) that will be submitted to the MoDNR for review and approval. The agency has already reviewed and approved (with minor changes) the present Master Work Plan (Argonne 2002) under which Argonne currently operates in Kansas. The PMWP (Argonne 2007) will provide detailed information and guidance on the investigative technologies, analytical methodologies, quality assurance-quality control measures, and general health and safety policies to be employed by

  20. Work Plan: Phase II Investigation at the Former CCC/USDA Grain Storage Facility in Montgomery City, Missouri

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M [Argonne National Lab. (ANL), Argonne, IL (United States)

    2012-05-01

    From September 1949 until September 1966, the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) leased property at the southeastern end of Montgomery City, Missouri, for the operation of a grain storage facility. During this time, commercial grain fumigants containing carbon tetrachloride were commonly used by the CCC/USDA and the private grain storage industry to preserve grain in their facilities.

  1. Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for Single-Shell Tank (SST) Waste Management Areas

    International Nuclear Information System (INIS)

    MCCARTHY, M.M.

    1999-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly

  2. Phase 1 RCRA Facility Investigation & Corrective Measures Study Work Plan for Single Shell Tank (SST) Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    MCCARTHY, M.M.

    1999-08-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly.

  3. Final work plan : phase I investigation of potential contamination at the former CCC/USDA grain storage facility in Montgomery City, Missouri.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2010-08-16

    former grain storage facility, the CCC/USDA will conduct investigations to (1) characterize the source(s), extent, and factors controlling the possible subsurface distribution and movement of carbon tetrachloride at the Montgomery City site and (2) evaluate the health and environmental threats potentially represented by the contamination. This work will be performed in accord with the Intergovernmental Agreement established between the Farm Service Agency of the USDA and the MoDNR, to address carbon tetrachloride contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The investigations at Montgomery City will be conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by UChicago Argonne, LLC, for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an agreement with DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. The site characterization at Montgomery City will take place in phases. This approach is recommended by the CCC/USDA and Argonne, so that information obtained and interpretations developed during each incremental stage of the investigation can be used most effectively to guide subsequent phases of the program. This site-specific Work Plan outlines the specific technical objectives and scope of work proposed for Phase I of the Montgomery City investigation. This Work Plan also includes the community relations plan to be followed throughout the CCC/USDA program at the Montgomery City site. Argonne is developing a Master Work Plan specific to operations in the state of Missouri. In the meantime, Argonne has issued a Provisional Master Work Plan (PMWP; Argonne 2007) that has been reviewed and approved by the MoDNR for current use. The PMWP (Argonne 2007) provides

  4. Final Site Safety and Health Plan for Phase II RCRA Facility Investigation Fort Benjamin Harrison Marion County, Indiana

    National Research Council Canada - National Science Library

    1996-01-01

    ..., representativeness, completeness, and comparability of its data are known and documented. To essure that responsibility is met uniformly, each party must prepare a written QA Project Plan (QAPjP...

  5. Facility effluent monitoring plan for the fast flux test facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Dahl, N.R.

    1992-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in US Department of Energy 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 requires the need for a facility effluent monitoring plan. 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

  6. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    International Nuclear Information System (INIS)

    ROGERS, P.M.

    2000-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted

  7. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    ROGERS, P.M.

    2000-06-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted.

  8. Facility effluent monitoring plan for 242-A Evaporator facility

    International Nuclear Information System (INIS)

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

    1993-03-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could 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

  9. Appendix E - Sample Production Facility Plan

    Science.gov (United States)

    This sample Spill Prevention, Control and Countermeasure (SPCC) Plan in Appendix E is intended to provide examples and illustrations of how a production facility could address a variety of scenarios in its SPCC Plan.

  10. Strategic facility planning improves capital decision making.

    Science.gov (United States)

    Reeve, J R

    2001-03-01

    A large, Midwestern IDS undertook a strategic facility-planning process to evaluate its facility portfolio and determine how best to allocate future investments in facility development. The IDS assembled a facility-planning team, which initiated the planning process with a market analysis to determine future market demands and identify service areas that warranted facility expansion. The team then analyzed each of the IDS's facilities from the perspective of uniform capacity measurements, highest and best use compared with needs, building condition and investment-worthiness, and facility growth and site development opportunities. Based on results of the analysis, the strategy adopted entailed, in part, shifting some space from inpatient care to ambulatory care services and demolishing and replacing the 11 percent of facilities deemed to be in the worst condition.

  11. Facility effluent monitoring plan for the 327 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  12. Facility effluent monitoring plan for the tank farm facility

    Energy Technology Data Exchange (ETDEWEB)

    Crummel, G.M.

    1998-05-18

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

  13. LMFBR safety experiment facility planning and analysis

    International Nuclear Information System (INIS)

    Stevenson, M.G.; Scott, J.H.

    1976-01-01

    In the past two years considerable effort has been placed on the planning and design of new facilities for the resolution of LMFBR safety issues. The paper reviews the key issues, the experiments needed to resolve them, and the design aspects of proposed new facilities. In addition, it presents a decision theory approach to selecting an optimal combination of modified and new facilities

  14. Facility effluent monitoring plan for the plutonium uranium extraction facility

    Energy Technology Data Exchange (ETDEWEB)

    Wiegand, D.L.

    1994-09-01

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

  15. Facility Effluent Monitoring Plan for the uranium trioxide facility

    International Nuclear Information System (INIS)

    Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

    1993-12-01

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

  16. Facility effluent monitoring plan for the plutonium uranium extraction facility

    International Nuclear Information System (INIS)

    Wiegand, D.L.

    1994-09-01

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

  17. Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

    International Nuclear Information System (INIS)

    Greager, E.M.

    1997-01-01

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

  18. Facility effluent monitoring plan for 242-A evaporator facility

    International Nuclear Information System (INIS)

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

    1995-02-01

    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

  19. ORNL Isotopes Facilities Shutdown Program Plan

    International Nuclear Information System (INIS)

    Gibson, S.M.; Patton, B.D.; Sears, M.B.

    1990-10-01

    This plan presents the results of a technical and economic assessment for shutdown of the Oak Ridge National Laboratory (ORNL) isotopes production and distribution facilities. On December 11, 1989, the Department of Energy (DOE), Headquarters, in a memorandum addressed to DOE Oak Ridge Operations Office (DOE-ORO), gave instructions to prepare the ORNL isotopes production and distribution facilities, with the exception of immediate facility needs for krypton-85, tritium, and yttrium-90, for safe shutdown. In response to the memorandum, ORNL identified 17 facilities for shutdown. Each of these facilities is located within the ORNL complex with the exception of Building 9204-3, which is located at the Y-12 Weapons Production Plant. These facilities have been used extensively for the production of radioactive materials by the DOE Isotopes Program. They currently house a large inventory of radioactive materials. Over the years, these aging facilities have inherited the problems associated with storing and processing highly radioactive materials (i.e., facilities' materials degradation and contamination). During FY 1990, ORNL is addressing the requirements for placing these facilities into safe shutdown while maintaining the facilities under the existing maintenance and surveillance plan. The day-to-day operations associated with the surveillance and maintenance of a facility include building checks to ensure that building parameters are meeting the required operational safety requirements, performance of contamination control measures, and preventative maintenance on the facility and facility equipment. Shutdown implementation will begin in FY 1993, and shutdown completion will occur by the end of FY 1994

  20. Emergency planning for fuel cycle facilities

    International Nuclear Information System (INIS)

    Lacey, L.R.

    1991-01-01

    In April 1989, NRC published new emergency planning regulations which apply to certain by-product, source, and special nuclear materials licensees including most fuel cycle facilities. In addition to these NRC regulations, other regulatory agencies such as EPA, OSHA, and DOT have regulations concerning emergency planning or notification that may apply to fuel cycle facilities. Emergency planning requirements address such areas as emergency classification, organization, notification and activation, assessment, corrective and protective measures, emergency facilities and equipment, maintaining preparedness, records and reports, and recovery. This article reviews applicable regulatory requirements and guidance, then concentrates on implementation strategies to produce an effective emergency response capability

  1. Facility effluent monitoring plan for the tank farms facilities

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-05-01

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

  2. Site and facility transportation services planning documents

    Energy Technology Data Exchange (ETDEWEB)

    Ratledge, J.E. (Oak Ridge National Lab., TN (USA)); Danese, L.; Schmid, S. (Science Applications International Corp., Oak Ridge, TN (USA))

    1990-01-01

    The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and processing of Site and Facility Specific Transportation Services Planning Documents (SPDs) and Site Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities over the next 2 years with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations. 3 figs., 1 tab.

  3. Site and facility transportation services planning documents

    International Nuclear Information System (INIS)

    Ratledge, J.E.; Danese, L.; Schmid, S.

    1990-01-01

    The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and processing of Site and Facility Specific Transportation Services Planning Documents (SPDs) and Site Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities over the next 2 years with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations. 3 figs., 1 tab

  4. Facility effluent monitoring plan for the 325 Facility

    International Nuclear Information System (INIS)

    1998-01-01

    The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  5. Remedial investigation/feasibility study Work Plan and addenda for Operable Unit 4-12: Central Facilities Area Landfills II and III at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Keck, K.N.; Stormberg, G.J.; Porro, I.; Sondrup, A.J.; McCormick, S.H.

    1993-07-01

    This document is divided into two main sections -- the Work Plan and the addenda. The Work Plan describes the regulatory history and physical setting of Operable Unit 4-12, previous sampling activities, and data. It also identifies a preliminary conceptual model, preliminary remedial action alternatives, and preliminary applicable or relevant and appropriate requirements. In addition, the Work Plan discusses data gaps and data quality objectives for proposed remedial investigation activities. Also included are tasks identified for the remedial investigation/feasibility study (RI/FS) and a schedule of RI/FS activities. The addenda include details of the proposed field activities (Field Sampling Plan), anticipated quality assurance activities (Quality Assurance Project Plan), policies and procedures to protect RI/FS workers and the environment during field investigations (Health and Safety Plan), and policies, procedures, and activities that the Department of Energy will use to involve the public in the decision-making process concerning CFA Landfills II and III RI/FS activities (Community Relations Plan)

  6. Remedial investigation/feasibility study Work Plan and addenda for Operable Unit 4-12: Central Facilities Area Landfills II and III at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Keck, K.N.; Stormberg, G.J.; Porro, I.; Sondrup, A.J.; McCormick, S.H.

    1993-07-01

    This document is divided into two main sections -- the Work Plan and the addenda. The Work Plan describes the regulatory history and physical setting of Operable Unit 4-12, previous sampling activities, and data. It also identifies a preliminary conceptual model, preliminary remedial action alternatives, and preliminary applicable or relevant and appropriate requirements. In addition, the Work Plan discusses data gaps and data quality objectives for proposed remedial investigation activities. Also included are tasks identified for the remedial investigation/feasibility study (RI/FS) and a schedule of RI/FS activities. The addenda include details of the proposed field activities (Field Sampling Plan), anticipated quality assurance activities (Quality Assurance Project Plan), policies and procedures to protect RI/FS workers and the environment during field investigations (Health and Safety Plan), and policies, procedures, and activities that the Department of Energy will use to involve the public in the decision-making process concerning CFA Landfills II and III RI/FS activities (Community Relations Plan).

  7. Facility effluent monitoring plan for the 324 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  8. Facility effluent monitoring plan for the tank farms facilities

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It 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 three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

  9. SURF II: Characteristics, facilities, and plans

    International Nuclear Information System (INIS)

    Madden, R.P.; Canfield, R.; Furst, M.; Hamilton, A.; Hughey, L.

    1992-01-01

    This facility report describes the Synchrotron Ultraviolet Radiation Facility (SURF II) operated by the National Institute of Standards and Technology, Gaithersburg, Maryland. SURF II is a 300-MeV electron storage ring which provides well characterized continuum radiation from the far infrared to the soft x-ray region with the critical wavelength at 17.4 nm. Brief descriptions are given of the user facilities, the characteristics of the synchrotron radiation, the main storage ring, the injector system and each of the operating beam lines, and associated instruments. Further description is given of expansion plans for additional beam lines

  10. Facility effluent monitoring plan for the uranium trioxide facility

    International Nuclear Information System (INIS)

    Thompson, R.J.; Sontag, S.

    1991-11-01

    A facility effluent monitoring plant is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It 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. The UO 3 Plant is located in the south-central portion of the 200 West Area of the Hanford Site. The plant consists of two primary processing buildings and several ancillary facilities. The purpose of the UO 3 Plant is to receive uranyl nitrate hexahydrate (UNH) from the Plutonium-Uranium Extraction (PUREX) Plant, concentrate it, convert the UNH to uranium trioxide (UO 3 ) powder by calcination and package it for offsite shipment. The UO 3 Plant has been placed in a standby mode. There are two liquid discharges, and three gaseous exhaust stacks, and seven building exhausters that are active during standby conditions

  11. National Ignition Facility Title II Design Plan

    International Nuclear Information System (INIS)

    Kumpan, S

    1997-01-01

    This National Ignition Facility (NIF) Title II Design Plan defines the work to be performed by the NIF Project Team between November 1996, when the U.S. Department of Energy (DOE) reviewed Title I design and authorized the initiation of Title H design and specific long-lead procurements, and September 1998, when Title 11 design will be completed

  12. WIPP Facility Work Plan for Solid Waste Management Units

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2001-02-25

    This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

  13. Planning Tool for Strategic Evaluation of Facility Plans - 13570

    Energy Technology Data Exchange (ETDEWEB)

    Magoulas, Virginia; Cercy, Michael [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States); Hall, Irin [Newport News Shipbuilding, 4101 Washington Ave., Newport News, VA 23607 (United States)

    2013-07-01

    Savannah River National Laboratory (SRNL) has developed a strategic planning tool for the evaluation of the utilization of its unique resources for processing and research and development of nuclear materials. The Planning Tool is a strategic level tool for assessing multiple missions that could be conducted utilizing the SRNL facilities and showcasing the plan. Traditional approaches using standard scheduling tools and laying out a strategy on paper tended to be labor intensive and offered either a limited or cluttered view for visualizing and communicating results. A tool that can assess the process throughput, duration, and utilization of the facility was needed. SRNL teamed with Newport News Shipbuilding (NNS), a division of Huntington Ingalls Industries, to create the next generation Planning Tool. The goal of this collaboration was to create a simulation based tool that allows for quick evaluation of strategies with respect to new or changing missions, and clearly communicates results to the decision makers. This tool has been built upon a mature modeling and simulation software previously developed by NNS. The Planning Tool provides a forum for capturing dependencies, constraints, activity flows, and variable factors. It is also a platform for quickly evaluating multiple mission scenarios, dynamically adding/updating scenarios, generating multiple views for evaluating/communicating results, and understanding where there are areas of risks and opportunities with respect to capacity. The Planning Tool that has been developed is useful in that it presents a clear visual plan for the missions at the Savannah River Site (SRS). It not only assists in communicating the plans to SRS corporate management, but also allows the area stakeholders a visual look at the future plans for SRS. The design of this tool makes it easily deployable to other facility and mission planning endeavors. (authors)

  14. Planning Tool for Strategic Evaluation of Facility Plans - 13570

    International Nuclear Information System (INIS)

    Magoulas, Virginia; Cercy, Michael; Hall, Irin

    2013-01-01

    Savannah River National Laboratory (SRNL) has developed a strategic planning tool for the evaluation of the utilization of its unique resources for processing and research and development of nuclear materials. The Planning Tool is a strategic level tool for assessing multiple missions that could be conducted utilizing the SRNL facilities and showcasing the plan. Traditional approaches using standard scheduling tools and laying out a strategy on paper tended to be labor intensive and offered either a limited or cluttered view for visualizing and communicating results. A tool that can assess the process throughput, duration, and utilization of the facility was needed. SRNL teamed with Newport News Shipbuilding (NNS), a division of Huntington Ingalls Industries, to create the next generation Planning Tool. The goal of this collaboration was to create a simulation based tool that allows for quick evaluation of strategies with respect to new or changing missions, and clearly communicates results to the decision makers. This tool has been built upon a mature modeling and simulation software previously developed by NNS. The Planning Tool provides a forum for capturing dependencies, constraints, activity flows, and variable factors. It is also a platform for quickly evaluating multiple mission scenarios, dynamically adding/updating scenarios, generating multiple views for evaluating/communicating results, and understanding where there are areas of risks and opportunities with respect to capacity. The Planning Tool that has been developed is useful in that it presents a clear visual plan for the missions at the Savannah River Site (SRS). It not only assists in communicating the plans to SRS corporate management, but also allows the area stakeholders a visual look at the future plans for SRS. The design of this tool makes it easily deployable to other facility and mission planning endeavors. (authors)

  15. National Ignition Facility (NIF) FY2015 Facility Use Plan

    Energy Technology Data Exchange (ETDEWEB)

    Folta, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wisoff, Jeff [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-12-18

    Major features of the FY2015 NIF Use Plan include: • Performing a record number of layered DT experiments with 28 planned compared with 15 in FY2014. Executing the first plutonium experiments on the NIF in support of the Science Campaigns. • Over 300 targets shots, a 57% increase compared to FY14. This is a stretch goal defined in the 120-Day Study document, and relies upon the success of many shot-rate improvement actions, as well as on the distribution of shot type selected by the users. While the Plan is consistent with this goal, the increased proportion of layered DT experiments described above reduces the margin against this goal. • Commissioning of initial ARC capability, which will support both SSP-HED and SSPICF programs. • Increase in days allocated to Discovery Science to a level that supports an ongoing program for academic use of NIF and an annual solicitation for new proposals. • Six Facility Maintenance and Reconfiguration (FM&R) periods totaling 30 days dedicated to major facility maintenance and modifications. • Utilization of the NIF Facility Advisory Schedule Committee (FASC) to provide stakeholder review and feedback on the NIF schedule. The Use Plan assumes a total FY2015 LLNL NIF Operations funding in MTE 10.7 of $229.465M and in MTE 10.3 of 47.0M. This Use Plan will be revised in the event of significant changes to the FY2015 funding or if NNSA provides FY2016 budget guidance significantly reduced compared to FY2015.

  16. WIPP Facility Work Plan for Solid Waste Management Units

    International Nuclear Information System (INIS)

    2000-01-01

    This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA. A

  17. 40 CFR 35.917 - Facilities planning (step 1).

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Facilities planning (step 1). 35.917... Facilities planning (step 1). (a) Sections 35.917 through 35.917-9 establish the requirements for facilities... the facilities planning provisions of this subpart before award of step 2 or step 3 grant assistance...

  18. 105-DR large sodium fire facility closure Plan. Revision 2

    International Nuclear Information System (INIS)

    Ruck, F.A. III.

    1995-03-01

    The 105-DR Large Sodium Fire Facility (LSFF), which was operated 1972-1986, was a research laboratory that occupied the former ventilation supply room on the SW side of the 105-DR Reactor Facility. (The 105-DR defense reactor was shut down in 1964.) LSFF was used to investigate fire and safety aspects of large sodium or other metal alkali fires in the LMFBR facilities; it was also used to store and treat alkali metal waste. This closure plan presents a description of the unit, the history of the waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of LSFF is expected. It is located within the 100-DR-2 (source) and 100-HR-3 (groundwater) operable units, which will be addressed through the RCRA facility investigation/corrective measures study process

  19. National Ignition Facility project acquisition plan

    International Nuclear Information System (INIS)

    Callaghan, R.W.

    1996-04-01

    The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility (NIF) Project. The scope of the plan describes the procurement activities and acquisition strategy for the following phases of the NIF Project, each of which receives either plant and capital equipment (PACE) or other project cost (OPC) funds: Title 1 and 2 design and Title 3 engineering (PACE); Optics manufacturing facilitization and pilot production (OPC); Convention facility construction (PACE); Procurement, installation, and acceptance testing of equipment (PACE); and Start-up (OPC). Activities that are part of the base Inertial Confinement Fusion (ICF) Program are not included in this plan. The University of California (UC), operating Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory, and Lockheed-Martin, which operates Sandia National Laboratory (SNL) and the University of Rochester Laboratory for Laser Energetics (UR-LLE), will conduct the acquisition of needed products and services in support of their assigned responsibilities within the NIF Project structure in accordance with their prime contracts with the Department of Energy (DOE). LLNL, designated as the lead Laboratory, will have responsibility for all procurements required for construction, installation, activation, and startup of the NIF

  20. Emergency planning and preparedness for nuclear facilities

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    Nuclear installations are designed, constructed and operated in such a way that the probability for an incident or accident is very low and the probability for a severe accident with catastrophic consequences is extremely small. These accidents represent the residual risk of the nuclear installation, and this residual risk can be decreased on one hand by a better design, construction and operation and on the other hand by planning and taking emergency measures inside the facility and in the environment of the facility. By way of introduction and definition it may be indicated to define some terms pertaining to the subject in order to make for more uniform understanding. (orig./DG)

  1. 15 CFR 923.13 - Energy facility planning process.

    Science.gov (United States)

    2010-01-01

    ... facility planning process. The management program must contain a planning process for energy facilities... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Energy facility planning process. 923... affected public and private parties will be involved in the planning process. [61 FR 33806, June 28, 1996...

  2. Decommissioning plan depleted uranium manufacturing facility

    International Nuclear Information System (INIS)

    Bernhardt, D.E.; Pittman, J.D.; Prewett, S.V.

    1987-01-01

    Aerojet Ordnance Tennessee, Inc. (Aerojet) is decommissioning its California depleted uranium (DU) manufacturing facility. Aerojet has conducted manufacturing and research and development activities at the facility since 1977 under a State of California Source Materials License. The decontamination is being performed by a contractor selector for technical competence through competitive bid. Since the facility will be released for uncontrolled use it will be decontaminated to levels as low as reasonably achievable (ALARA). In order to fully apply the principles of ALARA, and ensure the decontamination is in full compliance with appropriate guides, Aerojet has retained Rogers and Associaties Engineering Corporation (RAE) to assist in the decommissioning. RAE has assisted in characterizing the facility and preparing contract bid documents and technical specifications to obtain a qualified decontamination contractor. RAE will monitor the decontamination work effort to assure the contractor's performance complies with the contract specifications and the decontamination plan. The specifications require a thorough cleaning and decontamination of the facility, not just sufficient cleaning to meet the numeric cleanup criteria

  3. WIPP Facility Work Plan for Solid Waste Management Units

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2000-02-25

    This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED’s guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA

  4. 303-K Storage Facility closure plan

    International Nuclear Information System (INIS)

    1993-01-01

    Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5

  5. Near-Facility Environmental Monitoring Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    MCKINNEY, S.M.

    2000-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near-facility environmental monitoring directed by Waste Management Technical Services and supersedes HNF-EP-0538-4. This plan applies to all sampling and monitoring activities performed by Waste Management Technical Services in implementing near-facility environmental monitoring at the Hanford Site. This Quality Assurance Project Plan is required by U.S. Department of Energy Order 5400.1 (DOE 1990) as a part of the Environmental Monitoring Plan (DOE-RL 1997) and is used to define: Environmental measurement and sampling locations used to monitor environmental contaminants near active and inactive facilities and waste storage and disposal sites; Procedures and equipment needed to perform the measurement and sampling; Frequency and analyses required for each measurement and sampling location; Minimum detection level and accuracy; Quality assurance components; and Investigation levels. Near-facility environmental monitoring for the Hanford Site is conducted in accordance with the requirements of U.S. Department of Energy Orders 5400.1 (DOE 1990), 5400.5 (DOE 1993), 5484.1 (DOE 1990), and 435.1 (DOE 1999), and DOE/EH-O173T (DOE 1991). It is Waste Management Technical Services' objective to manage and conduct near-facility environmental monitoring activities at the Hanford Site in a cost-effective and environmentally responsible manner that is in compliance with the letter and spirit of these regulations and other environmental regulations, statutes, and standards

  6. National Ignition Facility project acquisition plan revision 1

    International Nuclear Information System (INIS)

    Clobes, A.R.

    1996-01-01

    The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility M Project. It was prepared for the NIP Prood Office by the NIF Procurement Manager

  7. 40 CFR 35.925-1 - Facilities planning.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Facilities planning. 35.925-1 Section... Facilities planning. That, if the award is for step 2, step 3, or step 2=3 grant assistance, the facilities planning requirements in § 35.917 et seq. have been met. ...

  8. National Ignition Facility Configuration Management Plan

    International Nuclear Information System (INIS)

    Cabral, S G; Moore, T L

    2002-01-01

    This Configuration Management Plan (CMP) describes the technical and administrative management process for controlling the National Ignition Facility (NIF) Project configuration. The complexity of the NIF Project (i.e., participation by multiple national laboratories and subcontractors involved in the development, fabrication, installation, and testing of NIF hardware and software, as well as construction and testing of Project facilities) requires implementation of the comprehensive configuration management program defined in this plan. A logical schematic illustrating how the plan functions is provided in Figure 1. A summary of the process is provided in Section 4.0, Configuration Change Control. Detailed procedures that make up the overall process are referenced. This CMP is consistent with guidance for managing a project's configuration provided in Department of Energy (DOE) Order 430.1, Guide PMG 10, ''Project Execution and Engineering Management Planning''. Configuration management is a formal discipline comprised of the following four elements: (1) Identification--defines the functional and physical characteristics of a Project and uniquely identifies the defining requirements. This includes selection of components of the end product(s) subject to control and selection of the documents that define the project and components. (2) Change management--provides a systematic method for managing changes to the project and its physical and functional configuration to ensure that all changes are properly identified, assessed, reviewed, approved, implemented, tested, and documented. (3) Data management--ensures that necessary information on the project and its end product(s) is systematically recorded and disseminated for decision-making and other uses. Identifies, stores and controls, tracks status, retrieves, and distributes documents. (4) Assessments and validation--ensures that the planned configuration requirements match actual physical configurations and

  9. PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

    International Nuclear Information System (INIS)

    Paladino, D.; Dreier, J.

    2012-01-01

    The PANDA facility is a large scale, multicompartmental thermal hydraulic facility suited for investigations related to the safety of current and advanced LWRs. The facility is multipurpose, and the applications cover integral containment response tests, component tests, primary system tests, and separate effect tests. Experimental investigations carried on in the PANDA facility have been embedded in international projects, most of which under the auspices of the EU and OECD and with the support of a large number of organizations (regulatory bodies, technical dupport organizations, national laboratories, electric utilities, industries) worldwide. The paper provides an overview of the research programs performed in the PANDA facility in relation to BWR containment systems and those planned for PWR containment systems.

  10. Emergency planning and preparedness for nuclear facilities

    International Nuclear Information System (INIS)

    1986-01-01

    In order to review the advances made over the past seven years in the area of emergency planning and preparedness supporting nuclear facilities and consider developments which are on the horizon, the IAEA at the invitation of the Government of Italy, organized this International Symposium in co-operation with the Italian Commission for Nuclear and Alternative Energy Sources, Directorate of Nuclear Safety and Health Protection (ENEA-DISP). There were over 250 designated participants and some 70 observers from 37 Member States and four international organizations in attendance at the Symposium. The Symposium presentations were divided into sessions devoted to the following topics: emergency planning (20 papers), accident assessment (30 papers), protective measures and recovery operations (10 papers) and emergency preparedness (16 papers). A separate abstract was prepared for each of these papers

  11. National Ignition Facility Site Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, V.

    1997-09-01

    The purpose of the NIF Site Management Plan is to describe the roles, responsibilities, and interfaces for the major NIF Project organizations involved in construction of the facility, installation and acceptance testing of special equipment, and the NIF activation. The plan also describes the resolution of priorities and conflicts. The period covered is from Critical Decision 3 (CD3) through the completion of the Project. The plan is to be applied in a stepped manner. The steps are dependent on different elements of the project being passed from the Conventional Facilities (CF) Construction Manager (CM), to the Special Equipment (SE) CMs, and finally to the Activation/ Start-Up (AS) CM. These steps are defined as follows: The site will be coordinated by CF through Project Milestone 310, end of conventional construction. The site is defined as the fenced area surrounding the facility and the CF laydown and storage areas. The building utilities that are installed by CF will be coordinated by CF through the completion of Project Milestone 310, end of conventional construction. The building utilities are defined as electricity, compressed air, de-ionized water, etc. Upon completion of the CF work, the Optics Assembly Building/Laser and Target Area Building (OAB/LTAB) will be fully operational. At that time, an Inertial Confinement Fusion (ICF) Program building coordinator will become responsible for utilities and site activities. * Step 1. Mid-commissioning (temperature stable, +1{degree}C) of an area (e.g., Laser Bay 2, OAB) will precipitate the turnover of that area (within the four walls) from CF to SE. * Step 2. Interior to the turned-over space, SE will manage all interactions, including those necessary by CF. * Step 3. As the SE acceptance testing procedures (ATPS) are completed, AS will take over the management of the area and coordinate all interactions necessary by CF and SE. For each step, the corresponding CMs for CF, SE, or AS will be placed in charge of

  12. National Ignition Facility Site Management Plan

    International Nuclear Information System (INIS)

    Roberts, V.

    1997-01-01

    The purpose of the NIF Site Management Plan is to describe the roles, responsibilities, and interfaces for the major NIF Project organizations involved in construction of the facility, installation and acceptance testing of special equipment, and the NIF activation. The plan also describes the resolution of priorities and conflicts. The period covered is from Critical Decision 3 (CD3) through the completion of the Project. The plan is to be applied in a stepped manner. The steps are dependent on different elements of the project being passed from the Conventional Facilities (CF) Construction Manager (CM), to the Special Equipment (SE) CMs, and finally to the Activation/ Start-Up (AS) CM. These steps are defined as follows: The site will be coordinated by CF through Project Milestone 310, end of conventional construction. The site is defined as the fenced area surrounding the facility and the CF laydown and storage areas. The building utilities that are installed by CF will be coordinated by CF through the completion of Project Milestone 310, end of conventional construction. The building utilities are defined as electricity, compressed air, de-ionized water, etc. Upon completion of the CF work, the Optics Assembly Building/Laser and Target Area Building (OAB/LTAB) will be fully operational. At that time, an Inertial Confinement Fusion (ICF) Program building coordinator will become responsible for utilities and site activities. * Step 1. Mid-commissioning (temperature stable, +1 degree C) of an area (e.g., Laser Bay 2, OAB) will precipitate the turnover of that area (within the four walls) from CF to SE. * Step 2. Interior to the turned-over space, SE will manage all interactions, including those necessary by CF. * Step 3. As the SE acceptance testing procedures (ATPS) are completed, AS will take over the management of the area and coordinate all interactions necessary by CF and SE. For each step, the corresponding CMs for CF, SE, or AS will be placed in charge of

  13. Fast Flux Test Facility (FFTF) standby plan

    Energy Technology Data Exchange (ETDEWEB)

    Hulvey, R.K.

    1997-03-06

    The FFTF Standby Plan, Revision 0, provides changes to the major elements and project baselines to maintain the FFTF plant in a standby condition and to continue washing sodium from irradiated reactor fuel. The Plan is consistent with the Memorandum of Decision approved by the Secretary of Energy on January 17, 1997, which directed that FFTF be maintained in a standby condition to permit the Department to make a decision on whether the facility should play a future role in the Department of Energy`s dual track tritium production strategy. This decision would be made in parallel with the intended December 1998 decision on the selection of the primary, long- term source of tritium. This also allows the Department to review the economic and technical feasibility of using the FFTF to produce isotopes for the medical community. Formal direction has been received from DOE-RL and Fluor 2020 Daniel Hanford to implement the FFTF standby decision. The objective of the Plan is maintain the condition of the FFTF systems, equipment and personnel to preserve the option for plant restart within three and one-half years of a decision to restart, while continuing deactivation work which is consistent with the standby mode.

  14. Fast Flux Test Facility (FFTF) standby plan

    International Nuclear Information System (INIS)

    Hulvey, R.K.

    1997-01-01

    The FFTF Standby Plan, Revision 0, provides changes to the major elements and project baselines to maintain the FFTF plant in a standby condition and to continue washing sodium from irradiated reactor fuel. The Plan is consistent with the Memorandum of Decision approved by the Secretary of Energy on January 17, 1997, which directed that FFTF be maintained in a standby condition to permit the Department to make a decision on whether the facility should play a future role in the Department of Energy's dual track tritium production strategy. This decision would be made in parallel with the intended December 1998 decision on the selection of the primary, long- term source of tritium. This also allows the Department to review the economic and technical feasibility of using the FFTF to produce isotopes for the medical community. Formal direction has been received from DOE-RL and Fluor 2020 Daniel Hanford to implement the FFTF standby decision. The objective of the Plan is maintain the condition of the FFTF systems, equipment and personnel to preserve the option for plant restart within three and one-half years of a decision to restart, while continuing deactivation work which is consistent with the standby mode

  15. Plan for 3-D full-scale earthquake testing facility

    International Nuclear Information System (INIS)

    Ohtani, K.

    2001-01-01

    Based on the lessons learnt from the Great Hanshin-Awaji Earthquake, National Research Institute for Earth Science and Disaster Prevention plan to construct the 3-D Full-Scale Earthquake Testing Facility. This will be the world's largest and strongest shaking table facility. This paper describes the outline of the project for this facility. This facility will be completed in early 2005. (author)

  16. Feasibility Investigation for a Solar Power Generation Facility

    Science.gov (United States)

    Nathan, Lakshmi

    2010-01-01

    The Energy Policy Act of 2005 states that by fiscal year 2013, at least 7.5% of the energy consumed by the government must be renewable energy. In an effort to help meet this goal, Johnson Space Center (JSC) is considering installing a solar power generation facility. The purpose of this project is to conduct a feasibility investigation for such a facility. Because Kennedy Space Center (KSC) has a solar power generation facility, the first step in this investigation is to learn about KSC's facility and obtain information on how it was constructed. After collecting this information, the following must be determined: the amount of power desired, the size of the facility, potential locations for it, and estimated construction and maintenance costs. Contacts with JSC's energy provider must also be established to determine if a partnership would be agreeable to both parties. Lastly, all of this data must be analyzed to decide whether or not JSC should construct the facility. The results from analyzing the data collected indicate that a 200 kW facility would provide enough energy to meet 1% of JSC's energy demand. This facility would require less than 1 acre of land. In the map below, potential locations are shown in green. The solar power facility is projected to cost $2 M. So far, the information collected indicates that such a facility could be constructed. The next steps in this investigation include contacting JSC's energy provider, CenterPoint Energy, to discuss entering a partnership; developing a life cycle cost analysis to determine payback time; developing more detailed plans; and securing funding.

  17. Category 3 investigation-derived waste Readiness Evaluation Plan

    International Nuclear Information System (INIS)

    Ludowise, J.D.

    1996-08-01

    This Readiness Evaluation Plan presents the methodology used to assess the readiness for loading investigation-derived waste (IDW) drums on trucks for transport to the Environmental Restoration Disposal Facility (ERDF). The scope of this Readiness Evaluation Plan includes an assessment of the organizations, procedures, and regulatory approvals necessary for the handling of IDW containers and the subsequent transportation of materials to ERDF

  18. Sites Requiring Facility Response Plans, Geographic NAD83, EPA (2006) [facility_response_plan_sites_la_EPA_2007

    Data.gov (United States)

    Louisiana Geographic Information Center — Locations of facilities in Louisiana requiring Oil Pollution Act (OPA) Facility Response Plans (FRP). The dataset was provided by the Region 6 OSCARS program....

  19. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ballinger, Marcel Y.; Gervais, Todd L.

    2004-11-15

    The Pacific Northwest National Laboratory (PNNL) operates a number of Research & Development (R&D) facilities for the U.S. Department of Energy (DOE) on the Hanford Site. Facility effluent monitoring plans (FEMPs) have been developed to document the facility effluent monitoring portion of the Environmental Monitoring Plan (DOE 2000) for the Hanford Site. Three of PNNL’s R&D facilities, the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling, and individual FEMPs were developed for these facilities in the past. In addition, a balance-of-plant (BOP) FEMP was developed for all other DOE-owned, PNNL-operated facilities at the Hanford Site. Recent changes, including shutdown of buildings and transition of PNNL facilities to the Office of Science, have resulted in retiring the 3720 FEMP and combining the 331 FEMP into the BOP FEMP. This version of the BOP FEMP addresses all DOE-owned, PNNL-operated facilities at the Hanford Site, excepting the Radiochemical Processing Laboratory, which has its own FEMP because of the unique nature of the building and operations. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R&D. R&D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in Appendix A. Potential radioactive airborne emissions in the BOP facilities are estimated annually using a building inventory-based approach provided in federal regulations. Sampling at individual BOP facilities is based on a potential-to-emit assessment. Some of these facilities are considered minor emission points and thus are sampled routinely, but not continuously, to confirm the low emission potential. One facility, the 331 Life Sciences Laboratory, has a major emission point and is sampled continuously. Sampling systems are

  20. 105-DR Large Sodium Fire Facility closure plan

    International Nuclear Information System (INIS)

    1993-05-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected

  1. 105-DR Large Sodium Fire Facility closure plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950`s and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

  2. Information security management system planning for CBRN facilities

    International Nuclear Information System (INIS)

    Lenaeu, Joseph D.; O'Neil, Lori Ross; Leitch, Rosalyn M.; Glantz, Clifford S.; Landine, Guy P.; Bryant, Janet L.; Lewis, John; Mathers, Gemma; Rodger, Robert; Johnson, Christopher

    2015-01-01

    The focus of this document is to provide guidance for the development of information security management system planning documents at chemical, biological, radiological, or nuclear (CBRN) facilities. It describes a risk-based approach for planning information security programs based on the sensitivity of the data developed, processed, communicated, and stored on facility information systems.

  3. Information security management system planning for CBRN facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lenaeu, Joseph D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); O' Neil, Lori Ross [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Leitch, Rosalyn M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glantz, Clifford S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Landine, Guy P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bryant, Janet L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lewis, John [National Nuclear Lab., Workington (United Kingdom); Mathers, Gemma [National Nuclear Lab., Workington (United Kingdom); Rodger, Robert [National Nuclear Lab., Workington (United Kingdom); Johnson, Christopher [National Nuclear Lab., Workington (United Kingdom)

    2015-12-01

    The focus of this document is to provide guidance for the development of information security management system planning documents at chemical, biological, radiological, or nuclear (CBRN) facilities. It describes a risk-based approach for planning information security programs based on the sensitivity of the data developed, processed, communicated, and stored on facility information systems.

  4. Sport Facility Planning and Management. Sport Management Library.

    Science.gov (United States)

    Farmer, Peter J.; Mulrooney, Aaron L.; Ammon, Rob, Jr.

    Students of sports facilities management will need to acquire a wide variety of managerial skills and knowledge in order to be adequately prepared to plan and manage these facilities. This textbook offers students a mix of practical examples and recognized theory to help them in the planning, constructing, promoting, and managing of sports…

  5. Planning Facilities for Athletics, Physical Education and Recreation. Revised.

    Science.gov (United States)

    American Alliance for Health, Physical Education, Recreation and Dance (AAHPERD).

    This revised edition includes new material recommended by a panel of experts in the field of recreational planning. The following topics are covered: (1) the planning process; (2) indoor facilities; (3) outdoor facilities; (4) indoor and outdoor swimming pools; (5) encapsulated spaces and stadiums; (6) service areas; (7) recreation and park…

  6. Site and facility waste transportation services planning documents

    International Nuclear Information System (INIS)

    Ratledge, J.E.; Schmid, S.; Danese, L.

    1991-01-01

    The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and maintenance of Site- and Facility-Specific Transportation Services Planning Documents (SPDs) and Site-Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities, with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations

  7. Waste Encapsulation and Storage Facility (WESF) Design Reconstitution Plan

    International Nuclear Information System (INIS)

    HERNANDEZ, R.

    1999-01-01

    The purpose of Design Reconstitution is to establish a Design Baseline appropriate to the current facility mission. The scope of this plan is to ensure that Systems, Structures and Components (SSC) identified in the WESF Basis for Interim Operation (HNF-SDWM-BIO-002) are adequately described and documented, in order to support facility operations. In addition the plan addresses the adequacy of selected Design Topics which are also crucial for support of the facility Basis for Interim Operation (BIO)

  8. An integrated approach for facilities planning by ELECTRE method

    Science.gov (United States)

    Elbishari, E. M. Y.; Hazza, M. H. F. Al; Adesta, E. Y. T.; Rahman, Nur Salihah Binti Abdul

    2018-01-01

    Facility planning is concerned with the design, layout, and accommodation of people, machines and activities of a system. Most of the researchers try to investigate the production area layout and the related facilities. However, few of them try to investigate the relationship between the production space and its relationship with service departments. The aim of this research to is to integrate different approaches in order to evaluate, analyse and select the best facilities planning method that able to explain the relationship between the production area and other supporting departments and its effect on human efforts. To achieve the objective of this research two different approaches have been integrated: Apple’s layout procedure as one of the effective tools in planning factories, ELECTRE method as one of the Multi Criteria Decision Making methods (MCDM) to minimize the risk of getting poor facilities planning. Dalia industries have been selected as a case study to implement our integration the factory have been divided two main different area: the whole facility (layout A), and the manufacturing area (layout B). This article will be concerned with the manufacturing area layout (Layout B). After analysing the data gathered, the manufacturing area was divided into 10 activities. There are five factors that the alternative were compared upon which are: Inter department satisfactory level, total distance travelled for workers, total distance travelled for the product, total time travelled for the workers, and total time travelled for the product. Three different layout alternatives have been developed in addition to the original layouts. Apple’s layout procedure was used to study and evaluate the different alternatives layouts, the study and evaluation of the layouts was done by calculating scores for each of the factors. After obtaining the scores from evaluating the layouts, ELECTRE method was used to compare the proposed alternatives with each other and with

  9. A guide for preparing Hanford Site facility effluent monitoring plans

    International Nuclear Information System (INIS)

    Nickels, J.M.

    1992-06-01

    This document provides guidance on the format and content of effluent monitoring plans for facilities at the Hanford Site. The guidance provided in this document is designed to ensure compliance with US Department of Energy (DOE) Orders 5400.1 (DOE 1988a), 5400.3 (DOE 1989a), 5400.4 (DOE 1989b), 5400.5 (DOE 1990a), 5480.1 (DOE 1982), 5480.11 (DOE 1988b), and 5484.1 (DOE 1981). These require environmental monitoring plans for each site, facility, or process that uses, generates, releases, or manages significant pollutants of radioactive or hazardous materials. In support of DOE Orders 5400.5 (Radiation Protection of the Public and the Environment) and 5400.1 (General Environmental Protection Program), the DOE Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE 1991) should be used to establish elements of a radiological effluent monitoring program in the Facility Effluent Monitoring Plan. Evaluation of facilities for compliance with the US Environmental Protection Agency Clean Air Act of 1977 requirements also is included in the airborne emissions section of the Facility Effluent Monitoring Plans. Sampling Analysis Plans for Liquid Effluents, as required by the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), also are included in the Facility Effluent Monitoring Plans. The Facility Effluent Monitoring Plans shall include complete documentation of gaseous and liquid effluent sampling and monitoring systems

  10. Major issues on establishing an emergency plan in nuclear facilities

    International Nuclear Information System (INIS)

    Chen, Zhu-zhou

    1988-03-01

    Several major issues on emergency planning and preparation in nuclear facilities were discussed -- such as the importance of emergency planning and preparation, basic principles of intervention and implementation of emergency plan and emergency training and drills to insure the effectiveness of the emergency plan. It is emphasized that the major key point of emergency planning and response is to avoid the occurrence of serious nonrandom effect. 12 refs., 3 tabs

  11. 200 Area Liquid Effluent Facilities -- Quality assurance program plan

    International Nuclear Information System (INIS)

    Fernandez, L.

    1995-01-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance and management controls used by the 200 Area Liquid Effluent Facilities (LEF) to perform its activities in accordance with DOE Order 5700.6C. The 200 Area LEF consists of the following facilities: Effluent Treatment Facility (ETF); Treated Effluent Disposal Facility (TEDF); Liquid Effluent Retention facility (LERF); and Truck Loading Facility -- (Project W291). The intent is to ensure that all activities such as collection of effluents, treatment, concentration of secondary wastes, verification, sampling and disposal of treated effluents and solids related with the LEF operations, conform to established requirements

  12. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  13. Computer-Assisted School Facility Planning with ONPASS.

    Science.gov (United States)

    Urban Decision Systems, Inc., Los Angeles, CA.

    The analytical capabilities of ONPASS, an on-line computer-aided school facility planning system, are described by its developers. This report describes how, using the Canoga Park-Winnetka-Woodland Hills Planning Area as a test case, the Department of City Planning of the city of Los Angeles employed ONPASS to demonstrate how an on-line system can…

  14. Facility effluent monitoring plan for the 2724-W Protective Equipment Decontamination Facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Lavey, G.H.

    1992-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires 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**. 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

  15. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Geiger, J.L.

    1992-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires 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. 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

  16. The planned Alaska SAR Facility - An overview

    Science.gov (United States)

    Carsey, Frank; Weeks, Wilford

    1987-01-01

    The Alaska SAR Facility (ASF) is described in an overview fashion. The facility consists of three major components, a Receiving Ground System, a SAR Processing System and an Analysis and Archiving System; the ASF Program also has a Science Working Team and the requisite management and operations systems. The ASF is now an approved and fully funded activity; detailed requirements and science background are presented for the facility to be implemented for data from the European ERS-1, the Japanese ERS-1 and Radarsat.

  17. 105-DR Large Sodium Fire Facility decontamination, sampling, and analysis plan

    International Nuclear Information System (INIS)

    Knaus, Z.C.

    1995-01-01

    This is the decontamination, sampling, and analysis plan for the closure activities at the 105-DR Large Sodium Fire Facility at Hanford Reservation. This document supports the 105-DR Large Sodium Fire Facility Closure Plan, DOE-RL-90-25. The 105-DR LSFF, which operated from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility in the 100-D Area of the Hanford Site. The LSFF was established to investigate fire fighting and safety associated with alkali metal fires in the liquid metal fast breeder reactor facilities. The decontamination, sampling, and analysis plan identifies the decontamination procedures, sampling locations, any special handling requirements, quality control samples, required chemical analysis, and data validation needed to meet the requirements of the 105-DR Large Sodium Fire Facility Closure Plan in compliance with the Resource Conservation and Recovery Act

  18. Ice condenser testing facility and plans

    International Nuclear Information System (INIS)

    Kannberg, L.D.; Ross, B.A.; Eschbach, E.J.; Ligotke, M.W.

    1987-01-01

    A facility is being constructed to experimentally validate the ICEDF computer code. The code was developed to estimate the extent of fission product retention in the ice compartments of pressurized water reactor ice condenser containment systems during severe accidents. The design and construction of the facility is based on a test design that addresses the validation needs of the code for conditions typical of those expected to occur during severe pressurized water reactor accidents. Detailed facility design has followed completion of a test design (i.e., assembled test cases each involving a different set of aerosol and thermohydraulic flow conditions). The test design was developed with the aid of statistical test design software and was scrutinized for applicability with the aid of ICEDF simulations. The test facility will incorporate a small section of a prototypic ice condenser (e.g., a cross section comprising the equivalent of four 1-ft-diameter ice baskets to their full prototypic height of 48 ft). The development of the test design, the detailed facility design, and the construction progress are described in this paper

  19. Fast Flux Test Facility project plan. Revision 2

    International Nuclear Information System (INIS)

    Hulvey, R.K.

    1995-11-01

    The Fast Flux Test Facility (FFTF) Transition Project Plan, Revision 2, provides changes to the major elements and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition

  20. Fast Flux Test Facility project plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Hulvey, R.K.

    1995-11-01

    The Fast Flux Test Facility (FFTF) Transition Project Plan, Revision 2, provides changes to the major elements and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition.

  1. Grout Treatment Facility Land Disposal Restriction Management Plan

    International Nuclear Information System (INIS)

    Hendrickson, D.W.

    1991-01-01

    This document establishes management plans directed to result in the land disposal of grouted wastes at the Hanford Grout Facilities in compliance with Federal, State of Washington, and Department of Energy land disposal restrictions. 9 refs., 1 fig

  2. Private sector's role in public school facility planning.

    Science.gov (United States)

    2009-03-01

    This report explores the role of private consultants in the school facility planning process. : It focuses on such issues as school siting and local government and school district collaboration. : As such, it seeks to demonstrate the importance of th...

  3. ERC Maintenance Implementation Plan for nuclear facilities

    International Nuclear Information System (INIS)

    Franquero, R.C.

    1997-05-01

    The inactive and surplus facilities assigned to the Environmental Restoration Contractor are shut down and have no operating production processes or production materials except for residual contamination. There is a minimal number of operating systems to support surveillance and maintenance or decontamination and decommissioning activities (D ampersand D). These systems may include heating and ventilation, air conditioning, lighting, and other electrical systems. Inactive and surplus facilities will be subject to periodic long-term surveillance to ensure the integrity of structures until D ampersand D. D ampersand D projects are of relatively short duration and end with all systems deactivated. Therefore, a rigorous in-depth maintenance program such as that required for producing nuclear facilities is not required or cost effective

  4. 202-S Hexone Facility supplemental information to the Hanford Facility Contingency Plan

    International Nuclear Information System (INIS)

    Ingle, S.J.

    1996-03-01

    This document is a unit-specific contingency plan for the 202-S Hexone Facility and is intended to be used as a supplement to the Hanford Facility Contingency Plan. This unit-specific plan is to be used to demonstrate compliance with the contingency plan requirements of WAC 173-303 for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units. The 202-S Hexone Facility is not used to process radioactive or nonradioactive hazardous material. Radioactive, dangerous waste material is contained in two underground storage tanks, 276-S-141 and 276-S-142. These tanks do not present a significant hazard to adjacent facilities, personnel, or the environment. Currently, dangerous waste management activities are not being applied at the tanks. It is unlikely that any incidents presenting hazards to public health or the environment would occur at the 202-S Hexone Facility

  5. Overview of planning process at FFTF [Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Gadeken, A.D.

    1986-03-01

    The planning process at the Fast Flux Test Facility (FFTF) is controlled through a hierarchy of documents ranging from a ten-year strategic plan to a weekly schedule. Within the hierarchy are a Near-Term (three-year) Operating Plan, a Cycle (six-month) Plan, and an Outage/Operating Phase Schedule. Coordination of the planning process is accomplished by a dedicated preparation team that also provides an overview of the formal planning timetable which identifies key action items required to be completed before an outage/operating phase can begin

  6. Near-facility environmental monitoring quality assurance project plan

    International Nuclear Information System (INIS)

    McKinney, S.M.

    1997-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near facility environmental monitoring performed by Waste Management Federal Services, Inc., Northwest Operations and supersedes WHC-EP-0538-2. This plan applies to all sampling and monitoring activities performed by waste management Federal Services, Inc., Northwest Operations in implementing facility environmental monitoring at the Hanford Site

  7. Fast flux test facility, transition project plan

    International Nuclear Information System (INIS)

    Guttenberg, S.

    1994-01-01

    The FFTF Transition Project Plan, Revision 1, provides changes and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition

  8. Fast flux test facility, transition project plan

    Energy Technology Data Exchange (ETDEWEB)

    Guttenberg, S.

    1994-11-15

    The FFTF Transition Project Plan, Revision 1, provides changes and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition.

  9. Planning the School Food Service Facilities. Revised 1967.

    Science.gov (United States)

    Utah State Board of Education, Salt Lake City.

    Evaluations of food service equipment, kitchen design and food service facilities are comprehensively reviewed for those concerned with the planning and equipping of new school lunchrooms or the remodeling of existing facilities. Information is presented in the form of general guides adaptable to specific local situations and needs, and is…

  10. Environmental Control Plan for the Industrial Hygiene Field Services Facility

    International Nuclear Information System (INIS)

    Donnelly, J.W.

    2000-01-01

    This environmental control plan is for the Hanford Site's Industrial Hygiene Field Services Facility, located in the 100-N Area. This facility is used for the maintenance and storage of respirators, respiratory equipment and testing, calibration and testing of industrial hygiene equipment, and asbestos fiber counting

  11. Readiness Assessment Plan, Hanford 200 areas treated effluent disposal facilities

    International Nuclear Information System (INIS)

    Ulmer, F.J.

    1995-01-01

    This Readiness Assessment Plan documents Liquid Effluent Facilities review process used to establish the scope of review, documentation requirements, performance assessment, and plant readiness to begin operation of the Treated Effluent Disposal system in accordance with DOE-RLID-5480.31, Startup and Restart of Facilities Operational Readiness Review and Readiness Assessments

  12. Facility effluent monitoring plan for WESF

    Energy Technology Data Exchange (ETDEWEB)

    SIMMONS, F.M.

    1999-09-01

    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.

  13. Facility effluent monitoring plan for WESF

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    1999-01-01

    The FEMP for the Waste Encapsulation and Storage Facility (WESF) provides sufficient information on the WESF effluent characteristics and the efferent 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

  14. Planning and Managing School Facilities for Agriculture

    Science.gov (United States)

    Staller, Bernie

    1976-01-01

    The Agribusiness Department at Janesville Parker Senior High in Wisconsin involves 360 students and three instructors in three different buildings. Facilities were provided through a variety of methods with major emphasis on utilizing the urban setting. Future Farmers of America students operate projects in orchards, greenhouse, gardens, and…

  15. Outline of electric power facility plan in fiscal year 1988

    International Nuclear Information System (INIS)

    1988-01-01

    As to the electric power facility plan in fiscal year 1988, 15 designated electric power enterprises made the notification to the Minister of International Trade and Industry in March, 1988. This outline of the facility plan summarized the plans of 66 enterprises in total, including the plans of municipally operated, joint thermal power and other enterprises in addition to the above 15. In order to ensure the stable supply of electric power, the Ministry of International Trade and Industry considers that it is indispensable to purposefully develop electric power sources and the facilities for distribution along this facility plan. The forecast for fiscal year 1997 is : total electric power demand 778.2 billion kWh, maximum power demand 151.21 million kW, and yearly load factor 56.9 %. This is equivalent to the yearly growth of 2.4 %. In fiscal year 1988, it is planned to present 29 plants of 2760 MW to the Power Source Development Coordination Council. The breakdown is : hydroelectricity 140 MW, thermal power 2010 MW, and nuclear power 610 MW. The Ministry guides electric power enterprises so as to realize the diversification of electric power sources. Also the increase of transmission and transformation facilities, the plan of equipment investment and others are reported. (Kako, I.)

  16. Synchronization of workshops, using facilities planning

    Science.gov (United States)

    Zineb, Britel; Abdelghani, Cherkaoui

    2017-08-01

    In this paper, we will present a methodology used for the synchronization of two workshops of a sheet metal department. These two workshops have a supplier-customer relationship. The aim of the study is to synchronise the two workshops as a step towards creating a better material flow, reduced inventory and achieving Just in time and lean production. To achieve this, we used a different set of techniques: SMED, Facilities planning…

  17. Facility Effluent Monitoring Plan for the 222-S Laboratory

    International Nuclear Information System (INIS)

    Robinson, A.V.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems against applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It 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. The current operation of the 222-S facilities includes the provision of analytical and radiological chemistry services in support of Hanford Site processing plants. The emphasis is on waste management, chemical processing, environmental monitoring effluent programs at B Plant, the Uranium Oxide Plant, Tank Farms, the 242-A Evaporator, the Waste Encapsulation and Storage Facility, the Plutonium-Uranium Extraction Facility, the Plutonium Finishing Plant, process development/impact activities, and essential materials. The laboratory also supplies analytical services in support of ongoing waste tank characterization

  18. Facility effluent monitoring plan for the B plant

    International Nuclear Information System (INIS)

    Lesser, J.E.

    1994-09-01

    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 impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plant 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 every three years

  19. Business plan Hatchery Facility Zambezi Valley, Mozambique

    NARCIS (Netherlands)

    Vernooij, A.G.; Wilschut, S.

    2015-01-01

    This business plan focuses on the establishment of a hatchery, one of the essential elements of a sustainable and profitable poultry meat value chain. There is a growing demand for poultry meat in the Zambezi Valley, and currently a large part of the consumed broilers comes from other parts of the

  20. Development of Facilities Master Plan and Laboratory Renovation Project

    Energy Technology Data Exchange (ETDEWEB)

    Fox, Andrea D

    2011-10-03

    Funding from this grant has allowed Morehouse School of Medicine to complete its first professionally developed, comprehensive campus master plan that is in alignment with the recently completed strategic plan. In addition to master planning activities, funds were used for programming and designing research renovations, and also to supplement other research facility upgrades by providing lighting and equipment. The activities funded by this grant will provide the catalyst for substantial improvement in the School's overall facilities for biomedical education and research, and will also provide much of the information needed to conduct a successful campaign to raise funds for proposed buildings and renovations.

  1. Risk evaluation system for facility safeguards and security planning

    International Nuclear Information System (INIS)

    Udell, C.J.; Carlson, R.L.

    1987-01-01

    The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planning assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily

  2. Hanford Site waste tank farm facilities design reconstitution program plan

    International Nuclear Information System (INIS)

    Vollert, F.R.

    1994-01-01

    Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980's has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan

  3. Federal Facilities Compliance Act, Conceptual Site Treatment Plan. Part 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-10-29

    This Conceptual Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed in this document include: general discussion of the plan, including the purpose and scope; technical aspects of preparing plans, including the rationale behind the treatability groupings and a discussion of characterization issues; treatment technology needs and treatment options for specific waste streams; low-level mixed waste options; TRU waste options; and future waste generation from restoration activities.

  4. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    International Nuclear Information System (INIS)

    Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

    1993-12-01

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

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

    International Nuclear Information System (INIS)

    Lewis, C.J.

    1995-10-01

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

  6. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    International Nuclear Information System (INIS)

    Thompson, R.J.; Sontage, S.

    1991-11-01

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

  7. Facility Effluent Monitoring Plan for the 2724-W Protective Equipment Decontamination Facility

    International Nuclear Information System (INIS)

    Carter, G.J.

    1991-11-01

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

  8. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-12-01

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

  9. The preliminary planning for decommissioning nuclear facilities in Taiwan

    International Nuclear Information System (INIS)

    Li, K.K.

    1993-01-01

    During the congressional hearing in 1992 for a $7 billion project for approval of the fourth nuclear power plant, the public was concerned about the decommissioning of the operating plants. In order to facilitate the public acceptance of nuclear energy and to secure the local capability for appropriate nuclear backend management, both technologically and financially, it is important to have preliminary planning for decommissioning the nuclear facilities. This paper attempted to investigate the possible scope of decommissioning activities and addressed the important regulatory, financial, and technological aspects. More research and development works regarding the issue of decommissioning are needed to carry out the government's will of decent management of nuclear energy from the cradle to the grave

  10. Planning and implementing nuclear emergency response facilities

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

    After Three Mile Island, Arkansas Nuclear One produced a planning document called TMI-2 Response Program. Phase I of the program defined action plans in nine areas: safety assessment, training, organization, public information, communication, security, fiscal-governmental, technical and logistical support. Under safety assessment, the staff was made even better prepared to handle radioactive material. Under training, on site simulators for each unit at ANO were installed. The other seven topics interface closely with each other. An emergency control center is diagrammed. A habitable technical support system was created. A media center, with a large media area, and an auditorium, was built. Electric door strike systems increased security. Phone networks independently run via microwave were installed. Until Three Mile Island, logistical problems were guesswork. That incident afforded an opportunity to better identify and prepare for these problems

  11. Federal Facilities Compliance Act, Draft Site Treatment Plan: Compliance Plan Volume. Part 2, Volume 2

    International Nuclear Information System (INIS)

    1994-01-01

    This document presents the details of the implementation of the Site Treatment Plan developed by Ames Laboratory in compliance with the Federal Facilities Compliance Act. Topics discussed in this document include: implementation of the plan; milestones; annual updates to the plan; inclusion of new waste streams; modifications of the plan; funding considerations; low-level mixed waste treatment plan and schedules; and TRU mixed waste streams

  12. 305 Building Cold Test Facility Management Plan

    International Nuclear Information System (INIS)

    Whitehurst, R.

    1994-01-01

    This document provides direction for the conduct of business in Building 305 for cold testing tools and equipment. The Cold Test Facility represents a small portion of the overall building, and as such, the work instructions already implemented in the 305 Building will be utilized. Specific to the Cold Test there are three phases for the tools and equipment as follows: 1. Development and feature tests of sludge/fuel characterization equipment, fuel containerization equipment, and sludge containerization equipment to be used in K-Basin. 2. Functional and acceptance tests of all like equipment to be installed and operated in K-Basin. 3. Training and qualification of K-Basin Operators on equipment to be installed and operated in the Basin

  13. Waste analysis plan for the 200 area effluent treatment facility and liquid effluent retention facility

    International Nuclear Information System (INIS)

    Ballantyne, N.A.

    1995-01-01

    This waste analysis plan (WAP) has been prepared for startup of the 200 Area Effluent Treatment Facility (ETF) and operation of the Liquid Effluent Retention Facility (LERF), which are located on the Hanford Facility, Richland, Washington. This WAP documents the methods used to obtain and analyze representative samples of dangerous waste managed in these units, and of the nondangerous treated effluent that is discharged to the State-Approved Land Disposal System (SALDS). Groundwater Monitoring at the SALDS will be addressed in a separate plan

  14. Facility Effluent Monitoring Plan for the 3720 Building

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the Environmental Science Laboratory (3720 Facility) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs'' This FEMP has been prepared for the 3720 Facility primarily because it has a major (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The 3720 Facility provides office and laboratory space for PNNL scientific and engineering staff conducting multidisciplinary research in the areas of materials characterization and testing and waste management. The facility is designed to accommodate the use of radioactive and hazardous materials to conduct these activities. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, and dispersible particulate. The facility is in the process of being vacated for shutdown, but is considered a Major Emission Point as of the date of this document approval.

  15. 303-K Radioactive Mixed-Waste Storage Facility closure plan

    International Nuclear Information System (INIS)

    1991-11-01

    The Hanford Site, located northwest of Richland, Washington, houses reactors chemical-separation systems, and related facilities used for the production o special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 303-K Radioactive Mixed-Waste Storage Facility (303-K Facility) has been used since 1943 to store various radioactive,and dangerous process materials and wastes generated by the fuel manufacturing processes in the 300 Area. The mixed wastes are stored in US Department of Transportation (DOT)-specification containers (DOT 1988). The north end of the building was used for storage of containers of liquid waste and the outside storage areas were used for containers of solid waste. Because only the north end of the building was used, this plan does not include the southern end of the building. This closure plan presents a description of the facility, the history of materials and wastes managed, and a description of the procedures that will be followed to chose the 303-K Facility as a greater than 90-day storage facility. The strategy for closure of the 303-K Facility is presented in Chapter 6.0

  16. Facility layout planning for educational systems: An application of fuzzy GIS and AHP

    Directory of Open Access Journals (Sweden)

    Hossein Ebrhaimzadeh Asmin

    2014-06-01

    Full Text Available One of the most important issues in urban planning programs is to allocate necessary spaces for educational applications. Selecting appropriate locations for training centers increases students' mental capabilities. Suitable location for the establishment of educational facilities is the first fundamental step for development of educational systems. The selection of optimal sites for educational facilities involves numerous parameters and it is essential to use multiple criteria decision making approaches to make wise decisions. This paper presents an empirical investigation on facility layout planning for educational systems in city of Birjand, Iran. Using fuzzy GIS as well as analytical hierarchy process (AHP, the study determines the most appropriate candidates for training centers.

  17. Facility effluent monitoring plan for the 300 Area Fuels Fabrication Facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Brendel, D.F.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring system 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. The Fuel Fabrication Facility in the Hanford 300 Area supported the production reactors from the 1940's until they were shut down in 1987. Prior to 1987 the Fuel Fabrication Facility released both airborne and liquid radioactive effluents. In January 1987 the emission of airborne radioactive effluents ceased with the shutdown of the fuels facility. The release of liquid radioactive effluents have continued although decreasing significantly from 1987 to 1990

  18. Project summary plan for HTGR recycle reference facility

    International Nuclear Information System (INIS)

    Baxter, B.J.

    1979-11-01

    A summary plan is introduced for completing conceptual definition of an HTGR Recycle Reference Facility (HRRF). The plan describes a generic project management concept, often referred to as the requirements approach to systems engineering. The plan begins with reference flow sheets and provides for the progressive evolution of HRRF requirements and definition through feasibility, preconceptual, and conceptual phases. The plan lays end-to-end all the important activities and elements to be treated during each phase of design. Identified activities and elements are further supported by technical guideline documents, which describe methodology, needed terminology, and where relevant a worked example

  19. Certification plan transuranic waste: Hazardous Waste Handling Facility

    International Nuclear Information System (INIS)

    1992-06-01

    The purpose of this plan is to describe the organization and methodology for the certification of transuranic (TRU) waste handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). The plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Quality Assurance Implementing Management Plan (QAIMP) for the HWBF; and a list of the current and planned implementing procedures used in waste certification

  20. Facility Effluent Monitoring Plan for the Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    FRAZIER, T.P.

    1999-01-01

    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 impact employee or public safety or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. To ensure the long-range integrity of the effluent monitoring systems, an update to this facility effluent monitoring plan is required whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document is reviewed annually even if there are no operational changes, and is updated, at a minimum, every 3 years

  1. Energy Systems Integration Facility (ESIF) Facility Stewardship Plan: Revision 2.1

    Energy Technology Data Exchange (ETDEWEB)

    Torres, Juan [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Anderson, Art [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-01-02

    The U.S. Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy (EERE), has established the Energy Systems Integration Facility (ESIF) on the campus of the National Renewable Energy Laboratory (NREL) and has designated it as a DOE user facility. This 182,500-ft2 research facility provides state-of-the-art laboratory and support infrastructure to optimize the design and performance of electrical, thermal, fuel, and information technologies and systems at scale. This Facility Stewardship Plan provides DOE and other decision makers with information about the existing and expected capabilities of the ESIF and the expected performance metrics to be applied to ESIF operations. This plan is a living document that will be updated and refined throughout the lifetime of the facility.

  2. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2001-01-01

    This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

  3. The national plan of radioactive materials and wastes management. ASN's notice about the choice of the sites to be investigated in view of the setting up of a disposal facility for low activity/long living wastes

    International Nuclear Information System (INIS)

    2009-07-01

    This short presentation, given by the national safety authority (ASN) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), presents, first, the second French national plan of radioactive materials and wastes management (PNGMDR) with its main priorities, and then, the choice of the sites to survey in view of the setting up of a disposal facility for low level/long living wastes. The ASN expresses its opinion about the criteria retained by the ANDRA (the national agency of radioactive waste management) to select the most suitable sites. (J.S.)

  4. Risk evaluation system for facility safeguards and security planning

    International Nuclear Information System (INIS)

    Udell, C.J.; Carlson, R.L.

    1987-01-01

    The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planing assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily

  5. Double-shell tank waste transfer facilities integrity assessment plan

    International Nuclear Information System (INIS)

    Hundal, T.S.

    1998-01-01

    This document presents the integrity assessment plan for the existing double-shell tank waste transfer facilities system in the 200 East and 200 West Areas of Hanford Site. This plan identifies and proposes the integrity assessment elements and techniques to be performed for each facility. The integrity assessments of existing tank systems that stores or treats dangerous waste is required to be performed to be in compliance with the Washington State Department of Ecology Dangerous Waste Regulations, Washington Administrative Code WAC-173-303-640 requirements

  6. Hexone Storage and Treatment Facility closure plan

    International Nuclear Information System (INIS)

    1992-11-01

    The HSTF is a storage and treatment unit subject to the requirements for the storage and treatment of dangerous waste. Closure is being conducted under interim status and will be completed pursuant to the requirements of Washington State Department of Ecology (Ecology) Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-610 and WAC 173-303-640. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of WAC 173-303 or of this closure plan. The information on radionuclides is provided only for general knowledge where appropriate. The known hazardous/dangerous waste remaining at the site before commencing other closure activities consists of the still vessels, a tarry sludge in the storage tanks, and residual contamination in equipment, piping, filters, etc. The treatment and removal of waste at the HSTF are closure activities as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and WAC 173-303

  7. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ballinger, M.Y.; Shields, K.D.

    1999-04-02

    The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP.

  8. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    International Nuclear Information System (INIS)

    Ballinger, M.Y.; Shields, K.D.

    1999-01-01

    The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP

  9. 2727-S Nonradioactive Dangerous Waste Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    Wilczek, T.A.; Laws, J.R.; Izatt, R.D.

    1992-01-01

    This closure plan describes the activities for final closure of the 2727-S Nonradioactive Dangerous Waste Storage (NRDWS) Facility at the Hanford Site. The 2727-S NRDWS Facility provided container storage for nonradioactive dangerous and extremely hazardous wastes generated in the research and development laboratories, process operations, and maintenance and transportation functions throughout the Hanford Site. Storage operations began at the 2727-S NRDWS Facility March 14, 1983, and continued until December 30, 1986, when the last shipment of materials from the facility took place. These storage operations have been moved to the new 616 NRDWS Facility, which is an interim status unit located between the 200 East and 200 West Areas of the Hanford Site

  10. Radiotherapy facilities: Master planning and concept design considerations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-08-15

    This publication provides guidelines on how to plan a radiotherapy facility in terms of the strategic master planning process including the legal, technical and infrastructure requirements. It outlines a risk assessment methodology, a typical project work plan and describes the professional expertise required for the implementation of such a project. Generic templates for a block design are suggested, which include possibilities for future expansion. These templates can be overlaid onto the designated site such that the most efficient workflow between the main functional areas can be ensured. A sample checklist is attached to act as a guideline for project management and to indicate the critical stages in the process where technical expert assistance may be needed. The publication is aimed at professionals and administrators involved in infrastructure development, planning and facility management, as well as engineers, building contractors and radiotherapy professionals.

  11. Radiotherapy Facilities: Master Planning and Concept Design Considerations (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidelines on how to plan a radiotherapy facility in terms of the strategic master planning process including the legal, technical and infrastructure requirements. It outlines a risk assessment methodology and a typical project work plan, and describes the professional expertise required for the implementation of such a project. Generic templates for a block design are suggested, which include possibilities for future expansion. These templates can be overlaid onto the designated site such that the most efficient workflow between the main functional areas can be ensured. A sample checklist is attached to act as a guideline for project management and to indicate the critical stages in the process where technical expert assistance may be needed. The publication is aimed at professionals and administrators involved in infrastructure development, planning and facility management, as well as engineers, building contractors and radiotherapy professionals

  12. Radiotherapy facilities: Master planning and concept design considerations

    International Nuclear Information System (INIS)

    2014-01-01

    This publication provides guidelines on how to plan a radiotherapy facility in terms of the strategic master planning process including the legal, technical and infrastructure requirements. It outlines a risk assessment methodology, a typical project work plan and describes the professional expertise required for the implementation of such a project. Generic templates for a block design are suggested, which include possibilities for future expansion. These templates can be overlaid onto the designated site such that the most efficient workflow between the main functional areas can be ensured. A sample checklist is attached to act as a guideline for project management and to indicate the critical stages in the process where technical expert assistance may be needed. The publication is aimed at professionals and administrators involved in infrastructure development, planning and facility management, as well as engineers, building contractors and radiotherapy professionals

  13. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    1991-12-01

    Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references

  14. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-12-01

    Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references.

  15. Savannah River Site plan for performing maintenance in Federal Facility Agreement areas (O and M Plan)

    International Nuclear Information System (INIS)

    Morris, D.R.

    1996-01-01

    The Savannah River Site was placed on the National Priority List (NPL) in December 1989 and became subject to comprehensive remediation in accordance with CERCLA. The FFA, effective August 16, 1993, establishes the requirements for Site investigation and remediation of releases and potential releases of hazardous substances, and interim status corrective action for releases of hazardous wastes or hazardous constituents. It was determined that further direction was needed for the Operating Departments regarding operation and maintenance activities within those areas listed in the FFA. The Plan for Performing Maintenance (O and M Plan) provides this additional direction. Section 4.0 addresses the operation and maintenance activities necessary for continued operation of the facilities in areas identified as RCRA/CERCLA Units or Site Evaluation Areas. Certain types of the O and M activity could be construed as a remedial or removal action. The intent of this Plan is to provide direction for conducting operation and maintenance activities that are not intended to be remedial or removal actions. The Plan identifies the locations of the units and areas, defines intrusive O and M activities, classifies the intrusive activity as either minor or major, and identifies the requirements, approvals, and documentation necessary to perform the activity in a manner that is protective of human health and the environment; and minimizes any potential impact to any future removal and remedial actions

  16. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    1992-11-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed

  17. Environmental Monitoring Plan, Nevada Test Site and support facilities

    International Nuclear Information System (INIS)

    1991-11-01

    This Operational Area Monitoring Plan for environmental monitoring, is for EG ampersand G Energy Measurements, Inc. (EG ampersand G/EM) which operates several offsite facilities in support of activities at the Nevada Test Site (NTS). These facilities include: (1) Amador Valley Operations (AVO), Pleasanton, California; (2) Kirtland Operations (KO), Kirtland Air Force base, Albuquerque, New Mexico (KAFB); (3) Las Vegas Area Operations (LVAO), Remote Sensing Laboratory (RSL), and North Las Vegas (NLV) Complex at Nellis Air Force Base (NAFB), North Las Vegas, Nevada; (4) Los Alamos Operations (LAO), Los Alamos, New Mexico; (5) Santa Barbara Operations (SBO), Goleta, California; (6) Special Technologies Laboratory (STL), Santa Barbara, California; (7) Washington Aerial Measurements Department (WAMD), Andrews Air Force Base, Maryland; and, (8) Woburn Cathode Ray Tube Operations (WCO), Woburn, Massachusetts. Each of these facilities has an individual Operational Area Monitoring Plan, but they have been consolidated herein to reduce redundancy

  18. Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

    Energy Technology Data Exchange (ETDEWEB)

    DAVIS, W.E.

    2000-03-08

    A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures 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 must be updated, as a minimum, every 3 years.

  19. Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    DAVIS, W.E.

    2000-01-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures 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 must be updated, as a minimum, every 3 years

  20. Emergency preparedness and response plan for nuclear facilities in Indonesia

    International Nuclear Information System (INIS)

    Nur Rahmah Hidayati; Pande Made Udiyani

    2009-01-01

    All nuclear facilities in Indonesia are owned and operated by the National Nuclear Energy Agency (BATAN). The programs and activities of emergency planning and preparedness in Indonesia are based on the existing nuclear facilities, i.e. research reactors, research reactor fuel fabrication plant, radioactive waste treatment installation and radioisotopes production installation. The assessment is conducted to learn of status of emergency preparedness and response plan for nuclear facilities in Indonesia and to support the preparation of future Nuclear Power Plant. The assessment is conducted by comparing the emergency preparedness and response system in Indonesia to the system in other countries such as Japan and Republic of Korea, since the countries have many Nuclear Power Plants and other nuclear facilities. As a result, emergency preparedness response plan for existing nuclear facility in Indonesia has been implemented in many activities such as environmental monitoring program, facility monitoring equipment, and the continuous exercise of emergency preparedness and response. However, the implementation need law enforcement for imposing the responsibility of the coordinators in National Emergency Preparedness Plan. It also needs some additional technical support systems which refer to the system in Japan or Republic of Korea. The systems must be completed with some real time monitors which will support the emergency preparedness and response organization. The system should be built in NPP site before the first NPP will be operated. The system should be connected to an Off Site Emergency Center under coordination of BAPETEN as the regulatory body which has responsibility to control of nuclear energy in Indonesia. (Author)

  1. NIF conventional facilities construction health and safety plan

    International Nuclear Information System (INIS)

    Benjamin, D W

    1998-01-01

    The purpose of this Plan is to outline the minimum health and safety requirements to which all participating Lawrence Livermore National Laboratory (LLNL) and non-LLNL employees (excluding National Ignition Facility [NIF] specific contractors and subcontractors covered under the construction subcontract packages (e.g., CSP-9)-see Construction Safety Program for the National Ignition Facility [CSP] Section I.B. ''NIF Construction Contractors and Subcontractors'' for specifics) shall adhere to for preventing job-related injuries and illnesses during Conventional Facilities construction activities at the NIF Project. For the purpose of this Plan, the term ''LLNL and non-LLNL employees'' includes LLNL employees, LLNL Plant Operations staff and their contractors, supplemental labor, contract labor, labor-only contractors, vendors, DOE representatives, personnel matrixed/assigned from other National Laboratories, participating guests, and others such as visitors, students, consultants etc., performing on-site work or services in support of the NIF Project. Based upon an activity level determination explained in Section 1.2.18, in this document, these organizations or individuals may be required by site management to prepare their own NIF site-specific safety plan. LLNL employees will normally not be expected to prepare a site-specific safety plan. This Plan also outlines job-specific exposures and construction site safety activities with which LLNL and non-LLNL employees shall comply

  2. Facility Effluent Monitoring Plan for the N Reactor

    International Nuclear Information System (INIS)

    Watson, D.J.; Brendel, D.F.; Shields, K.D.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It 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. The primary purpose of the N Reactor Facility Effluent Monitoring Plan (FEMP), during standby, is to ensure that the radioactive effluents are properly monitored and evaluated for compliance with the applicable DOE orders and regulatory agencies at the federal, state, and local levels. A secondary purpose of the FEMP is to ensure that hazardous wastes are not released, in liquid effluents, to the environment even though the potential to do so is extremely low. The FEMP is to provide a monitoring system that collects representative samples in accordance with industry standards, performs analyses within stringent quality control (QC) requirements, and evaluates the data through the use of comparative analysis with the standards and acceptable environmental models

  3. 190-C Facility <90 Day Storage Pad training plan

    International Nuclear Information System (INIS)

    Little, N.C.

    1996-12-01

    This is the Environmental Restoration Contractor (ERC) team training plan for the 190-C Facility <90 Day Storage Pad of Hazardous Waste. It is intended to meet the requirements of Washington Administrative Code (WAC) 173-303-330 and the Hanford Dangerous Waste Permit. Training unrelated to compliance with WAC 173-303-330 is not addressed in this training plan. WAC 173-303-330(1)(d)(ii, v, vi) requires that personnel be familiarized, where applicable, with waste feed cut-off systems, response to ground-water contamination incidents, and shutdown of operations. These are not applicable to 190-C Facility <90 Day Storage Pad, and are therefore not covered in this training plan

  4. The emergency plan implementing procedures for HANARO facility

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Tai; Khang, Byung Oui; Lee, Goan Yup; Lee, Moon [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-04-01

    The radiological emergency plan implementing procedures of HANARO (High-flux Advanced Neutron Application Reactor) facility is prepared based on the Korea Atomic Law, the Civil Defence Law, Disaster Protection Law and the emergency related regulatory guides such as Guidance for Evolution of Radiation Emergency Plans in Nuclear Research Facilities (KAERI/TR-956/98, Feb.1998) and the emergency plan of HANARO. These procedures is also prepared to ensure adequate response activities to the rediological events which would cause a significant risk to the KAERI staffs and the public nea to the site. Periodic trainning and exercise for the reactor operators and emergency staffs will reduce accident risks and the release of radioactivities to the environment. 61 refs., 81 tabs. (Author)

  5. Molecular Contamination Investigation Facility (MCIF) Capabilities

    Science.gov (United States)

    Soules, David M.

    2013-01-01

    This facility was used to guide the development of ASTM E 1559 center dot Multiple Quartz Crystal Microbalances (QCMs), large sample and spectral effects capability center dot Several instrumented, high vacuum chamber systems are used to evaluate the molecular outgassing characteristics of materials, flight components and other sensitive surfaces. Test materials for spacecraft/instrument selection center.Test flight components for acceptable molecular outgas levels center dot Determine time/temperature vacuum bake-out requirements center. Data used to set limits for use of materials and specific components center. Provide Input Data to Contamination Transport Models -Applied to numerous flight projects over the past 20 years.

  6. Fast Flux Test Facility, Sodium Storage Facility project-specific project management plan

    International Nuclear Information System (INIS)

    Shank, D.R.

    1994-01-01

    This Project-Specific Project Management Plan describes the project management methods and controls used by the WHC Projects Department to manage Project 03-F-031. The Sodium Storage Facility provides for storage of the 260,000 gallons of sodium presently in the FFTF Plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium

  7. Fast Flux Test Facility, Sodium Storage Facility project-specific project management plan

    Energy Technology Data Exchange (ETDEWEB)

    Shank, D.R.

    1994-12-29

    This Project-Specific Project Management Plan describes the project management methods and controls used by the WHC Projects Department to manage Project 03-F-031. The Sodium Storage Facility provides for storage of the 260,000 gallons of sodium presently in the FFTF Plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium.

  8. Construction plan of ion irradiation facility in JAERI

    International Nuclear Information System (INIS)

    Tanaka, Ryuichi

    1987-01-01

    The Takasaki Radiation Chemistry Research Establishment of Japan Atomic Energy Research Institute (JAERI) started the construction of an ion irradiation facility to apply ion beam to the research and development of radiation resistant materials for severe environment, the research on biotechnology and new functional materials. This project was planned as ion beam irradiation becomes an effective means for the research on fundamental physics and advanced technology, and the national guideline recently emphasizes the basic and pioneering field in research and development. This facility comprises an AVF cyclotron with an ECR ion source (maximum proton energy: 90 MeV), a 3 MV tandem accelerator, a 3 MV single end type Van de Graaf accelerator and a 400 kV ion implanter. In this report, the present status of planning the accelerators and the facility to be constructed, the outline of research plan, the features of the accelerators, and the beam characteristics are described. In this project, the research items are divided into the materials for space environment, the materials for nuclear fusion reactors, biotechnology, new functional materials, and ion beam technology. The ion beams required for the facility are microbeam, pulsed beam, multiple beam, neutron beam and an expanded irradiation field. (Kako, I.)

  9. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    International Nuclear Information System (INIS)

    Shields, K.D.; Ballinger, M.Y.

    1999-03-01

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

  10. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

  11. Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  12. Sampling and Analysis Plan for the 221-U Facility

    International Nuclear Information System (INIS)

    Rugg, J.E.

    1998-02-01

    This sampling and analysis plan (SAP) presents the rationale and strategy for the sampling and analysis activities proposed to be conducted to support the evaluation of alternatives for the final disposition of the 221-U Facility. This SAP will describe general sample locations and the minimum number of samples required. It will also identify the specific contaminants of potential concern (COPCs) and the required analysis. This SAP does not define the exact sample locations and equipment to be used in the field due to the nature of unknowns associated with the 221-U Facility

  13. Radiological planning and implementation for nuclear-facility decommissioning

    International Nuclear Information System (INIS)

    Valentine, A.M.

    1982-01-01

    The need and scope of radiological planning required to support nuclear facility decommissioning are issues addressed in this paper. The role of radiation protection engineering and monitoring professionals during project implementation and closeout is also addressed. Most of the discussion focuses on worker protection considerations; however, project support, environmental protection and site release certification considerations are also covered. One objective is to identify radiological safety issues that must be addressed. The importance of the issues will vary depending on the type of facility being decommissioned; however, by giving appropriate attention to these issues difficult decommissioning projects can be accomplished in a safer manner with workers and the public receiving minimal radiation exposures

  14. Waste Encapsulation and Storage Facility (WESF) Waste Analysis Plan

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  15. Considerations in setting up and planning a graft processing facility.

    Science.gov (United States)

    Koh, Mickey B C

    2017-12-01

    The graft processing facility forms one of the core components of a clinical haematopoietic stem cell transplant program. The quality of a graft is instrumental in leading to consistent and reproducible outcomes of engraftment and other parameters. As such, meticulous planning and consideration is required and will include core elements including physical design and clinical correlates. The successful running of such a facility depends on an overarching quality program and adherence to local and international regulatory guidelines. Copyright © 2017 King Faisal Specialist Hospital & Research Centre. Published by Elsevier B.V. All rights reserved.

  16. KSC facilities status and planned management operations. [for Shuttle launches

    Science.gov (United States)

    Gray, R. H.; Omalley, T. J.

    1979-01-01

    A status report is presented on facilities and planned operations at the Kennedy Space Center with reference to Space Shuttle launch activities. The facilities are essentially complete, with all new construction and modifications to existing buildings almost finished. Some activity is still in progress at Pad A and on the Mobile Launcher due to changes in requirements but is not expected to affect the launch schedule. The installation and testing of the ground checkout equipment that will be used to test the flight hardware is now in operation. The Launch Processing System is currently supporting the development of the applications software that will perform the testing of this flight hardware.

  17. Management plan -- Multi-Function Waste Tank Facility. Revision 1

    International Nuclear Information System (INIS)

    Fritz, R.L.

    1995-01-01

    This Westinghouse Hanford Company (WHC) Multi-Function Waste Tank Facility (MWTF) Management Plan provides guidance for execution WHC MWTF Project activities related to design, procurement, construction, testing, and turnover. This Management Plan provides a discussion of organizational responsibilities, work planning, project management systems, quality assurance (QA), regulatory compliance, personnel qualifications and training, and testing and evaluations. Classified by the US Department of Energy (DOE) as a major systems acquisition (MSA), the MWTF mission is to provide a safe, cost-effective, and environmentally sound method for interim storage of Hanford Site high-level wastes. This Management Plan provides policy guidance and direction to the Project Office for execution of the project activities

  18. Management plan -- Multi-Function Waste Tank Facility. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Fritz, R.L.

    1995-01-11

    This Westinghouse Hanford Company (WHC) Multi-Function Waste Tank Facility (MWTF) Management Plan provides guidance for execution WHC MWTF Project activities related to design, procurement, construction, testing, and turnover. This Management Plan provides a discussion of organizational responsibilities, work planning, project management systems, quality assurance (QA), regulatory compliance, personnel qualifications and training, and testing and evaluations. Classified by the US Department of Energy (DOE) as a major systems acquisition (MSA), the MWTF mission is to provide a safe, cost-effective, and environmentally sound method for interim storage of Hanford Site high-level wastes. This Management Plan provides policy guidance and direction to the Project Office for execution of the project activities.

  19. The integration of expert knowledge in decision support systems for facility location planning

    NARCIS (Netherlands)

    Arentze, T.A.; Borgers, A.W.J.; Timmermans, H.J.P.

    1995-01-01

    The integration of expert systems in DSS has led to a new generation of systems commonly referred to as knowledge-based or intelligent DSS. This paper investigates the use of expert system technology for the development of a knowledge-based DSS for the planning of retail and service facilities. The

  20. 105-DR Large Sodium Fire Facility Supplemental Information to the Hanford Facility Contingency Plan (DOE/RL-93-75)

    International Nuclear Information System (INIS)

    Edens, V.G.

    1998-05-01

    This document is a unit-specific contingency plan for the 105-DR Large Sodium Fire Facility and is intended to be used as a supplement to DOE/RL-93-75, Hanford Facility Contingency Plan (DOE-RL 1993). This unit-specific plan is to be used to demonstrate compliance with the contingency plan requirements of Washington Administrative Code (WAC) 173-303 for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units.The LSFF occupied the former ventilation supply fan room and was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires. The unit was used to conduct experiments for studying the behavior of molten alkali metals and alkali metal fires. This unit had also been used for the storage and treatment of alkali metal dangerous waste. Additionally, the Fusion Safety Support Studies programs sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium-lead compounds. The LSFF, which is a RCRA site, was partially clean closed in 1995 and is documented in 'Transfer of the 105-DR Large Sodium Fire Facility to Bechtel Hanford, Inc.' (BHI 1998). In summary, the 105-DR supply fan room (1720-DR) has been demolished, and a majority of the surrounding soils were clean-closed. The 117-DR Filter Building, 116-DR Exhaust Stack, 119- DR Sampling Building, and associated ducting/tunnels were not covered under this closure

  1. Experimental area plans for an advanced hadron facility

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, E.W.; Macek, R.J.; Tschalear, C.

    1986-01-01

    A brief overview is presented of the current plans for an experimental area for a new advanced hadron facility for the exploration of nuclear and particle physics. The facility, LAMPF II, is presently visualized as consisting of the LAMPF linac sending 800 MeV protons to a 6 GeV booster ring followed by a 45 GeV main ring. Two experimental areas area planned. The first is intended to provide neutrinos via a pair of pulsed focusing horns. The other is designed to accommodate secondary beams that span the range of useful energies up to GeV/c. Beam specification goals are discussed with respect to source brightness, beam purity, and beam-line acceptance and length. The various beam lines are briefly described. Production cross sections and rates are estimated for antiproton production. Problems of thermal energy deposition in both components and targets and of effectiveness of particle separators are discussed. 9 refs. (LEW)

  2. Experimental area plans for an advanced hadron facility

    International Nuclear Information System (INIS)

    Hoffman, E.W.; Macek, R.J.; Tschalear, C.

    1986-01-01

    A brief overview is presented of the current plans for an experimental area for a new advanced hadron facility for the exploration of nuclear and particle physics. The facility, LAMPF II, is presently visualized as consisting of the LAMPF linac sending 800 MeV protons to a 6 GeV booster ring followed by a 45 GeV main ring. Two experimental areas area planned. The first is intended to provide neutrinos via a pair of pulsed focusing horns. The other is designed to accommodate secondary beams that span the range of useful energies up to GeV/c. Beam specification goals are discussed with respect to source brightness, beam purity, and beam-line acceptance and length. The various beam lines are briefly described. Production cross sections and rates are estimated for antiproton production. Problems of thermal energy deposition in both components and targets and of effectiveness of particle separators are discussed. 9 refs

  3. A conceptual model for barrier free facilities planning.

    Science.gov (United States)

    Bittencourt, R S; de M Guimarães, L B

    2012-01-01

    This paper presents the proposal of a model for planning a barrier free industrial facilities, considering the demands that inclusion requires, ranging from outside the factory (social environment), to the needs of the production system and the workstation. Along with literature review, the demands were identified in a shoe manufacturer that employs people with disabilities, and organized taxonomically in agreement with the structure for planning facilities. The results show that the problems are not primarily related to eliminating architectural barriers and factors aimed at preventing risks to people's health and safety but, rather, are related to the company's cultural environment, because the main hazards are managerial. In special cases, it is suggested there is a need to adjust those parts of tasks that the worker cannot do, or even to re-schedule work so as to make it possible for employees with disabilities to perform their tasks.

  4. Pre-Project planning of Capital Facilities at NASA

    OpenAIRE

    Barrow, Benjamin John

    1999-01-01

    This thesis details the development of a NASA specific Project Definition Rating Index (PDRI) tool. This tool is to be used as a checklist for determining the necessary steps to follow in defining project scope and as a means to monitor progress and assess scope definition completeness at various stages during the NASA Pre-Project Planning process. This thesis also describes and identifies specific points in the NASA Capital Facility Programming Cycle for the performance of PDRI assessments ...

  5. 324 Facility B-Cell quality process plan

    International Nuclear Information System (INIS)

    Carlson, J.L.

    1998-01-01

    This report documents the quality process plan for the restart of a hot cell in the B Plant, originally a bismuth phosphate processing facility, but later converted to a waste fractionation plant. B-Cell is currently being cleaned out and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/1999. This report describes the major activities that remain for completion of the TPA milestone

  6. Planning for maintenance in radiochemical facilities [Paper No.: VB-2

    International Nuclear Information System (INIS)

    Balasubramanian, G.R.

    1981-01-01

    Reprocessing facilities in the earlier stages of development were planned mainly based on the concept of direct maintenance in view of the inherent advantage of man-machine interface and initial savings in the investment costs. With the mechanical processes finding a firm place in head-end operation and increase in down time necessary for elaborate decontamination efforts even for a minor modification has led to the review of the concept. For the same reason, the recent plants are based on the concept of harmonious blend of both direct and remote maintenance. The paper describes the planning needed from consideration of various aspects related to such concepts of maintenance during different phases of such type of facilities, highlighting some of the tools and special equipments to be developed for this purpose. A brief description of recent development in the field of remote maintenance is also given. Though the basic hot facility of reference is the one of reprocessing fast reactor fuels, the concepts and systems discussed are equally applicable to other radiochemical and radiometallurgical facilities also. (author)

  7. Category 2 and 4 investigation-derived waste readiness evaluation plan

    International Nuclear Information System (INIS)

    Ludowise, J.D.

    1996-08-01

    This Readiness Evaluation Plan presents the methodology used to assess the readiness for loading investigation-derived waste drums on trucks for transport to the Environmental Restoration Disposal Facility. The scope of this plan includes an assessment of the organizations, procedures, and regulatory approvals necessary for the handling of investigation-derived waste containers and the subsequent transportation of materials to the Environmental Restoration Disposal Facility

  8. National Ignition Facility Cryogenic Target Systems Interim Management Plan

    International Nuclear Information System (INIS)

    Warner, B

    2002-01-01

    Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety and Health (ES and H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for

  9. Hydrogeologic investigations sampling plan: Revision 0

    International Nuclear Information System (INIS)

    1988-11-01

    The goal of this sampling plan is to identify and develop specific plans for those investigative actions necessary to: (1) characterize the hydrologic regime; (2) define the extent and impact of contamination; and (3) predict future contaminant migration for the Weldon Spring Site (WSS) and vicinity. The plan is part of the Weldon Spring Site Remedial Action Project (WSSRAP) sponsored by the US Department of Energy (DOE) and has been developed in accordance with US EPA Remedial Investigation (RI) and Data Quality Objective (DQO) guidelines. The plan consists of a sequence of activities including the evaluation of data, development of a conceptual model, identification of data uses and needs, and the design and implementation of a data collection program. Data will be obtained to: (1) confirm the presence or absence of contaminants; (2) define contaminant sources and modes of transport; (3) delineate extent of contaminant migration and predict future migration; and (4) provide information to support the evaluation and selection of remedial actions. 81 refs., 62 figs., 26 tabs

  10. 303-K Storage Facility closure plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-15

    Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

  11. Final work plan : environmental site investigation at Sylvan Grove, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Science Division)

    2012-07-15

    In 1998, carbon tetrachloride was found above the maximum contaminant level (MCL) of 5 {micro}g/L in groundwater from one private livestock well at Sylvan Grove, Kansas, by the Kansas Department of Health and Environment (KDHE). The 1998 KDHE sampling was conducted under the U.S. Department of Agriculture (USDA) private well sampling program. The Commodity Credit Corporation (CCC), a USDA agency, operated a grain storage facility in Sylvan Grove from 1954 to1966. Carbon tetrachloride is the contaminant of primary concern at sites associated with former CCC/USDA grain storage operations. Sylvan Grove is located in western Lincoln County, approximately 60 mi west of Salina (Figure 1.1). To determine whether the former CCC/USDA facility at Sylvan Grove is a potential contaminant source and its possible relationship to the contamination in groundwater, the CCC/USDA has agreed to conduct an investigation, in accordance with the Intergovernmental Agreement between the KDHE and the Farm Service Agency (FSA) of the USDA. This Work Plan presents historical data related to previous investigations, grain storage operations, local private wells and public water supply (PWS) wells, and local geologic and hydrogeologic conditions at Sylvan Grove. The findings from a review of all available documents are discussed in Section 2. On the basis of the analyses of historical data, the following specific technical objectives are proposed for the site investigation at Sylvan Grove: (1) Evaluate the potential source of carbon tetrachloride at the former CCC/USDA facility; (2) Determine the relationship of potential contamination (if present) at the former CCC/USDA facility to contamination identified in 1998 in groundwater samples from one private well to the west; and (3) Delineate the extent of potential contamination associated with the former CCC/USDA facility. The detailed scope of work is outlined in Section 3. The results of the proposed work will provide the basis for determining

  12. Investigating walking environments in and around assisted living facilities: a facility visit study.

    Science.gov (United States)

    Lu, Zhipeng

    2010-01-01

    This study explores assisted living residents' walking behaviors, locations where residents prefer to walk, and walking environments in and around assisted living facilities. Regular walking is beneficial to older adults' physical and psychological health. Yet frail older residents in assisted living are usually too sedentary to achieve these benefits. The physical environment plays an important role in promoting physical activity. However, there is little research exploring this relationship in assisted living settings. The researcher visited 34 assisted living facilities in a major Texas city. Methods included walk-through observation with the Assisted Living Facility Walking Environment Checklist, and interviews with administrators by open- and close-ended questions. The data from 26 facilities were analyzed using descriptive statistics (for quantitative data) and content analysis (for qualitative data). The results indicate that (a) residents were walking both indoors and outdoors for exercise or other purposes (e.g., going to destinations); (b) assisted living facility planning and design details-such as neighborhood sidewalk conditions, facility site selection, availability of seating, walking path configuration (e.g., looped/nonlooped path), amount of shading along the path, presence of handrails, existence of signage, etc.-may influence residents' walking behaviors; and (c) current assisted living facilities need improvement in all aspects to make their environments more walkable for residents. Findings of the study provide recommendations for assisted living facilities to improve the walkability of environments and to create environmental interventions to promote regular walking among their residents. This study also implies several directions for future research.

  13. Energy secretary Spencer Abraham announces department of energy 20-year science facility plan

    CERN Multimedia

    2003-01-01

    "In a speech at the National Press Club today, U.S. Energy Secretary Spencer Abraham outlined the Department of Energy's Office of Science 20-year science facility plan, a roadmap for future scientific facilities to support the department's basic science and research missions. The plan prioritizes new, major scientific facilities and upgrades to current facilities" (1 page).

  14. Certification Plan, low-level waste Hazardous Waste Handling Facility

    International Nuclear Information System (INIS)

    Albert, R.

    1992-01-01

    The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met

  15. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2002-01-01

    This 2002 Facility Work Plan (FWP) has been prepared as required by Module VII, Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received on December 6, 2000 (NMED, 2000a). This February 2002 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the most recent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA processcan be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable

  16. Smart facility location planning for Smart Cities: using GIS technology and facility provision standards for pro-active planning of social facilities to support smart growth

    CSIR Research Space (South Africa)

    Green, Chéri

    2016-08-01

    Full Text Available step toward “smart” planning processes to support smart cities of the future. A case study application in Cape Town is used to illustrate the application of the methodology of spatially matching supply and demand for facilities using GIS tools...

  17. Waste sampling and characterization facility (WSCF) maintenance implementation plan

    International Nuclear Information System (INIS)

    Heinemann, J.L.; Millard, G.E.

    1997-08-01

    This Maintenance Implementation Plan (MIP) is written to satisfy the requirements of the US Department of Energy (DOE) Order 4330.4B, Maintenance Management Program that specifies the general policy and objectives for the establishment of the DOE controlled maintenance programs. These programs provide for the management and performance of cost effective maintenance and repair of the DOE property, which includes facilities. This document outlines maintenance activities associated with the facilities operated by Waste Management Hanford, Inc. (WMH). The objective of this MIP is to provide baseline information for the control and execution of WMH Facility Maintenance activities relative to the requirements of Order 4330.4B, assessment of the WMH maintenance programs, and actions necessary to maintain compliance with the Order. Section 2.0 summarizes the history, mission and description of the WMH facilities. Section 3.0 describes maintenance scope and requirements, and outlines the overall strategy for implementing the maintenance program. Specific elements of DOE Order 4330.4B are addressed in Section 4.0, listing the objective of each element, a discussion of the WMH compliance methodology, and current implementation requirements with references to WMH and HNF policies and procedures. Section 5.0 addresses deviations from policy requirements, and Section 6.0 is a schedule for specific improvements in support of this MIP

  18. Environmental restoration plan for the transfer of surplus facilities to the Facility Transition Program at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1995-08-01

    This report will provide guidance on management, coordination, and integration of plans to transition facilities to the Facility Transition Program and activities as related to the Oak Ridge National Laboratory (ORNL) Environmental Restoration Program facilities. This report gives (1) guidance on the steps necessary for identifying ORNL surplus facilities, (2) interfaces of Surveillance and Maintenance (S and M) and Isotope Facility Deactivation program managers, (3) roles and responsibilities of the facility managers, and (4) initial S and M requirements upon acceptance into the Facility Transition Program

  19. The outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

    International Nuclear Information System (INIS)

    Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Ohto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; Nemoto, Nobuaki; Watahiki, Shunsuke; Hanawa, Yoshio; Tsuboi, Kazuaki; Ogasawara, Yasushi; Nemoto, Hiroyoshi; Echigoya, Shinichi; Ohtsuka, Kaoru; Onoue, Ryuji; Koike, Sumio; Gorai, Shigeru; Nishiyama, Yutaka; Kurosawa, Akihiko; Hanawa, Nobuhiro; Tobita, Kenji; Tabata, Shuzo; Fukasaku, Akitomi; Isozaki, Takanori; Akashi, Kazutomo; Takahashi, Kunihiro; Tsuji, Tomoyuki

    2009-07-01

    The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation. (author)

  20. Power facility plan and power supply plan of Japan in 1988

    Energy Technology Data Exchange (ETDEWEB)

    Yoshino, Shoji; Makino, Masao

    1988-06-01

    The power facility plan and the power supply plan for 1988 are described. The demand by non-industrial use will grow at an average of 3.8% for the 1986-97 period due to changes in the life style, construction and extension of buildings and increasing use of OA equipment although the power conservation is promoted. The industrial consumption will increase at only 1.2% a year due to the slowed growth and energy saving. As a result, the total demand will be 778,200 million kWh in 1997 with annual growth of 2.4%. The maximum demand will be 151,210 kW in 1997 with annual growth of 2.9%. The annual load rate will decrease to 56.9%, showing a continuously worsening utilization efficiency of power facilities. The development of 29 power units with total capacity of 2,760 MW is planned in 1988 for a stable power supply with a sufficient margin regarding maximum demand. The plan requires the investment of 3,700 billion yen, including the power transmission systems and substations. The power supply plan in 1988 is aimed at the effective operation of facilities and cost reduction by regional management under proper recognition of local characteristics of each power source, while maintaining a stable power supply with specified margins. (1 fig, 11 tabs)

  1. Risk management plan for the National Ignition Facility

    International Nuclear Information System (INIS)

    Brereton, S.; Lane, M.; Smith, C.; Yatabe, J.

    1998-01-01

    The National Ignition Facility (NIF) is a U.S. Department of Energy inertial confinement laser fusion facility, currently under construction at the Lawrence Livermore National Laboratory (LLNL). NIF is a critical tool for the Department of Energy (DOE) science- based Stockpile Stewardship and Management Program. In addition, it represents a major step towards realizing inertial confinement fusion as a source of energy. The NIF will focus 192 laser beams onto spherical targets containing a mixture of deuterium and tritium, causing them to implode. This will create the high temperatures and pressures necessary for these targets to undergo fusion. The plan is for NIF to achieve ignition (i.e., self-heating of the fuel) and energy gain (i.e., more fusion energy produced than laser energy deposited) in the laboratory for the first time. A Risk Management Plan was prepared for the NIF design and construction Project. The plan was prepared in accordance with the DOE Life Cycle Asset Management Good Practice Guide. The objectives of the plan were to: (1) identify the risks to the completion of the Project in terms of meeting technical and regulatory requirements, cost, and schedule, (2) assess the risks in terms of likelihood of occurrence and their impact potential relative to technical performance, ES ampersand H (environment, safety and health), costs, and schedule, and (3) address each risk in terms of suitable risk management measures. Major risk elements were identified for the NIF Project. A risk assessment methodology was developed, which was utilized to rank the Project risks with respect to one another. Those elements presenting greater risk were readily identified by this process. This paper describes that methodology and the results

  2. The role of SANRAD facility in quantitative and morphological investigation

    International Nuclear Information System (INIS)

    Nshimirimana, Robert; Beer, Frikkie de; Radebe, Mabuti

    2011-01-01

    The SANRAD (South African Neutron Radiography) facility hosts a neutron/X-ray tomography system, which is extensively being utilized in non-destructive examination experiments where it is necessary to determine the properties (e.g. size, porosity, permeability and morphology) of samples. Those properties have a great importance in a variety of fields such as nuclear shielding, paleontology, geosciences, anatomy and reverse engineering studies. Quantitative and morphological investigations require a tomography system capable of producing tomograms with a high spatial resolution and free of artefacts where specialized imaging software is applied in the investigations. The SANRAD facility is used by the scientific and engineering communities in their qualitative, quantitative and morphological investigations. The capability of the SANRAD facility to investigate qualitatively and quantitatively the internal structure of several objects non-destructively is demonstrated with special emphasis on the precision and accuracy of the system.

  3. Groundwater protection plan for the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Weekes, D.C.; Jaeger, G.K.; McMahon, W.J.; Ford, B.H.

    1996-01-01

    This document is the groundwater protection plan for the Environmental Restoration Disposal Facility (ERDF) Project. This plan is prepared based on the assumption that the ERDF will receive waste containing hazardous/dangerous constituents, radioactive constituents, and combinations of both. The purpose of this plan is to establish a groundwater monitoring program that (1) meets the intent of the applicable or relevant and appropriate requirements, (2) documents baseline groundwater conditions, (3) monitors those conditions for change, and (4) allows for modifications to groundwater sampling if required by the leachate management program. Groundwater samples indicate the occurrence of preexisting groundwater contamination in the uppermost unconfined aquifer below the ERDF Project site, as a result of past waste-water discharges in the 200 West Area. Therefore, it is necessary for the ERDF to establish baseline groundwater quality conditions and to monitor changes in the baseline over time. The groundwater monitoring program presented in this plan will provide the means to assess onsite and offsite impacts to the groundwater. In addition, a separate leachate management program will provide an indication of whether the liners are performing within design standards

  4. Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

    International Nuclear Information System (INIS)

    Albert, R.

    1992-01-01

    The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification

  5. Final Work Plan: Phase I Investigation at Bladen, Nebraska

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division. Applied Geosciences and Environmental Management Section; Yan, Eugene [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division

    2014-07-01

    The village of Bladen is a town of population approximately 237 in the northwest part of Webster County, Nebraska, 30 mi southwest of Hastings and 140 mi southwest of Lincoln, Nebraska. In 2000, the fumigant-related compound carbon tetrachloride was detected in public water supply well PWS 68-1, at a trace level. Low-level contamination, below the maximum contamination level (MCL) of 5.0 μg/L, has been detected intermittently in well PWS 68-1 since 2000, including in the last sample taken in July 2013. In 2006, the village installed a new well, PWS 2006-1, that remains free of contamination. Because the carbon tetrachloride found in well PWS 68-1 might be linked to historical use of fumigants containing carbon tetrachloride at grain storage facilities, including its former facility in Bladen, the CCC/USDA is proposing an investigation to (1) delineate the source and extent of the carbon tetrachloride contamination potentially associated with its former facility, (2) characterize pathways and controlling factors for contaminant migration in the subsurface, and (3) establish a basis for estimating potential health and environmental risks. The work will be performed in accordance with the Intergovernmental Agreement established between the NDEQ and the Farm Service Agency of the USDA. The site investigation at Bladen will be implemented in phases, so that data collected and interpretations developed during each phase can be evaluated to determine if a subsequent phase of investigation is warranted and, if warranted, to provide effective guidance for the subsequent investigation activities. This Work Plan identifies the specific technical objectives and defines the scope of work proposed for the Phase I investigation by compiling and evaluating historical data. The proposed investigation activities will be performed on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research

  6. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E.

    1998-10-02

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina.

  7. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    International Nuclear Information System (INIS)

    Palmer, E.

    1998-01-01

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina

  8. EXPERIENCE AND PLANS OF THE JLAB FEL FACILITY AS A USER FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Michelle D. Shinn

    2007-08-26

    Jefferson Lab's IR Upgrade FEL building was planned from the beginning to be a user facility, and includes an associated 600 m2 area containing seven laboratories. The high average power capability (multikilowatt-level) in the near-infrared (1-3 microns), and many hundreds of watts at longer wavelengths, along with an ultrafast (~ 1 ps) high PRF (10's MHz) temporal structure makes this laser a unique source for both applied and basic research. In addition to the FEL, we have a dedicated laboratory capable of delivering high power (many tens of watts) of broadband THz light. After commissioning the IR Upgrade, we once again began delivering beam to users in 2005. In this presentation, I will give an overview of the FEL facility and its current performance, lessons learned over the last two years, and a synopsis of current and future experiments.

  9. National Ignition Facility risk management plan, rev. 1

    International Nuclear Information System (INIS)

    Brereton, S J; Lane, M A

    1998-01-01

    The initial release of the National Ignition Facility (AUF) Risk Management Plan (LLNL, 1997a) was prepared in accordance with the DOE Life Cycle Asset Management Good Practice Guide (DOE, 1996a) and supported Critical Decision 3 (CD3), Approval to Initiate Construction (DOE, 1997a). The objectives of the plan were to: (1) Identify the risks to the completion of the Project in terms of meeting technical and regulatory requirements, cost, and schedule. (2) Assess the risks in terms of likelihood of occurrence and their impact potential relative to technical performance, ES and H (environmental, safety and health), costs, and schedule. (3) Address suitable risk mitigation measures for each identified risk. This revision of the Risk Management Plan considers project risks and vulnerabilities after CD3 (DOE, 1997a) was approved by the Secretary of Energy. During the one-year period since the initial release, the vulnerabilities of greatest concern have been the litigation of the Programmatic Environmental Impact Statement (PEIS) (DOE, 1996b) by a group of environmental organizations led by the Natural Resources Defense Council; the finding and successful clean-up of polychlorinated biphenyl (PCB)-filled electrical capacitors at the NIF site excavation; the FY98 congressional budget authorization and request for the FY99 budget authorization; funding for Inertial Confinement Fusion (ICF)/NIF programmatic activities (including French and other sources of funding); and finally, progress in the core science and technology, and optics program that form the basis for the NIF design

  10. Clean slate corrective action investigation plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    The Clean Slate sites discussed in this report are situated in the central portion of the Tonopah Test Range (TTR), north of the Nevada Test Site (NTS) on the northwest portion of the Nellis Air Force Range (NAFR) which is approximately 390 kilometers (km) (240 miles [mi]) northwest of Las Vegas, Nevada. These sites were the locations for three of the four Operation Roller Coaster experiments. These experiments evaluated the dispersal of plutonium in the environment from the chemical explosion of a plutonium-bearing device. Although it was not a nuclear explosion, Operation Roller Coaster created some surface contamination which is now the subject of a corrective action strategy being implemented by the Nevada Environmental Restoration Project (NV ERP) for the U.S. Department of Energy (DOE). Corrective Action Investigation (CAI) activities will be conducted at three of the Operation Roller Coaster sites. These are Clean Slate 1 (CS-1), Clean Slate 2 (CS-2), and Clean Slate 3 (CS-3) sites, which are located on the TTR. The document that provides or references all of the specific information relative to the various investigative processes is called the Corrective Action Investigation Plan (CAIP). This CAIP has been prepared for the DOE Nevada Operations Office (DOE/NV) by IT Corporation (IT).

  11. Clean slate corrective action investigation plan

    International Nuclear Information System (INIS)

    1996-05-01

    The Clean Slate sites discussed in this report are situated in the central portion of the Tonopah Test Range (TTR), north of the Nevada Test Site (NTS) on the northwest portion of the Nellis Air Force Range (NAFR) which is approximately 390 kilometers (km) (240 miles [mi]) northwest of Las Vegas, Nevada. These sites were the locations for three of the four Operation Roller Coaster experiments. These experiments evaluated the dispersal of plutonium in the environment from the chemical explosion of a plutonium-bearing device. Although it was not a nuclear explosion, Operation Roller Coaster created some surface contamination which is now the subject of a corrective action strategy being implemented by the Nevada Environmental Restoration Project (NV ERP) for the U.S. Department of Energy (DOE). Corrective Action Investigation (CAI) activities will be conducted at three of the Operation Roller Coaster sites. These are Clean Slate 1 (CS-1), Clean Slate 2 (CS-2), and Clean Slate 3 (CS-3) sites, which are located on the TTR. The document that provides or references all of the specific information relative to the various investigative processes is called the Corrective Action Investigation Plan (CAIP). This CAIP has been prepared for the DOE Nevada Operations Office (DOE/NV) by IT Corporation (IT)

  12. 190-C Facility <90 Day Storage Pad supplemental information to the Hanford facility contingency plan

    International Nuclear Information System (INIS)

    Little, N.C.

    1996-12-01

    The 190-C Facility <90 Day Storage Pad stores waste oils primarily contaminated with lead generated while draining equipment within the building of residual lubricating oils. Waste oils are packaged and stored in fifty-five gallon drums, or other containers permitted by the Site Specific Waste Management Instruction. Bechtel Hanford, Inc. (BHI) manual BHI-EE-02, Environmental Requirements Procedures, references this document. This document is to be used to demonstrate compliance with the contingency plan requirements in Washington Administrative Code, Chapter 173-303, Dangerous Waste Regulations, for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units (units). Refer to BHI-EE-02, for additional information

  13. State Environmental Policy Act (SEPA) Checklist for the 105-DR Large Sodium Fire Facility Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the DR defense reactor, which was shut down in 1964. The LSFF is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Clean closure is the proposed method of closure for the LSFF. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989). This closure plan presents a description of the facility, the history of wastes managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

  14. Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

    International Nuclear Information System (INIS)

    1994-10-01

    The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition

  15. Laser programs facility management plan for environment, safety, and health

    International Nuclear Information System (INIS)

    Cruz, G.E.

    1996-01-01

    The Lawrence Livermore National Laboratory's (LLNL) Laser Programs ES ampersand H policy is established by the Associate Director for Laser Programs. This FMP is one component of that policy. Laser Programs personnel design, construct and operate research and development equipment located in various Livermore and Site 300 buildings. The Programs include a variety of activities, primarily laser research and development, inertial confinement fusion, isotope separation, and an increasing emphasis on materials processing, imaging systems, and signal analysis. This FMP is a formal statement of responsibilities and controls to assure operational activities are conducted without harm to employees, the general public, or the environment. This plan identifies the hazards associated with operating a large research and development facility and is a vehicle to control and mitigate those hazards. Hazards include, but are not limited to: laser beams, hazardous and radioactive materials, criticality, ionizing radiation or x rays, high-voltage electrical equipment, chemicals, and powered machinery

  16. National ignition facility environment, safety, and health management plan

    International Nuclear Information System (INIS)

    1995-11-01

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

  17. Model business plan for a sterile insect production facility

    International Nuclear Information System (INIS)

    2008-01-01

    For over 50 years the sterile insect technique (SIT) is a pest control strategy which has been used for eradication, and more recently for suppression, containment and prevention, of unwanted insect pest populations. Examples of successful applications of SIT, almost always applied in conjunction with other control methods in an area-wide integrated approach, are available from around the world. The development and application of SIT has relied overwhelmingly on public or donor initiative and funding throughout its history, although the private sector has always been involved as participants, cooperators or partners in funding. The demand for SIT, and therefore the market for sterile insects, has increased in recent years. This increase coincides with the introduction of new pests through the expansion of global trade and, at the same time, widespread pressure to find alternatives to pesticides. Recent improvements in the technology supporting SIT facilitate its application and suggest lower costs can be achieved. The conditions are therefore met for a greater commercialization of the technique to bring it in line with other pest control approaches that are fully integrated into a market approach. Several challenges arise, however, in pursuing sterile insect production as a commercial venture, ranging from intellectual property protection to pricing of the product. Routine insurance requirements, for instance, are complicated by the biological aspects of the business. This report is aimed at facilitating private sector involvement in the production of sterile insects for use in pest control. It provides guidelines and tools to support the development of specific business plans for a new SIT venture. By providing an international perspective on such issues as initial capital costs and recurring operational expenditures for a sterile insect facility, it may be used to evaluate the feasibility of proceeding with the construction or expansion of a sterile insect

  18. Brookhaven National Laboratory's Accelerator Test Facility: research highlights and plans

    Science.gov (United States)

    Pogorelsky, I. V.; Ben-Zvi, I.

    2014-08-01

    The Accelerator Test Facility (ATF) at Brookhaven National Laboratory has served as a user facility for accelerator science for over a quarter of a century. In fulfilling this mission, the ATF offers the unique combination of a high-brightness 80 MeV electron beam that is synchronized to a 1 TW picosecond CO2 laser. We unveil herein our plan to considerably expand the ATF's floor space with an upgrade of the electron beam's energy to 300 MeV and the CO2 laser's peak power to 100 TW. This upgrade will propel the ATF even further to the forefront of research on advanced accelerators and radiation sources, supporting the most innovative ideas in this field. We discuss emerging opportunities for scientific breakthroughs, including the following: plasma wakefield acceleration studies in research directions already active at the ATF; laser wakefield acceleration (LWFA), where the longer laser wavelengths are expected to engender a proportional increase in the beam's charge while our linac will assure, for the first time, the opportunity to undertake detailed studies of seeding and staging of the LWFA; proton acceleration to the 100-200 MeV level, which is essential for medical applications; and others.

  19. Stormwater Pollution Prevention Plan - TA-60 Material Recycling Facility

    Energy Technology Data Exchange (ETDEWEB)

    Sandoval, Leonard Frank [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-01-31

    This Storm Water Pollution Prevention Plan (SWPPP) was developed in accordance with the provisions of the Clean Water Act (33 U.S.C. §§1251 et seq., as amended), and the Multi-Sector General Permit for Storm Water Discharges Associated with Industrial Activity (U.S. EPA, June 2015) issued by the U.S. Environmental Protection Agency (EPA) for the National Pollutant Discharge Elimination System (NPDES) and using the industry specific permit requirements for Sector P-Land Transportation and Warehousing as a guide. This SWPPP applies to discharges of stormwater from the operational areas of the TA- 60 Material Recycling Facility at Los Alamos National Laboratory. Los Alamos National Laboratory (also referred to as LANL or the “Laboratory”) is owned by the Department of Energy (DOE), and is operated by Los Alamos National Security, LLC (LANS). Throughout this document, the term “facility” refers to the TA-60 Material Recycling Facility. The current permit expires at midnight on June 4, 2020.

  20. Antares facility for inertial-fusion experiments: status and plans

    International Nuclear Information System (INIS)

    Goldstone, P.D.; Allen, G.; Jansen, H.; Saxman, A.; Singer, S.; Thuot, M.

    1982-01-01

    Antares is a large, 30 to 40 kJ CO 2 laser system which will provide a base for experiments to determine the efficiency with which 10 μm light can be used to drive target implosions while maintaining an acceptable level of preheat. Construction of the facility is in the final stages and diagnostics for initial experiments are being designed and constructed with operations scheduled to begin early in FY-84. After an initial shakedown period, we expect to perform a series of measurements to determine the energy scaling of hot electron temperature and target coupling efficiency in selected set of targets including simple spheres. We also expect to continue experiments, now planned for Helios, to determine whether CO 2 -produced ions are appropriate for driving inertial fusion targets with acceptable efficiency (Helios experiments have demonstrated that as much as 40% of the incident light can be converted to fast ions). Details of these experiments, as well as plans for further experiments, are still being defined

  1. Liquid effluent retention facility final-status groundwater monitoring plan

    International Nuclear Information System (INIS)

    Sweeney, M.D.; Chou, C.J.; Bjornstad, B.N.

    1997-09-01

    The following sections describe the groundwater-monitoring program for the Liquid Effluent Retention Facility (LERF). The LERF is regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The LERF is included in the open-quotes Dangerous Waste Portion of the Resource Conservation and Recovery Act Permit for the Treatment, Storage, and Disposal of Dangerous Waste, Permit WA890008967close quotes, (referred to herein as the Permit) (Ecology 1994) and is subject to final-status requirements for groundwater monitoring (WAC 173-303-645). This document describes a RCRA/WAC groundwater detection-monitoring program for groundwater in the uppermost aquifer system at the LERF. This plan describes the LERF monitoring network, constituent list, sampling schedule, statistical methods, and sampling and analysis protocols that will be employed for the LERF. This plan will be used to meet the groundwater monitoring requirements from the time the LERF becomes part of the Permit and through the post-closure care period, until certification of final closure

  2. Facility Response Plan (FRP) Points, Region 9, 2014, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — A Facility Response Plan (FRP) demonstrates a facility's preparedness to respond to a worst case oil discharge. Under the Clean Water Act, as amended by the Oil...

  3. Facility Response Plan (FRP) Points, Region 9, 2013, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — A Facility Response Plan (FRP) demonstrates a facility's preparedness to respond to a worst case oil discharge. Under the Clean Water Act, as amended by the Oil...

  4. Facility Response Plan (FRP) Points, Region 9, 2012, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — A Facility Response Plan (FRP) demonstrates a facility's preparedness to respond to a worst case oil discharge. Under the Clean Water Act, as amended by the Oil...

  5. Design verification and validation plan for the cold vacuum drying facility

    International Nuclear Information System (INIS)

    NISHIKAWA, L.D.

    1999-01-01

    The Cold Vacuum Drying Facility (CVDF) provides the required process systems, supporting equipment, and facilities needed for drying spent nuclear fuel removed from the K Basins. This document presents the both completed and planned design verification and validation activities

  6. Facility Response Plan (FRP) Inspected Points, Region 9, 2014, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — A Facility Response Plan (FRP) demonstrates a facility's preparedness to respond to a worst case oil discharge. Under the Clean Water Act, as amended by the Oil...

  7. 200 Areas Remedial Investigation/Feasibility Study Implementation Plan - Environmental Restoration Program

    International Nuclear Information System (INIS)

    Knepp, A. J.

    1999-01-01

    The 200 Areas Remedial Investigation/Feasibility Study Implementation Plan - Environmental Restoration Program (Implementation Plan) addresses approximately 700 soil waste sites (and associated structures such as pipelines) resulting from the discharge of liquids and solids from processing facilities to the ground (e.g., ponds, ditches, cribs,burial grounds) in the 200 Areas and assigned to the Environmental Restoration Program. The Implementation Plan outlines the framework for implementing assessment activities in the 200 Areas to ensure consistency in documentation, level of characterization, and decision making. The Implementation Plan also consolidates background information and other typical work plan materials, to serve as a single referenceable source for this type of information

  8. Preliminary rock mechanics laboratory: Investigation plan

    International Nuclear Information System (INIS)

    Oschman, K.P.; Hummeldorf, R.G.; Hume, H.R.; Karakouzian, M.; Vakili, J.E.

    1987-01-01

    This document presents the rationale for rock mechanics laboratory testing (including the supporting analysis and numerical modeling) planned for the site characterization of a nuclear waste repository in salt. This plan first identifies what information is required for regulatory and design purposes, and then presents the rationale for the testing that satisfies the required information needs. A preliminary estimate of the minimum sampling requirements for rock laboratory testing during site characterization is also presented. Periodic revision of this document is planned

  9. Dry-run of site investigation planning using the manual for preliminary investigation in Japan

    International Nuclear Information System (INIS)

    Akamura, Shigeki; Miwa, Tadashi; Tanaka, Tatsuya; Shiratsuchi, Hiroshi; Horio, Atsushi

    2011-01-01

    A stepwise site selection process has been adopted for geological disposal of HLW in Japan. Literature surveys, followed by preliminary investigations (PI) and, finally, detailed investigations in underground facilities will be carried out in the successive selection stages. In the PI stage, surface-based investigations such as borehole surveys and geophysical prospecting will be implemented. In order to conduct the PI appropriately and efficiently within a restricted timeframe and budget, planning and management of PI are very important. NUMO therefore compiled existing knowledge and experience in the planning and managing of investigations in the form of manuals to be used to improve and maintain internal expertise. The first editions of the two manuals were prepared on the basis of experience overseas, and then they were revised by taking technological environment, laws and regulation in Japan into consideration. This paper introduces the procedure of PI planning using manual as well as the results of the dry-run, with the Yokosuka area as a hypothetical PI area, where the monstraction study is under way. Based on the dry-run, applicability of the manual is checked and, at the same time, further revisions are made to improve the content. (author)

  10. Investigation plan for infiltration experiment in Olkiluoto

    International Nuclear Information System (INIS)

    Lehtinen, A.; Lindgren, S.; Ikonen, A.

    2008-11-01

    hydrological modelling to investigate the process of infiltration. The experiment makes it possible to extend the understanding of hydrogeology in the upper part of the bedrock, which will also help in future predictions. This report describes the plans on the experimental site, field investigations, data acquisition and interpretation, and modelling approaches. (orig.)

  11. Facility effluent monitoring plan for the 284-E and 284-W power plants

    International Nuclear Information System (INIS)

    Nickels, J.M.; Herman, D.R.

    1992-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. 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

  12. Test plan for the soils facility demonstration: A petroleum contaminated soil bioremediation facility

    International Nuclear Information System (INIS)

    Lombard, K.H.

    1994-01-01

    The objectives of this test plan are to show the value added by using bioremediation as an effective and environmentally sound method to remediate petroleum contaminated soils (PCS) by: demonstrating bioremediation as a permanent method for remediating soils contaminated with petroleum products; establishing the best operating conditions for maximizing bioremediation and minimizing volatilization for SRS PCS during different seasons; determining the minimum set of analyses and sampling frequency to allow efficient and cost-effective operation; determining best use of existing site equipment and personnel to optimize facility operations and conserve SRS resources; and as an ancillary objective, demonstrating and optimizing new and innovative analytical techniques that will lower cost, decrease time, and decrease secondary waste streams for required PCS assays

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-04-01

    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).

  14. Vulnerability Assessments and Resilience Planning at Federal Facilities. Preliminary Synthesis of Project

    Energy Technology Data Exchange (ETDEWEB)

    Moss, R. H. [Pacific Northwest National Lab. (PNNL)/Univ. of Maryland, College Park, MD (United States). Joint Global Change Research Inst.; Blohm, A. J. [Univ. of Maryland, College Park, MD (United States); Delgado, A. [Pacific Northwest National Lab. (PNNL)/Univ. of Maryland, College Park, MD (United States). Joint Global Change Research Inst.; Henriques, J. J. [James Madison Univ., Harrisonburg, VA (United States); Malone, E L. [Pacific Northwest National Lab. (PNNL)/Univ. of Maryland, College Park, MD (United States). Joint Global Change Research Inst.

    2015-08-15

    U.S. government agencies are now directed to assess the vulnerability of their operations and facilities to climate change and to develop adaptation plans to increase their resilience. Specific guidance on methods is still evolving based on the many different available frameworks. Agencies have been experimenting with these frameworks and approaches. This technical paper synthesizes lessons and insights from a series of research case studies conducted by the investigators at facilities of the U.S. Department of Energy and the Department of Defense. The purpose of the paper is to solicit comments and feedback from interested program managers and analysts before final conclusions are published. The paper describes the characteristics of a systematic process for prioritizing needs for adaptation planning at individual facilities and examines requirements and methods needed. It then suggests a framework of steps for vulnerability assessments at Federal facilities and elaborates on three sets of methods required for assessments, regardless of the detailed framework used. In a concluding section, the paper suggests a roadmap to further develop methods to support agencies in preparing for climate change. The case studies point to several preliminary conclusions; (1) Vulnerability assessments are needed to translate potential changes in climate exposure to estimates of impacts and evaluation of their significance for operations and mission attainment, in other words into information that is related to and useful in ongoing planning, management, and decision-making processes; (2) To increase the relevance and utility of vulnerability assessments to site personnel, the assessment process needs to emphasize the characteristics of the site infrastructure, not just climate change; (3) A multi-tiered framework that includes screening, vulnerability assessments at the most vulnerable installations, and adaptation design will efficiently target high-risk sites and infrastructure

  15. Investigating the Importance of Sports Facilities & Staff for Football Fans

    Directory of Open Access Journals (Sweden)

    Pinelopi Athanasopoulou

    2012-01-01

    Full Text Available (a Purpose: This study seeks to investigate the importance of facilities and staff for football fans in Greece. (b Design/methodology/approach: A survey was carried out during two matches of Superleague games with a convenience sample of 312 spectators. A structured questionnaire was used with scales based on previous research. (c Findings: Factor analysis revealed four reliable factor dimensions: facilities design; staff; facilities maintenance, and quick & easy access. Staff and quick & easy access are shown to be the most important dimensions for respondents followed by the other two. Results also indicated that there are significant differences in the importance assigned to these 4 factor dimensions among different levels of age; education; income, and marital status. (d Research limitations/implications: This study is limited to one sport and on a convenience sample of football fans. Future research can validate further these findings and increase their generalisability. (e Practical implications: The results of this study challenge sport managers to manage effectively the design of the stadium; the processes of entry and exit of fans; the environment of the game; and the quality of stadium facilities.

  16. Forensic investigation of suicide cases in major Greek correctional facilities.

    Science.gov (United States)

    Sakelliadis, E I; Vlachodimitropoulos, D G; Goutas, N D; Panousi, P I; Logiopoulou, A-P I; Delicha, E M; Spiliopoulou, C A

    2013-11-01

    According to Greek legislation the medico-legal investigation of deaths occurring in prisons is mandatory. Furthermore, in cases of suicide or of suspected suicide the contribution of medico-legal investigation is of grave importance. The current paper addresses the medico-legal investigation of suicide cases in Greek correctional facilities and aims to describe the current situation. Our study consists of the meticulous research in the data records of major Greek correctional facilities, for the time period 1999-2010. Official permission was obtained by the Hellenic Ministry of Justice, which provided us the access to the records. Data was also collected from the Piraeus Forensic Service, from the Department of Pathological Anatomy of the University of Athens and finally from our own records. Measures were taken to respect the anonymity of the cases. Data was collected for the social, penal, medical history as well as for the medico-legal investigation. It appears that 85.7% of suicide cases were transferred to the Prisoner's Hospital (p < 0.0001), the forensic pathologist who conducted the PME did not perform scene investigation in none of the 70 suicide cases. In a total of 70 cases, histopathological examination, was requested only in 30 cases (42.9%). Hanging was the preferred method for those who committed suicide, followed by the poisoning due to psychoactive substances. Understanding the mistakes made during the forensic investigation of suicide cases inside correctional facilities is necessary, in order to prevent them from occurring again in the future, by implementing appropriate new policies and guidelines. Crown Copyright © 2013. Published by Elsevier Ltd. All rights reserved.

  17. Achievements and Future Plans of CLIC Test Facilities

    CERN Document Server

    Braun, Hans Heinrich

    2001-01-01

    CTF2 was originally designed to demonstrate the feasibility of two-beam acceleration with high current drive beams and a string of 30 GHz CLIC accelerating structure prototypes (CAS). This goal was achieved in 1999 and the facility has since been modified to focus on high gradient testing of CAS's and 30 GHz single cell cavities (SCC). With these modifications, it is now possible to provide 30 GHz RF pulses of more than 150 MW and an adjustable pulselength from 3 to 15 ns. While the SCC results are promising, the testing of CAS's revealed problems of RF breakdown and related surface damage. As a consequence, a new R&D program has been launched to advance the understanding of RF breakdown processes, to improve surface properties, investigate new materials and to optimise the structure geometries of the CAS's. In parallel the construction of a new facility named CTF3 has started. CTF3 will mainly serve two purposes. The first is the demonstration of the CLIC drive beam generation scheme. CTF3 will acceler-a...

  18. Radiation protection planning for decommissioning of research reactor facilities

    International Nuclear Information System (INIS)

    Jackson, Roger; Harman, Neil; Craig, David; Fecitt, Lorna; Lobach, Yuri; Gorlinskij, Juri; Kolyadin, Vyacheslav; Pavlenko, Vytali

    2008-01-01

    The MR reactor at the Russian Research Centre Kurchatov Institute (RRCKI), Moscow was a 50 MW multipurpose material testing and research reactor equipped with nine experimental loop facilities to test prototype fuel for various nuclear power reactors being developed. The reactor was shut down in 1993 and de-fuelled. The experimental loops are located in basement rooms around the reactor. The nature of the research into the characteristics of fuel design and coolant chemistry resulted in fission products and activation products in the test loop equipment. Decommissioning of the loops therefore presents a number of challenges. In addition the city of Moscow has expanded such that the RRC KI is now surrounded by housing which had to be taken into account in the radiological protection planning. This paper describes the techniques proposed to undertake the dismantling operations in order to minimise the radiation exposure to workers and members of the public. Estimates have been made of the worker doses which could be incurred during the dismantling process and the environmental impacts which could occur. These are demonstrated to be as low as reasonably achievable. The work was funded by the UK Department of Business Enterprise and Regulatory Reform (DBERR) (formerly the Department of Trade and Industry) under the Nuclear Safety Programme (NSP) set up to address nuclear safety issues in the Former Soviet Union. (author)

  19. Investigation on calibration parameter of mammography calibration facilities at MINT

    International Nuclear Information System (INIS)

    Asmaliza Hashim; Wan Hazlinda Ismail; Md Saion Salikin; Muhammad Jamal Md Isa; Azuhar Ripin; Norriza Mohd Isa

    2004-01-01

    A mammography calibration facility has been established in the Medical Physics Laboratory, Malaysian Institute for Nuclear Technology Research (MINT). The calibration facility is established at the national level mainly to provide calibration services for radiation measuring test instruments or test tools used in quality assurance programme in mammography, which is being implemented in Malaysia. One of the accepted parameters that determine the quality of a radiation beam is the homogeneity coefficient. It is determined from the values of the 1 st and 2 nd Half Value Layer (HVL). In this paper, the consistency of the mammography machine beam qualities that is available in MINT, is investigated and presented. For calibration purposes, five radiation qualities namely 23, 25, 28, 30 and 35 kV, selectable from the control panel of the X-ray machine is used. Important parameters that are set for this calibration facility are exposure time, tube current, focal spot to detector distance (FDD) and beam size at specific distance. The values of homogeneity coefficient of this laboratory for the past few years tip to now be presented in this paper. Backscatter radiations are also considered in this investigation. (Author)

  20. Gas supply planning for new gas-fired electricity generation facilities

    International Nuclear Information System (INIS)

    Slocum, J.C.

    1990-01-01

    This paper explores several key issues in gas supply planning for new gas fired electric generation facilities. This paper will have two main sections, as follows: developing the gas supply plan for a gas-fired electricity generation facility and exploring key gas supply contract pricing issues

  1. Dual Axis Radiographic Hydrodynamic Test Facility mitigation action plan. Annual report for 1998

    Energy Technology Data Exchange (ETDEWEB)

    Haagenstad, T.

    1999-01-15

    This Mitigation Action Plan Annual Report (MAPAR) has been prepared as part of implementing the Dual Axis Radiographic Hydrodynamic Test Facility (DARHT) Mitigation Action Plan (MAP) to protect workers, soils, water, and biotic and cultural resources in and around the facility.

  2. Dual Axis Radiographic Hydrodynamic Test Facility mitigation action plan. Annual report for 1998

    International Nuclear Information System (INIS)

    Haagenstad, T.

    1999-01-01

    This Mitigation Action Plan Annual Report (MAPAR) has been prepared as part of implementing the Dual Axis Radiographic Hydrodynamic Test Facility (DARHT) Mitigation Action Plan (MAP) to protect workers, soils, water, and biotic and cultural resources in and around the facility

  3. Provision of family planning services in Tanzania: a comparative analysis of public and private facilities

    NARCIS (Netherlands)

    Kakoko, D.C.; Ketting, E.; Kamazima, S.R.; Ruben, R.

    2012-01-01

    Adherence to the policy guidelines and standards is necessary for family planning services. We compared public and private facilities in terms of provision of family planning services. We analyzed data from health facility questionnaire of the 2006 Tanzania Service Provision Assessment survey, based

  4. Family and Consumer Sciences: A Facility Planning and Design Guide for School Systems.

    Science.gov (United States)

    Maryland State Dept. of Education, Baltimore.

    This document presents design concepts and considerations for planning and developing middle and high school family and consumer sciences education facilities. It includes discussions on family and consumer sciences education trends and the facility planning process. Design concepts explore multipurpose laboratories and spaces for food/nutrition…

  5. 200 area liquid effluent facility quality assurance program plan. Revision 1

    International Nuclear Information System (INIS)

    Sullivan, N.J.

    1995-01-01

    Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities

  6. Hanford Facility resource conservation and recovery act permit general inspection plan

    International Nuclear Information System (INIS)

    Beagles, D.B.

    1995-12-01

    The Hanford Facility Resource Conservation and Recovery Act Permit, General Inspection Requirements, includes a requirement that general facility inspections be conducted of the 100, 200 East, 200 West, 300, 400, and 1100 Areas and the banks of the Columbia River. This inspection plan describes the activities that shall be conducted for a general inspection of the Hanford Facility

  7. Gas storage facilities. Investigation of their social value. Supplement

    International Nuclear Information System (INIS)

    1997-02-01

    The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

  8. Gas storage facilities. Investigation of their social value

    International Nuclear Information System (INIS)

    1997-02-01

    The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

  9. Field Lysimeter Test Facility for protective barriers: Experimental plan

    International Nuclear Information System (INIS)

    Kirkham, R.R.; Gee, G.W.; Downs, J.L.

    1987-12-01

    This document was first written in October 1986 and has been used to guide the design of the Field Lysimeter Test Facility (FLTF) and to promote discussions between research and engineering staff regarding the selection of barrier treatments for inclusion in the FLTF. The construction of the lysimeter facility was completed June 28, 1987. This document describes the facility, the treatments placed in each lysimeter, types of measurements made in each lysimeter, and a brief discussion of project activities related to quality assurance, safety, and funding requirements. The treatment description and figures have been updated to reflect the lysimeter facility as constructed. 12 refs., 6 figs., 5 tabs

  10. Chemical Hygiene Plan for Onsite Measurement and Sample Shipping Facility Activities

    International Nuclear Information System (INIS)

    Price, W.H.

    1998-01-01

    This chemical hygiene plan presents the requirements established to ensure the protection of employee health while performing work in mobile laboratories, the sample shipping facility, and at the onsite radiological counting facility. This document presents the measures to be taken to promote safe work practices and to minimize worker exposure to hazardous chemicals. Specific hazardous chemicals present in the mobile laboratories, the sample shipping facility, and in the radiological counting facility are presented in Appendices A through G

  11. Strategic planning and marketing research for older, inner-city health care facilities: a case study.

    Science.gov (United States)

    Wood, V R; Robertson, K R

    1992-01-01

    Numerous health care facilities, located in downtown metropolitan areas, now find themselves surrounded by a decaying inner-city environment. Consumers may perceive these facilities as "old," and catering to an "urban poor" consumer. These same consumers may, therefore, prefer to patronize more modern facilities located in suburban areas. This paper presents a case study of such a health care facility and how strategic planning and marketing research were conducted in order to identify market opportunities and new strategic directions.

  12. Microdosimetric investigations at the fast neutron therapy facility at Fermilab

    International Nuclear Information System (INIS)

    Langen, K.M.

    1997-01-01

    Microdosimetry was used to investigate three issues at the neutron therapy facility (NTF) at Fermilab. Firstly, the conversion factor from absorbed dose in A-150 tissue equivalent plastic to absorbed dose in ICRU tissue was determined. For this, the effective neutron kerma factor ratios, i.e., oxygen tissue equivalent plastic and carbon to A-150 tissue equivalent plastic, were measured in the neutron beam. An A-150 tissue equivalent plastic to ICRU tissue absorbed dose conversion factor of 0.92 ± 0.04 was determined. Secondly, variations in the radiobiological effectiveness (RBE) in the beam were mapped by determining variations in two related quantities, e * and R, with field size and depth in tissue. Maximal variation in e * and R of 9% and 15% respectively were determined. Lastly, the feasibility of utilizing the boron neutron capture reaction on boron-10 to selectively enhance the tumor dose in the NTF beam was investigated

  13. Life Sciences Space Station planning document: A reference payload for the Life Sciences Research Facility

    Science.gov (United States)

    1986-01-01

    The Space Station, projected for construction in the early 1990s, will be an orbiting, low-gravity, permanently manned facility providing unprecedented opportunities for scientific research. Facilities for Life Sciences research will include a pressurized research laboratory, attached payloads, and platforms which will allow investigators to perform experiments in the crucial areas of Space Medicine, Space Biology, Exobiology, Biospherics and Controlled Ecological Life Support System (CELSS). These studies are designed to determine the consequences of long-term exposure to space conditions, with particular emphasis on assuring the permanent presence of humans in space. The applied and basic research to be performed, using humans, animals, and plants, will increase our understanding of the effects of the space environment on basic life processes. Facilities being planned for remote observations from platforms and attached payloads of biologically important elements and compounds in space and on other planets (Exobiology) will permit exploration of the relationship between the evolution of life and the universe. Space-based, global scale observations of terrestrial biology (Biospherics) will provide data critical for understanding and ultimately managing changes in the Earth's ecosystem. The life sciences community is encouraged to participate in the research potential the Space Station facilities will make possible. This document provides the range and scope of typical life sciences experiments which could be performed within a pressurized laboratory module on Space Station.

  14. Closure Plan for the E-Area Low-Level Waste Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    2000-10-30

    A closure plan has been developed to comply with the applicable requirements of the U.S. Department of Energy Order 435.2 Manual and Guidance. The plan is organized according to the specifications of the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans.

  15. Closure Plan for the E-Area Low-Level Waste Facility

    International Nuclear Information System (INIS)

    Cook, J.R.

    2000-01-01

    A closure plan has been developed to comply with the applicable requirements of the U.S. Department of Energy Order 435.2 Manual and Guidance. The plan is organized according to the specifications of the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans

  16. LASL experimental engineered waste burial facility: design considerations and preliminary plan

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1980-01-01

    The LASL Experimental Engineered Waste Burial Facility is a part of the National Low-Level Waste Management Program on Shallow-Land Burial Technology. It is a test facility where basic information can be obtained on the processes that occur in shallow-land burial operations and where new concepts for shallow-land burial can be tested on an accelerated basis on an appropriate scale. The purpose of this paper is to present some of the factors considered in the design of the facility and to present a preliminary description of the experiments that are initially planned. This will be done by discussing waste management philosophies, the purposes of the facility in the context of the waste management philosophy for the facility, and the design considerations, and by describing the experiments initially planned for inclusion in the facility, and the facility site

  17. Joint Integration Test Facility (JITF) Engineering II Performance Measurement Plans

    National Research Council Canada - National Science Library

    Boucher, Joanne

    2001-01-01

    ..., effectiveness, and accountability in federal programs and spending. The plan establishes six separate performance measurements, which correlate directly to customer satisfaction, Intelligence Mission Application (IMA...

  18. The Pinellas Plant RCRA facility investigation - A case study

    International Nuclear Information System (INIS)

    Kilbury, Richard; Keshian, Berg; Farley, Dwain; Meyer, David; Ingle, David; Biedermann, Charles

    1992-01-01

    Under the direction of the U.S. Department of Energy Albuquerque Field Office Environmental Restoration Program, a Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) was completed at the Pinellas Plant to fulfill requirements of the Hazardous and Solid Waste Amendments of 1984 (HSWA) permit issued on February 9, 1990 by the U.S. Environmental Protection Agency (EPA). This RFI addressed potential contaminant releases and environmental conditions at 15 solid waste management units (SWMUs). The RFI characterization program began in April 1990 and was completed in May 1991. The scope of RFI data collection activities is presented in the Pinellas Plant RFI Workplan issued in May 1990 and approved by EPA on April 16, 1991. An RFI Report was submitted to EPA on September 1, 1991. This paper presents a summary of RFI results and conclusions. Primary environmental concerns at the Pinellas Plant are emphasized. (author)

  19. West Valley Demonstration Project facilities utilization plan for the existing facilities at the Western New York Nuclear Service Center

    International Nuclear Information System (INIS)

    Skillern, C.G.

    1986-05-01

    In 1980, Congress passed Public Law 96-368, the West Valley Demonstration Project (WVDP) Act. As a primary objective, the Act authorized the US Department of Energy (DOE) to solidify the high-level waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC) into a form suitable for transportation and disposal in a federal repository. This report will describe how WVDP proposes to use the existing WNYNSC Facilities in an efficient and technically effective manner to comply with Public Law 96-368. In support of the above cited law, the DOE has entered into a ''Cooperative agreement between the United States Department of Energy and the New York State Energy Research and Development Authority on the Western New York Nuclear Service Center at West Valley, New York.'' The state-owned areas turned over to the DOE for use are as follows: Process Plant, Waste Storage, Low-Level Waste Treatment Facility, Service Facilities, Plant Security, and Additional Facilities. The Facilities Utilization Plan (FUP) describes how the state-owned facilities will be utilized to complete the Project; it is divided into five sections as follows: Executive Summary - an overview; Introduction - the WVDP approach to utilizing the WNYNSC Facilities; WVDP Systems - a brief functional description of the system, list of equipment and components to be used and decontamination and decommissioning (D and D) support; WVDP Support Facilities; and Caveats that could effect or change the potential usage of a particular area

  20. An Examination of the Structure of Sustainable Facilities Planning Scale for User Satisfaction in Nigerian Universities

    Directory of Open Access Journals (Sweden)

    Abayomi Ibiyemi

    2014-09-01

    Full Text Available Universities are under increasing pressure to demonstrate that continuous performance improvement is being delivered for user satisfaction, but the importance of facilities planning as a student-staff focused tool needs to be emphasised. This research sought answers to questions relating to the underlying structure of sustainable facilities planning and user satisfaction, and the number of factors that make up the facilities planning scale. Three universities from the south-western part of Nigeria were selected randomly using ownership structure to define the cases: University of Lagos, Akoka, Lagos, Ladoke Akintola University of Technology, Ogbomoso and Joseph Ayo Babalola University, Ikeji Arakeji, each representing the Federal, State, and Private ownership. A questionnaire survey was used on a random sample of 651 staff and students from the three universities. Six hundred questionnaires were retrieved (response rate of 92.2%. An exploratory factor analysis was used to understand the responses and the interrelationships. The results showed a two-factor solution of ‘locational advantages and user needs’ and ‘adequacy of facilities/functional connection and four core determinants for acceptance. It is concluded that universities should factor student-staff focus points into their facilities planning schemes to optimise their service deliveries. The study contributes to the discussion on factor structure of sustainable facilities planning scale with a focus on students and staff of universities.   Keywords: Facilities planning, universities, data structure, factors, Nigeria.

  1. An Examination of the Structure of Sustainable Facilities Planning Scale for User Satisfaction in Nigerian Universities

    Directory of Open Access Journals (Sweden)

    Abayomi Ibiyemi

    2014-09-01

    Full Text Available Universities are under increasing pressure to demonstrate that continuous performance improvement is being delivered for user satisfaction, but the importance of facilities planning as a student-staff focused tool needs to be emphasised. This research sought answers to questions relating to the underlying structure of sustainable facilities planning and user satisfaction, and the number of factors that make up the facilities planning scale. Three universities from the south-western part of Nigeria were selected randomly using ownership structure to define the cases: University of Lagos, Akoka, Lagos, Ladoke Akintola University of Technology, Ogbomoso and Joseph Ayo Babalola University, Ikeji Arakeji, each representing the Federal, State, and Private ownership. A questionnaire survey was used on a random sample of 651 staff and students from the three universities. Six hundred questionnaires were retrieved (response rate of 92.2%. An exploratory factor analysis was used to understand the responses and the interrelationships. The results showed a two-factor solution of ‘locational advantages and user needs’ and ‘adequacy of facilities/functional connection and four core determinants for acceptance. It is concluded that universities should factor student-staff focus points into their facilities planning schemes to optimise their service deliveries. The study contributes to the discussion on factor structure of sustainable facilities planning scale with a focus on students and staff of universities. Keywords: Facilities planning, universities, data structure, factors, Nigeria.

  2. Scientific investigation plan for initial engineered barrier system field tests

    International Nuclear Information System (INIS)

    Wunan Lin.

    1993-02-01

    The purpose of this Scientific Investigation Plan (SIP) is to describe tests known as Initial Engineered Barrier System Field Tests (IEBSFT) and identified by Work Breakdown Structure as WBS 1.2.2.2.4. The IEBSFT are precursors to the Engineered Barrier System Field Test (EBSFT), WBS 1.2.2.2.4, to be conducted in the Exploratory Study Facility (ESF) at Yucca Mountain. The EBSFT and IEBSFT are designed to provide information on the interaction between waste packages (simulated by heated containers) and the surrounding rock mass, its vadose water, and infiltrated water. Heater assemblies will be installed in drifts or boreholes openings and heated to measure moisture movement during heat-up and subsequent cool-down of the rock mass. In some of the tests, infiltration of water into the heated rock mass will be studied. Throughout the heating and cooling cycle, instruments installed in the rock will monitor such parameters as temperature, moisture content, concentration of some chemical species, and stress and strain. Rock permeability measurements, rock and fluid (water and gas) sampling, and fracture pattern measurements will also be made before and after the test

  3. 111-B Metal Examination Facility Concrete Tanks Characterization Plan

    International Nuclear Information System (INIS)

    Encke, D.B.

    1997-08-01

    The 111-B Metal Examination Facility was a single-story, wood frame 'L'-shaped building built on a concrete floor slab. The facility served as a fuel failure inspection facility. Irradiated fuel pieces were stored and examined in two below grade concrete storage tanks filled with water. The tanks have been filled with grout to stabilize the contamination they contained, and overall dimensions are 5 ft 9 in. (1.5 m 22.8 cm ) wide, 9 ft 1 in. (2.7 m 2.54 cm ) deep, and 10 ft 8 in. (3.0 m 20.32 cm) long, and are estimated to weigh 39 tons. The tanks were used to store and examine failed fuel rods, using water as a radiation shield. The tanks were lined with stainless steel; however, drawings show the liner has been removed from at least one tank (south tank) and was partially filled with grout. The south tank was used to contain the Sample Storage Facility, a multi-level metal storage rack for failed nuclear fuel rods (shown in drawings H-1-2889 and -2890). Both tanks were completely grouted sometime before decontamination and demolition (D ampersand D) of the above ground facility in 1984. The 111-B Metal Examination Facility contained two concrete tanks located below floor level for storage and examination of failed fuel. The tanks were filled with concrete as part of decommissioning the facility prior to 1983 (see Appendix A for description of previous work). Funding for removal and disposal of the tanks ran out before they could be properly disposed

  4. Long range planning of radiotherapy facilities in the Netherlands

    NARCIS (Netherlands)

    Postma, T.J.B.M.; Terpstra, S.

    2000-01-01

    The subject of this paper is long range planning or policy development for healthcare in the Netherlands. Especially the co-ordinating function of planning will be discussed. In healthcare different actors or stakeholders are involved. Each of these actors may have their own interests, expectations,

  5. Screening criteria for siting waste management facilities: Regional Management Plan

    International Nuclear Information System (INIS)

    1986-01-01

    The Midwest Interstate Low-Level Radioactive Waste Commission (Midwest Compact) seeks to define and place into operation a system for low-level waste management that will protect the public health and safety and the environment from the time the waste leaves its point of origin. Once the system is defined it will be necessary to find suitable sites for the components of that waste management system. The procedure for siting waste management facilities that have been chosen by the compact is one in which a host state is chosen for each facility. The host state is then given the freedom to select the site. Sites will be needed of low-level waste disposal facilities. Depending on the nature of the waste management system chosen by the host state, sites may also be needed for regional waste treatment facilities, such as compactors or incinerators. This report provides example criteria for use in selecting sites for low-level radioactive waste treatment and disposal facilities. 14 refs

  6. Investigation on proper materials of a liner system for trench type disposal facilities of radioactive wastes from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Arikawa, Masanobu; Sakamoto, Yoshiaki

    2011-08-01

    The Low-level Radioactive Waste Disposal Project Center of Japan Atomic Energy Agency will settle on near surface disposal facilities with and without engineered barriers for radioactive wastes from research, industrial and medical facilities. Both of them are so called 'concrete pit type' and 'trench type', respectively. The technical standard of constructing and operating a disposal facility based on 'Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors' have been regulated partly by referring to that of 'Waste Management and Public Cleansing Law'. This means that the concrete pit type and the trench type disposal facility resemble an isolated type for specified industrial wastes and a non leachate controlled type final disposal site for stable industrial wastes, respectively. On the other, We plan to design a disposal facility with a liner system corresponding to a leachate controlled type final disposal site on a crucial assumption that radioactive wastes other than stable industrial wastes to be disposed into the trench type disposal facility is generated. By current nuclear related regulations in Japan, There are no technical standard of constructing the disposal facility with the liner system referring to that of 'Waste Management and Public Cleansing Law'. We investigate the function of the liner system in order to design a proper liner system for the trench type disposal facility. In this report, We investigated liner materials currently in use by actual leachate controlled type final disposal sites in Japan. Thereby important items such as tensile strength, durability from a view point of selecting proper liner materials were studied. The items were classified into three categories according to importance. We ranked proper liner materials for the trench type disposal facility by evaluating the important items per material. As a result, high density polyethylene(HDPE) of high elasticity type polymetric sheet was selected

  7. Russian Federal nuclear center facilities for nuclear spectroscopy investigations

    International Nuclear Information System (INIS)

    Ilkaev, R.I.; Punin, V.T.; Abramovich, S.N.

    2001-01-01

    Russian Federal Nuclear Center facilities for Spectroscopy investigation in the field of nuclear spectroscopy are described. Here are discussed basic properties of used radiation sources, facilities and technologies for target material production and manufacture of targets from rare, high-toxic or radioactive materials. Here are also reported basic features of complex detector systems and technologies for manufacture of scintillation detectors with special properties VNIIEF was founded as a weapons laboratory. The development of nuclear and thermonuclear bombs was followed by a wide complex of nuclear-physics investigations. Naturally, data on nuclear-physics properties of active and structure materials being part of nuclear weapons were of greatest interest.At the initial stage of work on the development of nuclear weapons the information on nuclear constants of materials including the most important neutron ones was rather scant. Data published in scientific literature had low exactness and were insecure. Results of measurements sometimes differed greatly by various groups of investigators. At the same time it was clear that, for example, a 1,5-times mistake in the fission cross-section could cause a several times mistake in the choice of uranium or plutonium mass, which is necessary for the bomb development. These circumstances determined importance of the nuclear-physics investigations. Demands on knowledge of process details occurring inside the nuclei conditioned by a problem of developing and improving of nuclear weapons and atomic power are rather limited. However, the further development of nuclear industry has proved a well-known point that this knowledge being accumulated forms a critical mass that leads to an explosive situation in the elaboration both of ideological and technological aspects of these problems. It is the tendency of inside development of nuclear science that has conditioned preparedness of knowledge about intranuclear processes for

  8. ORNL Surplus Facilities Management Program maintenance and surveillance plan for fiscal year 1984

    International Nuclear Information System (INIS)

    Coobs, J.H.; Myrick, T.E.

    1986-10-01

    The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. The purpose and objectives of the national program are set forth in the current SFMP Program Plan and include (1) the maintenance and surveillance of facilities awaiting decommissioning, (2) planning for the orderly decommissioning of these facilities, and (3) implementation of a program to accomplish the facility disposition in a safe, cost-effective, and timely manner. As outlined in the national program plan, participating SFMP contractors are required to prepare a formal plan that documents the maintenance and surveillance (M and S) programs established for each site. This report has been prepared to provide this documentation for those facilties included in the ORNL SFMP

  9. Stormwater Pollution Prevention Plan TA-60 Roads and Grounds Facility and Associated Sigma Mesa Staging Area

    Energy Technology Data Exchange (ETDEWEB)

    Sandoval, Leonard Frank [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-02-01

    This Stormwater Pollution Prevention Plan (SWPPP) is applicable to operations at the Technical Area -60 (TA-60) Roads and Grounds Facility and Associated Sigma Mesa Staging Area off Eniwetok Drive, in Los Alamos County, New Mexico.

  10. Straighttalk. The ideal master facility plan begins with business strategy and integrates operational improvement.

    Science.gov (United States)

    Powder, Scott; Brown, Richard E; Haupert, John M; Smith, Ryder

    2007-04-02

    Given the scarcity of capital to meet ever-growing demands for healthcare services, master facility planning has become more important than ever. Executives must align their master facility plans with their overall business strategy, incorporating the best in care- and service-delivery models. In this installment of Straight Talk, executives from two health systems--Advocate Health Care in Oak Brook, Ill. and Parkland Health & Hospital System in Dallas--discuss master facility planning. Modern Healthcare and PricewaterhouseCoopers present Straight Talk. The session on master facility planning was held on March 8, 2007 at Modern Healthcare's Chicago Headquarters. Charles Lauer, former vice president of publishing and editorial director at Modern Healthcare, was the moderator.

  11. Atmospheric Radiation Measurement (ARM) Climate Research Facility Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mather, James [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-04-01

    Mission and Vision Statements for the U.S. Department of Energy (DOE)’s Atmospheric Radiation Measurement (ARM) Climate Research Facility Mission The ARM Climate Research Facility, a DOE scientific user facility, provides the climate research community with strategically located in situ and remote-sensing observatories designed to improve the understanding and representation, in climate and earth system models, of clouds and aerosols as well as their interactions and coupling with the Earth’s surface. Vision To provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes to resolve the uncertainties in climate and Earth system models toward the development of sustainable solutions for the nation's energy and environmental challenges.

  12. Seismic qualification program plan for continued operation at DOE-SRS nuclear material processing facilities

    International Nuclear Information System (INIS)

    Talukdar, B.K.; Kennedy, W.N.

    1991-01-01

    The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.IA requirements. In addition, many of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) his developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards,for existing NMP facility structures to continue operation Professionals involved in similar effort at other DOE facilities may find the program useful

  13. Surplus Facilities and Resource Conservation and Recovery Act Closure program plan, fiscal year 1992

    International Nuclear Information System (INIS)

    Hughes, M.C.; Wahlen, R.K.; Winship, R.A.

    1991-10-01

    The Surplus Facilities and Resource Conservation and Recovery Act Closure program is responsible to US Department of Energy Field Office, Richland for the safe, cost-effective surveillance, maintenance, and decommissioning of surplus facilities at the Hanford Site. The Surplus Facilities and Resource Conservation and Recovery Act Closure program is also responsible to US Department of Energy Field Office, Richland for the program management of specific Resource Conservation and Recovery Act closures at the Hanford Site. This program plan addresses only the surplus facilities. The criteria used to evaluate each factor relative to decommissioning are based on the guidelines presented by the US Department of Energy Field Office, Richland, Environmental Restoration Division. The guidelines are consistent with the Westinghouse Hanford Company commitment to decommission Hanford Site retired facilities in the safest and most cost-effective way achievable. This document outlines the plan for managing these facilities until disposal

  14. Hanford Facility Resource Conservation and Recovery Act Permit General Inspection Plan

    International Nuclear Information System (INIS)

    Beagles, D.S.

    1995-02-01

    This inspection plan describes the activities that shall be conducted for a general inspection of the Hanford Facility. RCRA includes a requirement that general facility inspections be conducted of the 100, 200 East, 200 West, 300, 400, and 1100 areas and the banks of the Columbia River. This plan meets the RCRA requirements and also provides for scheduling of inspections and defines general and specific items to be noted during the inspections

  15. Environmental restoration contractor facility safety plan -- MO-561 100-D site remediation project

    International Nuclear Information System (INIS)

    Donahoe, R.L.

    1996-11-01

    This safety plan is applicable to Environmental Restoration Contractor personnel who are permanently assigned to MO-561 or regularly work in the facility. The MO-561 Facility is located in the 100-D Area at the Hanford Site in Richland, Washington. This plan will: (a) identify hazards potentially to be encountered by occupants of MO-561; (b) provide requirements and safeguards to ensure personnel safety and regulatory compliance; (c) provide information and actions necessary for proper emergency response

  16. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs.

  17. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    International Nuclear Information System (INIS)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs

  18. Final Work Plan: Targeted Investigation at York, Nebraska

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-08-01

    The targeted investigation at York will be implemented in phases, so that data collected and interpretations developed at each stage of the program can be evaluated to guide subsequent phases most effectively. Section 2 of this Work Plan presents a brief overview of the York site, its geologic and hydrologic setting, and the previous CCC/USDA investigations. Section 3, outlines the proposed technical program for the targeted investigation, and Section 4 describes the investigative methods to be employed. A community relations plan is in Section 5, and Section 6 includes health and safety information. In addition to this site-specific Work Plan, the Master Work Plan (Argonne 2002) developed by Argonne for CCC/USDA investigations in Nebraska should be consulted for complete details of the methods and procedures to be used at York.

  19. Experimental facilities for plate-out investigations and future work

    International Nuclear Information System (INIS)

    Muenchow, K.; Dederichs, H.; Iniotakis, N.; Sackmann, B.

    1981-01-01

    The safety of HTR under normal operation and accident conditions, the possibility of inspection, maintenance and repair or decontamination of single primary components as well as the safety of maintenance personnel are essentially determined by the transport- and deposition behaviour of the non gaseous fission - and activation products in the primary loop of the reactor. A comprehensive program has been started in 1969 in KFA in collaboration with various industrial firms and foreign institutions to investigate these problems. The program includes in-pile and out-pile experiments, simulating reactor conditions and also different laboratory experiments and extensive theoretical investigations. The aim of these efforts is to test experimentally the models and computercodes, which are used for prediction of transport and deposition behaviour of fission products for HTR's as well under normal as under accident conditions. Further more a verified dataset is to be established. In this paper a survey is given of the experimental facilities carried out by KFA or in cooperation with KFA

  20. Remedial Action Plan for Expanded Bioventing System Facility 6454

    National Research Council Canada - National Science Library

    1996-01-01

    This draft remedial action plan (RAP) presents the scope for an expanded bioventing system for in situ treatment of fuel-contaminated soils at Site 6454 at Vandenberg Air Force Base (AFB), California...

  1. Nuclear fuel cycle facilities in the world (excluding the centrally planned economies)

    International Nuclear Information System (INIS)

    1979-01-01

    Information on the existing, under construction and planned fuel cycle facilities in the various countries is presented. Some thirty countries have activities related to different nuclear fuel cycle steps and the information covers the capacity, status, location, and the names of owners of the facilities

  2. Environmental Control Plan for the Industrial Hygiene Field Services Facility; TOPICAL

    International Nuclear Information System (INIS)

    J. W. Donnelly

    2001-01-01

    This environmental control plan is for the Hanford Site's industrial hygiene field services facility, located in the 100-N Area. The facility is used for the maintenance and storage of respirators, respiratory equipment and testing, calibration and testing of industrial hygiene equipment, and asbestos fiber counting

  3. Standard format and content for emergency plans for fuel cycle and materials facilities

    International Nuclear Information System (INIS)

    1990-09-01

    This regulatory guides is being developed to provide guidance acceptable to the NRC staff on the information to be included in emergency plans and to establish a format for presenting the information. Use of a standard format will help ensure uniformity and completeness in the preparation of emergency plans. An acceptable emergency plan should describe the licensed activities conducted at the facility and the types of accidents that might occur. It should provide information on classifying postulated accidents and the licensee's procedures for notifying and coordinating with offsite authorities. The plan should provide information on emergency response measures that might be necessary, the equipment and facilities available to respond to an emergency, and how the licensee will maintain emergency preparedness capability. It should describe the records and reports that will be maintained. There should also be a section on recovery after an accident and plans for restoring the facility to a safe condition. 4 refs

  4. Minimum dose method for walking-path planning of nuclear facilities

    International Nuclear Information System (INIS)

    Liu, Yong-kuo; Li, Meng-kun; Xie, Chun-li; Peng, Min-jun; Wang, Shuang-yu; Chao, Nan; Liu, Zhong-kun

    2015-01-01

    Highlights: • For radiation environment, the environment model is proposed. • For the least dose walking path problem, a path-planning method is designed. • The path-planning virtual–real mixed simulation program is developed. • The program can plan walking path and simulate. - Abstract: A minimum dose method based on staff walking road network model was proposed for the walking-path planning in nuclear facilities. A virtual–reality simulation program was developed using C# programming language and Direct X engine. The simulation program was used in simulations dealing with virtual nuclear facilities. Simulation results indicated that the walking-path planning method was effective in providing safety for people walking in nuclear facilities

  5. Oral medicines for children in the European paediatric investigation plans

    NARCIS (Netherlands)

    van Riet-Nales, Diana A; Römkens, Erwin G A W; Saint-Raymond, Agnes; Kozarewicz, Piotr; Schobben, Alfred F A M; Egberts, Toine C G; Rademaker, Carin M A

    2014-01-01

    INTRODUCTION: Pharmaceutical industry is no longer allowed to develop new medicines for use in adults only, as the 2007 Paediatric Regulation requires children to be considered also. The plans for such paediatric development called Paediatric Investigation Plans (PIPs) are subject to agreement by

  6. Particular intervention plan of the Areva La Hague facility - 2012 edition

    International Nuclear Information System (INIS)

    2012-01-01

    The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Areva NC La Hague fuel reprocessing plant (located on the territories of Beaumont-Hague, Digulleville, Herqueville, Jobourg and Omonville-la-Petite towns, Manche, France) which comprises the totally decommissioned UP2 400 unit, and the UP2 800 production unit still in operation

  7. Planning for off-site response to radiation accidents in nuclear facilities

    International Nuclear Information System (INIS)

    1981-01-01

    The purpose of this publication is to give guidance to those who are responsible for the protection of the public in the event of an accident occurring at a land-based nuclear facility. This guidance should assist in the advance preparation of emergency response plans and implementing procedures. Basic principles of protective measures along with their advantages and disadvantages are discussed. Other principles related to emergency planning and the operational response to an emergency are outlined. Although the guidance is primarily oriented towards land-based nuclear power facilities, the guidance does have general application to other types of nuclear facility

  8. Planning for off-site response to radiation accidents in nuclear facilities

    International Nuclear Information System (INIS)

    1979-01-01

    The purpose of this manual is to give guidance to those who are responsible for the protection of the public in the event of an accident occurring at a land-based nuclear facility. This guidance should assist in the advance preparation of emergency response plans and implementing procedures. Basic principles of protective measures along with their advantages and disadvantages are discussed. Other principles related to emergency planning and the operational response to an emergency are outlined. Although the guidance is primarily oriented toward land-based nuclear power facilities, the guidance does have general application to other types of nuclear facilities

  9. Endangered Species Act and energy facility planning: compliance and conflict

    Energy Technology Data Exchange (ETDEWEB)

    Shreeve, D; Calef, C; Nagy, J

    1978-05-01

    New energy facilities such as coal mines, gasification plants, refineries, and power plants--because of their severe environmental impacts--may, if sited haphazardly, jeopardize endangered species. By law, conflicts between energy-facility siting and endangered species occurrence must be minimized. To assess the likelihood of such conflicts arising, the authors used data from the Fish and Wildlife Service, Endangered Species Office, that describe the species' ranges by county. This data set was matched with county-level occurrences of imminent energy developments to find counties of overlap and hence potential conflict. An index was developed to measure the likelihood of actual conflict occurring in such counties. Factors determining the index are: numbers of endangered species inhabiting the county, number of energy-related developments, and to what degree the county remains in a wild or undeveloped state. Maps were prepared showing (1) geographic ranges of endangered species by taxonomic groups (mammals, fish, etc.) and (2) counties of conflict.

  10. Plutonium reclamation facility (PRF, building 236-Z) layup plan

    International Nuclear Information System (INIS)

    ANDERSON, R.N.

    1999-01-01

    This document reviews each system inside PRF to determine the operation and maintenance requirements necessary to maintain safe and predictable system performance for facility systems needed to remain operational while minimizing the maintenance and surveillance being performed. Also covered are the actions required to place PRF in a safe layup configuration while minimizing hazards and taking into account the need for reactivation of certain equipment when cleanup work commences in the future

  11. Sampling and Analysis Plan for the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    Mihalic, M.A.

    1998-02-01

    This Sampling and Analysis Plan (SAP) provides the information and instructions to be used for sampling and analysis activities in the 233-S Plutonium Concentration Facility. The information and instructions herein are separated into three parts and address the Data Quality Objective (DQO) Summary Report, Quality Assurance Project Plan (QAP), and SAP

  12. 77 FR 3389 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2012-01-24

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants, State of West Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator Units, Plan Revision... final action to approve a revision to the West Virginia hospital/medical/infectious waste incinerator...

  13. 77 FR 3422 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2012-01-24

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; State of West Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator Units, Plan Revision... revision to the West Virginia hospital/medical/infectious waste incinerator (HMIWI) Section 111(d)/ 129...

  14. Five Recession-Driven Strategies for Planning and Managing Campus Facilities

    Science.gov (United States)

    Rudden, Michael S.

    2010-01-01

    Colleges and universities continue to face significant fiscal challenges in the current recession. A review of ongoing campus facilities planning projects, coupled with a review of more than 30 recent campus master planning requests for proposals and the relevant literature, indicates that colleges and universities are finding innovative ways to…

  15. 78 FR 34973 - Proposal for Sewage Sludge Incinerators State Plan for Designated Facilities and Pollutants; Indiana

    Science.gov (United States)

    2013-06-11

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 62 [EPA-R05-OAR-2013-0372; FRL-9820-9] Proposal for Sewage Sludge Incinerators State Plan for Designated Facilities and Pollutants; Indiana AGENCY... direct final rulemaking, Indiana's State Plan to control air pollutants from Sewage Sludge Incinerators...

  16. Federal Facility Compliance Act, Proposed Site Treatment Plan: Background Volume. Executive Summary

    International Nuclear Information System (INIS)

    1995-01-01

    This Federal Facility Compliance Act Site Treatment Plan discusses the options of radioactive waste management for Ames Laboratory. This is the background volume which discusses: site history and mission; framework for developing site treatment plans; proposed plan organization and related activities; characterization of mixed waste and waste minimization; low level mixed waste streams and the proposed treatment approach; future generation of TRU and mixed wastes; the adequacy of mixed waste storage facilities; and a summary of the overall DOE activity in the area of disposal of mixed waste treatment residuals

  17. Status of U.S. Plans for an Advanced ISOL Facility. A Brief Report

    International Nuclear Information System (INIS)

    Bertrand, F.E.

    1998-01-01

    A brief discussion is provided of the current status of plans to build an advanced ISOL radioactive ion beam facility in the US. Designs for this new facility, which was recommended as the next major construction project of the DOE Nuclear Physics Program Office, have been proposed by two US national laboratories, Argonne National Laboratory and Oak Ridge National Laboratory. The new facility will provide orders-of-magnitude higher radioactive beam currents than existing facilities of this type and will cost in the range of $250 million

  18. Implementation plan for deployment of Federal Interim Storage facilities for commercial spent nuclear fuel

    International Nuclear Information System (INIS)

    1986-12-01

    This document is the third annual report on plans for providing Federal Interim Storage (FIS) capacity. References are made to the first and second annual reports, as necessary. Background factors and aspects that were considered in the development of this deployment plan and activities and interactions considered to be required to implement an FIS program are discussed. A generic description of the approach that the Department plans to follow in deploying FIS facilities is also described

  19. Implementation plan for deployment of Federal Interim Storage facilities for commercial spent nuclear fuel

    International Nuclear Information System (INIS)

    1985-01-01

    This document is the second annual report on plans for providing Federal Interim Storage (FIS) capacity. References are made to the first annual report as necessary (DOE/RW-0003, 1984). Background factors and aspects that were considered in the development of this deployment plan and activities and interactions considered to be required to implement an FIS program are discussed. The generic approach that the Department plans to follow in deploying FIS facilities is also described

  20. Implementation plan for deployment of Federal Interim Storage facilities for commercial spent nuclear fuel

    International Nuclear Information System (INIS)

    1989-01-01

    This document is the sixth annual report on plans for providing FIS capacity. References are made to the first, second, third, fourth, and fifth annual reports, as necessary. Background factors and aspects that were considered in the development of this deployment plan and activities and interactions considered to be required to implement an FIS program are discussed. A generic description of the approach that the Department plans to follow in deploying FIS facilities is also described. 21 refs., 1 fig., 1 tab

  1. Federal Facilities Compliance Act, Draft Site Treatment Plan: Background Volume, Part 2, Volume 1

    International Nuclear Information System (INIS)

    1994-01-01

    This Draft Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed include: purpose and scope of the plan; site history and mission; draft plant organization; waste minimization; waste characterization; preferred option selection process; technology for treating low-level radioactive wastes and TRU wastes; future generation of mixed waste streams; funding; and process for evaluating disposal issues in support of the site treatment plan

  2. The Remote Handled Immobilization Low-Activity Waste Disposal Facility Environmental Permits and Approval Plan

    International Nuclear Information System (INIS)

    DEFFENBAUGH, M.L.

    2000-01-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational

  3. Planning study for advanced national synchrotron-radiation facilities

    International Nuclear Information System (INIS)

    1984-01-01

    A new generation of synchrotron-radiation sources based on insertion devices offers gains in photon-beam brilliance as large as the gains that present-day synchrotron sources provided over conventional sources. This revolution in synchrotron capability and its impact on science and technology will be as significant as the original introduction of synchrotron radiation. This report recommends that insertion-device technology be pursued as our highest priority, both through the full development of insertion-device potential on existing machines and through the building of new facilities

  4. DOE standard: Filter test facility quality program plan

    International Nuclear Information System (INIS)

    1999-02-01

    This standard was developed primarily for application in US Department of Energy programs. It contains specific direction for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should be sent to the Office of Nuclear Safety Policy and Standards (EH-31), US Department of Energy, Washington, DC 20585, by letter or by using the self-addressed Document Improvement Proposal form (DOE F 1300.3) appearing at the end of this document

  5. Methodologies for and Results of Planning later Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Auler, I.; Paul, R.; Petrasch, P.

    1996-01-01

    Cost and success of decommissioning and dismantling nuclear power plants or other nuclear facilities are very much related to the chosen strategy and their implementation in practice. The strategy to be developed depends on the specific boundary conditions in a certain country and plant. Inadequate planning and equipment considered too late cause delays in the project performance and improvisations with financial and radiological consequences. For the development of a decommissioning strategy for a nuclear power plant broad experience from past D and D-projects is very important. That experience is very helpful in assessing the importance of the many factors which determine the success or failure of strategic decisions Tools for the systematic recording and investigation of the needed measures and expenditures are available, eg. the decommissioning cost program STILLKO-2, which has been established as standard tool. (author)

  6. Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

    2013-09-30

    This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

  7. Involvement of the Public Health Authority in emergency planning and preparedness for nuclear facilities in Hungary

    International Nuclear Information System (INIS)

    Sztanyik, L.B.

    1986-01-01

    It is required by the Hungarian Atomic Energy Act and its enacting clause of 1980 that facilities established for the application of atomic energy be designed, constructed and operated in such a manner that abnormal operational occurrences can be avoided and unplanned exposures to radiation and radioactive substances can be prevented. The primary responsibility for planning and implementing emergency actions rests with the management of the operating organization. Thus one of the prerequisites of licensing the first nuclear power plant in Hungary was the preparation and submission for approval of an emergency plan by the operating organization. In addition to this, the council of the county where the power plant is located has also been obliged to prepare a complementary emergency plan, in co-operation with other regional and national authorities, for the prevention of consequences from an emergency that may extend beyond the site boundary of the plant. In preparing the complementary plan, the emergency plan of the facility had to be taken into account. Unlike most national authorities involved in nuclear matters, the Public Health Authority is involved in the preparation of plans for every kind of emergency in a nuclear facility, including even those whose consequences can probably be confined to the plant site. The paper discusses in detail the role and responsibility of the Public Health Authority in emergency planning and preparedness for nuclear facilities. (author)

  8. Computer Security Incident Response Planning at Nuclear Facilities

    International Nuclear Information System (INIS)

    2016-06-01

    The purpose of this publication is to assist Member States in developing comprehensive contingency plans for computer security incidents with the potential to impact nuclear security and/or nuclear safety. It provides an outline and recommendations for establishing a computer security incident response capability as part of a computer security programme, and considers the roles and responsibilities of the system owner, operator, competent authority, and national technical authority in responding to a computer security incident with possible nuclear security repercussions

  9. 300 Area Treated Effluent Disposal Facility permit reopener run plan

    International Nuclear Information System (INIS)

    Olander, A.R.

    1995-01-01

    The 300 Area Treated Effluent Disposal Facility (TEDF) is authorized to discharge treated effluent to the Columbia River by National Pollutant Discharge Elimination System permit WA-002591-7. The letter accompanying the final permit noted the following: EPA recognizes that the TEDF is a new waste treatment facility for which full scale operation and effluent data has not been generated. The permit being issued by EPA contains discharge limits that are intended to force DOE's treatment technology to the limit of its capability.'' Because of the excessively tight limits the permit contains a reopener clause which may allow limits to be renegotiated after at least one year of operation. The restrictions for reopening the permit are as follows: (1) The permittee has properly operated and maintained the TEDF for a sufficient period to stabilize treatment plant operations, but has nevertheless been unable to achieve the limitation specified in the permit. (2) Effluent data submitted by the permittee supports the effluent limitation modifications(s). (3) The permittee has submitted a formal request for the effluent limitation modification(s) to the Director. The purpose of this document is to guide plant operations for approximately one year to ensure appropriate data is collected for reopener negotiations

  10. Mixed Waste Management Facility, revised FY94 Plan

    International Nuclear Information System (INIS)

    Streit, R.

    1994-01-01

    This revision of the FY94 Plan incorporates changes to work during FY94 in response to the DOE request in the DOE KD-1 decision letter of June 28,1994. This letter provided guidance of both scope and budget profile in response to the Conceptual Design Report (CDR) issued by the MWMF Project in April, 1994. This work plan only addresses work for the remainder of FY94. A revised plan for the complete project is in development and will be issued separately. Since February, 1994, the MWMF Project has been operating on DOE guidance directing that work on the CDR be completed, that only other essential work be continued to maintain the project, and that costs be maintained at approximately the January, 1994 spending levels until a KD-1 decision was made. This has formed the basis for monthly reports through June, 1994. The baseline contained in this report will become the basis for reports during the remainder of FY94

  11. Los Alamos National Laboratory plans for a laboratory microfusion facility

    International Nuclear Information System (INIS)

    Harris, D.B.

    1988-01-01

    Los Alamos National Laboratory is actively participating in the National Laboratory Microfusion Facility (LMF) Scoping Study. We are currently performing a conceptual design study of a krypton-fluoride laser system that appears to meet all of the diver requirements for the LMF. A new theory of amplifier module scaling has been developed recently and it appears that KrF amplifier modules can be scaled up to output energies much larger than thought possible a few years ago. By using these large amplifier modules, the reliability and availability of the system is increased and its cost and complexity is decreased. Final cost figures will be available as soon as the detailed conceptual design is complete

  12. Planning of Eka Hospital Pekanbaru wastewater recycling facility

    Science.gov (United States)

    Jecky, A.; Andrio, D.; Sasmita, A.

    2018-04-01

    The Ministry of Public Works No. 06 2011 required the large scale of water to conserve the water resource, Eka Hospital Pekanbaru have to improve the sewage treatment plant through the wastewater recycling. The effluent from the plant can be used to landscape gardening and non-potable activities. The wastewater recycling design was done by analyzing the existing condition of thesewage treatment plant, determine the effluent quality standards for wastewater recycling, selected of alternative technology and processing, design the treatment unit and analyze the economic aspects. The design of recycling facility by using of combination cartridge filters processing, ultrafiltration membranes, and desinfection by chlorination. The wastewater recycling capacity approximately of 75 m3/day or 75% of the STP effluent. The estimated costs for installation of wastewater recycling and operation and maintenance per month are Rp 111,708,000 and Rp 2,498,000 respectively.

  13. Planning a 60Co irradiation facility for fruit preservation

    International Nuclear Information System (INIS)

    Yuan, H.C.

    1978-01-01

    A conceptual design for a conveyor system is proposed for use in fruit irradiation. The seasonal nature of the fruit harvest requires that the 60 Co source inventory should be sufficient to meet the demand at peak season, but this would be excessive at the beginning and towards the end of the harvest. Because of the short crop period the possibility of other irradiation services should be exploited to ensure full utilization of the facility. For successful extension of fruit shelf-life rigid practices in pre-irradiation treatment are essential and careful packaging is indispensable to the operation of the irradiator. Based on the time required for construction and equipment supply, a period of 18 months should be assumed for completion of the project. (author)

  14. Groundwater Monitoring Plan for the Z-Area Saltstone Facility

    International Nuclear Information System (INIS)

    Wells, D.

    2002-01-01

    Groundwater monitoring has been conducted at the Z-Area Saltstone Disposal Facility since 1987. At that time, groundwater monitoring was not required by the industrial landfill regulations, but a modest monitoring program was required by the operating permit. In 1996 SRS proposed a program based on direct push sampling. This program called for biennial direct push sampling within 25 feet of each waste-containing cell with additional samples being taken in areas where excessive cracking had been observed. The direct push proposal was accepted by The South Carolina Department of Health and Environmental Control (SCDHEC). The Industrial Solid Waste Landfill Regulations were revised in 1998 and now include requirements for groundwater monitoring. The major elements of those regulations and their application at Z-Area are discussed. These are a point of compliance, groundwater protection standards, the groundwater monitoring system, sampling and analysis, and data evaluation and reporting

  15. The 4843 Alkali Metal Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    1991-06-01

    The 4843 AMSF has been used primarily to provide a centralized building to receive and store dangerous and mixed alkali metal waste, including sodium and lithium, which has been generated at the Fast Flux Test Facility and at various other Hanford Site operations that used alkali metals. Most of the dangerous and mixed alkali metal waste received consists of retired equipment from liquid sodium processes. The unit continues to store material. In general, only solid alkali metal waste that is water reactive is stored at the 4843 AMSF. The 4843 AMSF will be closed in a manner consistent with Ecology guidelines and regulations (WAC 173-303-610). The general closure procedure is detailed as follows

  16. The plan to coordinate NEHRP post-earthquake investigations

    Science.gov (United States)

    Holzer, Thomas L.; Borcherdt, Roger D.; Comartin, Craig D.; Hanson, Robert D.; Scawthorn, Charles R.; Tierney, Kathleen; Youd, T. Leslie

    2003-01-01

    This is the plan to coordinate domestic and foreign post-earthquake investigations supported by the National Earthquake Hazards Reduction Program (NEHRP). The plan addresses coordination of both the NEHRP agencies—Federal Emergency Management Agency (FEMA), National Institute of Standards and Technology (NIST), National Science Foundation (NSF), and U. S. Geological Survey (USGS)—and their partners. The plan is a framework for both coordinating what is going to be done and identifying responsibilities for post-earthquake investigations. It does not specify what will be done. Coordination is addressed in various time frames ranging from hours to years after an earthquake. The plan includes measures for (1) gaining rapid and general agreement on high-priority research opportunities, and (2) conducting the data gathering and fi eld studies in a coordinated manner. It deals with identifi cation, collection, processing, documentation, archiving, and dissemination of the results of post-earthquake work in a timely manner and easily accessible format.

  17. Statistical sampling plan for the TRU waste assay facility

    International Nuclear Information System (INIS)

    Beauchamp, J.J.; Wright, T.; Schultz, F.J.; Haff, K.; Monroe, R.J.

    1983-08-01

    Due to limited space, there is a need to dispose appropriately of the Oak Ridge National Laboratory transuranic waste which is presently stored below ground in 55-gal (208-l) drums within weather-resistant structures. Waste containing less than 100 nCi/g transuranics can be removed from the present storage and be buried, while waste containing greater than 100 nCi/g transuranics must continue to be retrievably stored. To make the necessary measurements needed to determine the drums that can be buried, a transuranic Neutron Interrogation Assay System (NIAS) has been developed at Los Alamos National Laboratory and can make the needed measurements much faster than previous techniques which involved γ-ray spectroscopy. The previous techniques are reliable but time consuming. Therefore, a validation study has been planned to determine the ability of the NIAS to make adequate measurements. The validation of the NIAS will be based on a paired comparison of a sample of measurements made by the previous techniques and the NIAS. The purpose of this report is to describe the proposed sampling plan and the statistical analyses needed to validate the NIAS. 5 references, 4 figures, 5 tables

  18. Environmental Monitoring Plan, Nevada Test Site and support facilities

    International Nuclear Information System (INIS)

    1991-11-01

    This Environmental Monitoring Plan applies to the US Department of Energy's (DOE's) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Field Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this Environmental Monitoring Plan brings together in one document a description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA). The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards

  19. National Ignition Facility quality assurance plan for laser materials and optical technology

    Energy Technology Data Exchange (ETDEWEB)

    Wolfe, C.R.

    1996-05-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This subtier Quality Assurance Plan (QAP) applies to activities of the Laser Materials & Optical Technology (LM&OT) organization and its subcontractors. It responds to the NIF Quality Assurance Program Plan (QAPP, L-15958-2, NIF-95-499) and Department of Energy (DOE) Order 5700.6C. This Plan is organized according to 10 Quality Assurance (QA) criteria and subelements of a management system as outlined in the NIF QAPP. This Plan describes how those QA requirements are met. This Plan is authorized by the Associate Project Leader for the LM&OT organization, who has assigned responsibility to the Optics QA engineer to maintain this plan, with the assistance of the NIF QA organization. This Plan governs quality-affecting activities associated with: design; procurement; fabrication; testing and acceptance; handling and storage; and installation of NIF Project optical components into mounts and subassemblies.

  20. Integrated social facility location planning for decision support: Accessibility studies provide support to facility location and integration of social service provision

    CSIR Research Space (South Africa)

    Green, Cheri A

    2012-09-01

    Full Text Available for two or more facilities to create an integrated plan for development Step 6 Costing of development plan Case Study Access norms and thresholds guidelines in accessibility analysis Appropriate norms/provision guidelines facilitate both service... access norms and threshold standards ?Test the relationship between service demand and the supply (service capacity) of the facility provision points within a defined catchment area ?Promote the ?right?sizing? of facilities relative to the demand...

  1. National Biomedical Tracer Facility planning and feasibility study

    International Nuclear Information System (INIS)

    Ketchem, L.; Holmes, R.A.

    1991-01-01

    Since its establishment in mid-1989, the DOE Office of Isotope Production and Distribution has examined the recommendations of the Los Alamos Report and the Health and Environmental Research Advisory Committee (HERAC) Report. The main recommendation from these deliberations is for the DOE to establish an accelerator dedicated to biomedical radioisotope production. Representatives of the nuclear medicine community, meeting at a DOE workshop in August 1988, evaluated present and future needs for accelerator-produced radioisotopes. Workshop participants concluded in the Los Alamos Report that approximately 90% of their radioisotope needs could be met by a machine that delivers a 70 million electronic volts (MeV), 500-microamp proton beam. The HERAC Report provides more quantification of radioisotope needs, and included isotopes that can be produced effectively only at higher energies. An accelerator facility with an upper energy limit of 100 MeV and beam current of 750 to 1,000 microamps, could produce all important accelerator- produced radioisotopes in current use, as well as those isotopes judged to have future potential value in medical research and clinical practice. We therefore recommend that the NBTF have a 100-MeV proton beam accelerator with an extracted beam current of 750 to 1,000 microamps

  2. National Biomedical Tracer Facility planning and feasibility study

    Energy Technology Data Exchange (ETDEWEB)

    Ketchem, L. (ed.); Holmes, R.A.

    1991-03-02

    Since its establishment in mid-1989, the DOE Office of Isotope Production and Distribution has examined the recommendations of the Los Alamos Report and the Health and Environmental Research Advisory Committee (HERAC) Report. The main recommendation from these deliberations is for the DOE to establish an accelerator dedicated to biomedical radioisotope production. Representatives of the nuclear medicine community, meeting at a DOE workshop in August 1988, evaluated present and future needs for accelerator-produced radioisotopes. Workshop participants concluded in the Los Alamos Report that approximately 90% of their radioisotope needs could be met by a machine that delivers a 70 million electronic volts (MeV), 500-microamp proton beam. The HERAC Report provides more quantification of radioisotope needs, and included isotopes that can be produced effectively only at higher energies. An accelerator facility with an upper energy limit of 100 MeV and beam current of 750 to 1,000 microamps, could produce all important accelerator- produced radioisotopes in current use, as well as those isotopes judged to have future potential value in medical research and clinical practice. We therefore recommend that the NBTF have a 100-MeV proton beam accelerator with an extracted beam current of 750 to 1,000 microamps.

  3. National Biomedical Tracer Facility planning and feasibility study. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Ketchem, L. [ed.; Holmes, R.A.

    1991-03-02

    Since its establishment in mid-1989, the DOE Office of Isotope Production and Distribution has examined the recommendations of the Los Alamos Report and the Health and Environmental Research Advisory Committee (HERAC) Report. The main recommendation from these deliberations is for the DOE to establish an accelerator dedicated to biomedical radioisotope production. Representatives of the nuclear medicine community, meeting at a DOE workshop in August 1988, evaluated present and future needs for accelerator-produced radioisotopes. Workshop participants concluded in the Los Alamos Report that approximately 90% of their radioisotope needs could be met by a machine that delivers a 70 million electronic volts (MeV), 500-microamp proton beam. The HERAC Report provides more quantification of radioisotope needs, and included isotopes that can be produced effectively only at higher energies. An accelerator facility with an upper energy limit of 100 MeV and beam current of 750 to 1,000 microamps, could produce all important accelerator- produced radioisotopes in current use, as well as those isotopes judged to have future potential value in medical research and clinical practice. We therefore recommend that the NBTF have a 100-MeV proton beam accelerator with an extracted beam current of 750 to 1,000 microamps.

  4. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume I. Organization plan

    International Nuclear Information System (INIS)

    1981-12-01

    This plan and the accompanying MFTF-B Integrated Operations Plan are submitted in response to UC/LLNL Purchase Order 3883801, dated July 1981. The organization plan also addresses the specific tasks and trade studies directed by the scope of work. The Integrated Operations Plan, which includes a reliability, quality assurance, and safety plan and an integrated logistics plan, comprises the burden of the report. In the first section of this volume, certain underlying assumptions and observations are discussed setting the requirements and limits for organization. Section B presents the recommended structure itself. Section C Device Availability vs Maintenance and Support Efforts and Section D Staffing Levels and Skills provide backup detail and justification. Section E is a trade study on maintenance and support by LLNL staff vs subcontract and Section F is a plan for transitioning from the construction phase into operation. A brief summary of schedules and estimated costs concludes the volume

  5. Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

    International Nuclear Information System (INIS)

    HUNACEK, G.S.

    2000-01-01

    A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and 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 is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary

  6. Facility effluent monitoring plan for K area spent fuel storage basin

    International Nuclear Information System (INIS)

    Hunacek, G.S.

    1996-01-01

    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 impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in WHC-EP-0438-1, A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, and 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 is the second revision to the original annual report. Long-range integrity of the effluent monitoring system shall be ensured with updates of this report whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

  7. Facility Effluent Monitoring Plan for the Plutonium Finishing Plant (PFP); FINAL

    International Nuclear Information System (INIS)

    FRAZIER, T.P.

    1999-01-01

    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 impact employee or public safety or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. To ensure the long-range integrity of the effluent monitoring systems, an update to this facility effluent monitoring plan is required whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document is reviewed annually even if there are no operational changes, and is updated, at a minimum, every 3 years

  8. Quality Assurance Program Plan (QAPP) Waste Encapsulation and Storage Facility (WESF)

    International Nuclear Information System (INIS)

    ROBINSON, P.A.

    2000-01-01

    This Quality Assurance Plan describes how the Waste Encapsulation and Storage Facility (WESF) implements the quality assurance (QA) requirements of the Quality Assurance Program Description (QAPD) (HNF-Mp-599) for Project Hanford activities and products. This QAPP also describes the organizational structure necessary to successfully implement the program. The QAPP provides a road map of applicable Project Hanford Management System Procedures, and facility specific procedures, that may be utilized by WESF to implement the requirements of the QAPD

  9. Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Graf, F.A. Jr.

    1995-02-27

    This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System`s pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System.

  10. Facility Effluent Monitoring Plan for the 284-E and 284-W power plants

    International Nuclear Information System (INIS)

    Herman, D.R.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It 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. The 284-E and 284-W Power Plants are coal-fired plants used to generate steam. Electricity is not generated at these facilities. The maximum production of steam is approximately 159 t (175 tons)/h at 101 kg (225 lb)/in 2 . Steam generated at these facilities is used in other process facilities (i. e., the B Plant, Plutonium-Uranium Extraction Plant, 242-A Evaporator) for heating and process operations. The functions or processes associated with these facilities do not have the potential to generate radioactive airborne effluents or radioactive liquid effluents, therefore, radiation monitoring equipment is not used on the discharge of these streams. The functions or processes associated with the production of steam result in the use, storage, management and disposal of hazardous materials

  11. Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

    International Nuclear Information System (INIS)

    Graf, F.A. Jr.

    1995-01-01

    This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System's pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System

  12. Suggestions and comments about preliminary plans of ABNT 20:04.002-001 standard 'Seismic actions for nuclear facilities project'

    International Nuclear Information System (INIS)

    Soares, W.A.

    1984-01-01

    This paper presents an analysis of preliminary plans of standard 'seismic actions for nuclear facilities project'. This document presents since seismic event characterization up to details of structural project of nuclear facilities construction. (C.M.)

  13. Surveillance and Maintenance Plan for the Uranium Trioxide(UO3) Facility

    International Nuclear Information System (INIS)

    McGuire, J.J.

    1999-01-01

    This document provides a plan for implementing surveillance and maintenance (S and M) activities to ensure the Uranium Oxide(UO3) Facility is maintained in a safe, environmentally secure, and cost effective manner until subsequent closure during the final disposition phase of decommissioning. This plan has been prepared in accordance with the guidelines provided in the U.S. Department of Energy (DOE) Office of Environmental Management (EM) Decommissioning Resource Manual (DOE 1995) and Section 8.6 of TPA change form P-08-97-01 to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology, et al. 1996)

  14. An exploratory shaft facility in SALT: Draft shaft study plan

    International Nuclear Information System (INIS)

    1987-03-01

    This draft Shaft Study Plan describes a program of testing and monitoring in the Exploratory Shafts of a candidate high-level nuclear waste repository site in Deaf Smith County, Texas. The purpose of the programs to assist with site characterization in support of a determination of site suitability for development as a repository design and performance assessment evaluations. The program includes a variety of geological, geophysical, geomechanical, thermomechanical, and geohydrological testing and monitoring. The program is presented as a series of separate studies concerned with geological, geomechanical, and geohydrological site characterization, and with evaluating the mechanical and hydrological response of the site to construction of the shafts. The various studies, and associated test or monitoring methods are shown. The procedure used in developing the test program has been to initially identify the information necessary to satisfy (1) federal, state, and local requirements, and (2) repository program requirements. These information requirements have then been assessed to determine which requirements can be addressed wholly or in significant part by monitoring and testing from within the shafts. Test methods have been identified to address specific information requirements. 67 refs., 39 figs., 31 tabs

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

    International Nuclear Information System (INIS)

    Denney, R.D.

    1995-10-01

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

  16. Decontamination and Decommissioning at Small Nuclear Facilities: Facilitating the Submission of Decommissioning Funding Plans

    International Nuclear Information System (INIS)

    Minor, D.A.; Grumbles, A.

    2009-01-01

    This paper describes the efforts of the Washington State Department of Health to ensure that small nuclear facilities have the tools each needs to submit Decommissioning Funding Plans. These Plans are required by both the U.S. Nuclear Regulatory Commission (NRC) and in some states - in the case of Washington state, the Washington State Department of Health is the regulator of radioactive materials. Unfortunately, the guidance documents provided by the U.S. NRC pertain to large nuclear facilities, such as nuclear fuel fabrication plants, not the small nuclear laboratory nor small nuclear laundry that may also be required to submit such Plans. These small facilities are required to submit Decommissioning Funding Plans by dint of their nuclear materials inventory, but have only a small staff, such as a Radiation Safety Officer and few authorized users. The Washington State Department of Health and Attenuation Environmental Company have been working on certain tools, such as templates and spreadsheets, that are intended to assist these small nuclear facilities prepare compliant Decommissioning Funding Plans with a minimum of experience and effort. (authors)

  17. Planning solutions of sanitary facilities in modern residential buildings

    Directory of Open Access Journals (Sweden)

    Orlov Evgeniy Vladimirovich

    2015-01-01

    Full Text Available In the article the short historical review on the design of sanitary rooms and their configurations is given. The main errors of the recent years, which led to the decrease in accommodation convenience because of the wrong approach from both the architect and engineers, are given. It is possible to use a small useful area for sanitary facilities, but it is connected with the lack of possibility of connecting washing and dishwashers. The author considers the options of engineering equipment placement in sanitary rooms taking into account the convenience of use, safety, and also resource-saving aspect. Various solutions on the organization of heating and ventilation are provided. The possible technical solutions allowing solving a flooding problem of the first floors in elite housing estates in case of accident are offered with the help of full waterproofing of sanitary rooms, and also the whole area of the apartment. The main attention was focused on the improvements of sanitary rooms for one-room and two-room apartments, which are the most demanded in the modern market of real estate. Layout solutions of the reduced bathrooms on the placement of the necessary equipment with choice justification are provided. The attention is paid to the layout solution for modern kitchens on order to increase their comfort by the use of special two-section sinks, and also a grinder of food waste in order to allow to lower the load of the systems of rubbish disposal of a building, by dumping the crushed garbage in an internal sewer network. Various options of evolutionary development of sanitary rooms for increasing the comfort degree are given. First of all, the development should happen in the direction of not only sanitation and hygiene, but also of the maintenance of the physical health of the people living in the building. It can be carried out by increase in a useful area of sanitary rooms, installation of exercise machines, medical bathtubs and a Jacuzzi

  18. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-03-01

    Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase future decommissioning needs, the NRC staff began an in-depth review and re-evaluation of NRC's regulatory approach to decommissioning in 1975. Major technical studies on decommissioning have been initiated at Battelle Pacific Northwest Laboratory in order to provide a firm information base on the engineering methodology, radiation risks, and estimated costs of decommissioning light water reactors and associated fuel cycle facilities. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. The report sets forth in detail the NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  19. Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

  20. Groundwater Monitoring Plan for the 1301-N, 1324-N/NA, and 1325-N RCRA Facilities

    International Nuclear Information System (INIS)

    Hartman, Mary J.

    2001-01-01

    The 1301-N and 1325-N Liquid Waste Disposal Facilities, the 1324-N Surface Impoundment, and the 1324-NA Percolation Pond, located in the 100 N Area of the Hanford Site, are regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The closure plans for these facilities stipulate that groundwater is monitored according to the 100-N Pilot Project: Proposed Consolidated Groundwater Monitoring Program (BHI-00725). This document supplements the consolidated plan by providing information on sampling and analysis protocols, quality assurance, data management, and a conceptual model for the RCRA sites. Monitoring well networks, constituents, and sampling frequency remain the same as in the consolidated plan or the previous groundwater monitoring plan (Hartman 1996)

  1. Groundwater monitoring plan: 200 Areas treated effluent disposal facility (Project W-049H)

    International Nuclear Information System (INIS)

    Barnett, D.B.; Davis, J.D.; Collard, L.B.; Freeman, P.B.; Chou, C.J.

    1995-04-01

    This groundwater monitoring plan provides information that supports the US Department of Energy's application (DOE-RL 1994) for waste water discharge permit No. WA-ST-4502 from the State of Washington, under the auspices of Washington Administrative Code 173-216. The monitoring plan has two functions: (1) to summarize the results of a 3-yr characterization of the current hydrogeology and groundwater quality of the discharge site and (2) to provide plans for evaluating the effects of the facility's operation on groundwater quality and document compliance with applicable groundwater quality standards. Three wells were drilled to define the stratigraphy, evaluate sediment characteristics, and establish a groundwater monitoring net work for the discharge facility. These wells monitor groundwater quality upgradient and downgradient in the uppermost aquifer. This report proposes plans for continuing the monitoring of groundwater quality and aquifer characteristics after waste water discharges begin

  2. Engineering Task Plan for the Integrity Assessment Examination of Double-Contained Receiver Tanks (DCRT), Catch Tanks and Ancillary facilities

    International Nuclear Information System (INIS)

    BECKER, D.L.

    2000-01-01

    This Engineering Task Plan (ETP) presents the integrity assessment examination of three DCRTs, seven catch tanks, and two ancillary facilities located in the 200 East and West Areas of the Hanford Site. The integrity assessment examinations, as described in this ETP, will provide the necessary information to enable the independently qualified registered professional engineer (IQRPE) to assess the condition and integrity of these facilities. The plan is consistent with the Double-Shell Tank Waste Transfer Facilities Integrity Assessment Plan

  3. Mobilization plan for the Y-12 9409-5 tank storage facility RCRA closure plan. Final report. Revision 1

    International Nuclear Information System (INIS)

    1993-11-01

    This mobilization plan identifies the activities and equipment necessary to begin the field sampling for the Oak Ridge Y-12 9409-5 Diked Tank Storage Facility (DTSF) Resource Conservation and Recovery Act (RCRA) closure. Elements of the plan outline the necessary components of each mobilization task and identify whether SAIC or the Martin Marietta Energy Systems, Inc. Y-12 Environmental Restoration Division will be responsible for task coordination. Field work will be conducted in two phases: mobilization phase and soil sampling phase. Training and medical monitoring, access, permits and passes, decontamination/staging area, equipment, and management are covered in this document

  4. Investigation-Derived Waste Management Plan. Revision 2

    International Nuclear Information System (INIS)

    Molen, G.

    1995-01-01

    SRS has implemented a comprehensive environmental program to maintain compliance with environmental regulations and mitigate impacts to the environment. One element of the environmental program is the investigation of inactive waste units. Environmental Investigation-Derived Waste (IDW). IDW may include purge water , soil cuttings, drilling fluids, well pumping test and development water, decontamination solutions, contaminated equipment, and personal protection equipment (PPE). In cases where investigations confirm the presence of contamination and the IDW contains waste constituents in concentrations high enough to be of environmental or health concern, special management procedures are warranted. This IDW Management Plan describes specific SRS initiatives for IDW management. The goal is the development of a plan for prudent management of IDW from environmental investigations that is protective of human health and the environment

  5. 120-D-1 (100-D) Ponds supplemental information to the Hanford Facility Contingency Plan. Revision 2

    International Nuclear Information System (INIS)

    Petersen, S.W.; Zoric, J.P.

    1997-06-01

    This document is a supplement to the Hanford Facility Contingency Plan and provides the unit-specific information needed to fully comply with the Washington Administrative Code 173-303 for contingency plans. The 100-D ponds are unlined surface impoundments that were mainly used to dispose of nondangerous wastewater, The ponds are designated as a single treatment, storage, and/or disposal unit because of potential corrosive characteristics of the wastewater. No waste is currently present at the 100-D Ponds

  6. Radioactive and mixed waste management plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility

    International Nuclear Information System (INIS)

    1995-01-01

    This Radioactive and Mixed Waste Management Plan for the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory is written to meet the requirements for an annual report of radioactive and mixed waste management activities outlined in DOE Order 5820.2A. Radioactive and mixed waste management activities during FY 1994 listed here include principal regulatory and environmental issues and the degree to which planned activities were accomplished

  7. Monte Carlo studies for irradiation process planning at the Portuguese gamma irradiation facility

    International Nuclear Information System (INIS)

    Oliveira, C.; Salgado, J.; Botelho, M.L.M. Luisa; Ferreira, L.M.

    2000-01-01

    The paper describes a Monte Carlo study for planning the irradiation of test samples for microbiological validation of distinct products in the Portuguese Gamma Irradiation Facility. Three different irradiation geometries have been used. Simulated and experimental results are compared and good agreement is observed. It is shown that Monte Carlo simulation improves process understanding, predicts absorbed dose distributions and calculates dose uniformity in different products. Based on these results, irradiation planning of the product can be performed

  8. Capacity Planning for Batch and Perfusion Bioprocesses Across Multiple Biopharmaceutical Facilities

    OpenAIRE

    Siganporia, Cyrus C; Ghosh, Soumitra; Daszkowski, Thomas; Papageorgiou, Lazaros G; Farid, Suzanne S

    2014-01-01

    Production planning for biopharmaceutical portfolios becomes more complex when products switch between fed-batch and continuous perfusion culture processes. This article describes the development of a discrete-time mixed integer linear programming (MILP) model to optimize capacity plans for multiple biopharmaceutical products, with either batch or perfusion bioprocesses, across multiple facilities to meet quarterly demands. The model comprised specific features to account for products with fe...

  9. Microdosimetric investigation at the therapeutic proton beam facility of CATANA.

    Science.gov (United States)

    De Nardo, L; Moro, D; Colautti, P; Conte, V; Tornielli, G; Cuttone, G

    2004-01-01

    Proton beams (62 Mev) are used by the Laboratori Nazionali del Sud of the Italian Institute of Nuclear Physics to treat eye melanoma tumours at the therapeutic facility called CATANA. A cylindrical slim tissue-equivalent proportional counter (TEPC) of 2.7 mm external diameter has been used to compare the radiation quality of two spread-out Bragg peaks (SOBP) at the CATANA proton beam.

  10. Microdosimetric investigation at the therapeutic proton beam facility of Catana

    International Nuclear Information System (INIS)

    De Nardo, L.; Moro, D.; Colautti, P.; Conte, V.; Tornielli, G.; Cuttone, G.

    2004-01-01

    Proton beams (62 Mev) are used by the Laboratori Nazionali del Sud of the Italian Inst. of Nuclear Physics to treat eye melanoma tumours at the therapeutic facility called CATANA. A cylindrical slim tissue-equivalent proportional counter (TEPC) of 2.7 mm external diameter has been used to compare the radiation quality of two spread-out Bragg peaks (SOBP) at the CATANA proton beam. (authors)

  11. Implementation Plans for a Systems Microbiology and Extremophile Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Wiley, H. S.

    2009-04-20

    solve DOE problems. Recent advances in whole-genome sequencing for a variety of organisms and improvements in high-throughput instrumentation have contributed to a rapid transition of the biological research paradigm towards understanding biology at a systems level. As a result, biology is evolving from a descriptive to a quantitative, ultimately predictive science where the ability to collect and productively use large amounts of biological data is crucial. Understanding how the ensemble of proteins in cells gives rise to biological outcomes is fundamental to systems biology. These advances will require new technologies and approaches to measure and track the temporal and spatial disposition of proteins in cells and how networks of proteins and other regulatory molecules give rise to specific activities. The DOE has a strong interest in promoting the application of systems biology to understanding microbial function and this comprises a major focus of its Genomics:GTL program. A major problem in pursuing what has been termed “systems microbiology” is the lack of the facilities and infrastructure for conducting this new style of research. To solve this problem, the Genomics:GTL program has funded a number of large-scale research centers focused on either mission-oriented outcomes, such as bioenergy, or basic technologies, such as gene sequencing, high-throughput proteomics or the identification of protein complexes. Although these centers generate data that will be useful to the research community, their scientific goals are relatively narrow and are not designed to accommodate the general community need for advanced capabilities for systems microbiology research.

  12. AN INVESTIGATION ON THE FOREST ROAD PLANNING AND ROAD GROUND

    Directory of Open Access Journals (Sweden)

    Hafız Hulusi ACAR

    2001-01-01

    Full Text Available It is required that the capital used for construction of road must be technical, economical and used in its location. For this reason, the projects must be prepared for forest roads and all operations belong to roads must be guided according to these projects. In this investigation, available forest road network plan and constructed forest roads were investigated at the point of view technical and forest transportation. After this, it were studied to reach the highest exploitation rate as can as possible. Available forest road density were found as 11.9 m/ha in forest areas for Yesiltepe District. In this condition, exploitation rate was 78 %. After that, optimum forest road network were planned and road density were reached to 22 m/ha and exploitation rate to 86 %. Directed sample method were used from taking soil sample methods and samples were took in mixed system. According to results of the experiments, available forest roads were found in a good degree at the point of view endurance, pressing and transportation capacity. With these results, it is aimed to reach higher exploitation rate with given attention to landslide areas during planning of forest roads on the mountain areas such as Black Sea Region. For this reason, required importance must be given to planning of truck and logging roads. Ground analysis must be done and took care before during planning process of forest road network.

  13. Investigation on integrity of JMTR concrete structures, cooling system and utility facilities

    International Nuclear Information System (INIS)

    Ebisawa, Hiroyuki; Tobita, Kenji; Fukasaku, Akitomi; Kaminaga, Masanori

    2010-02-01

    The condition of facilities and components to be used for re-operation of the Japan Materials Testing Reactor (JMTR) from FY2011, was investigated before the refurbishment work. An investigation of aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, trench, canal, filter banks and for aged components of tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out from the beginning of FY2007. As a result, cracks of concrete structures such as the exhaust stack, a foundation of the UCL (Utility Cooling Line) elevated water tank were repaired and pipe linings of secondary cooling system were replaced. Motors of primary cooling pumps, pumps in the secondary cooling system and in other systems were decided to replace from viewpoints of future maintenance and improvement of reliability. Other components and the reactor building were decided to use continuously for a long-term by appropriate maintenance activities based on the long-term maintenance plan. In this paper, the aged-investigation for the JMTR reactor building, heat exchangers and emergency generators is presented. (author)

  14. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-11-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed.

  15. Emergency planning and preparedness for nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    Because of their inventories of radioactive materials nuclear facilities represent a hazard potential which, though comparable with that posed by other large technical facilities, demands particular protective measures to be taken. As a consequence of the extreme safety provisions, made, accidents with major impacts on the environment of nuclear facilities are excluded to the best human knowledge. However, as there are distinct limits to human planning and recognition, a residual risk remains despite all these precautions. In order to reduce that risk, recommendations for emergency protection in the environment of nuclear facilities have been drafted. To the extent in which measures are required outside the specific emergency protection plans apply which contain non-object related planning preparations. The recommendation also omits potential repercussions of nuclear accidents which might require measures in the sector of preventive health protection under the Radiation Protection Provisions act or the government measures to be taken. The recommendation is applied to German nuclear installations and those foreign installations whose proximity to the border requires planning measures to be taken on German territory in the sense of this recommendation. (author) [pt

  16. 78 FR 40015 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2013-07-03

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; District of Columbia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator Units AGENCY: Environmental... negative declaration for hospital/medical/infectious waste incinerator (HMIWI) units within the District of...

  17. 75 FR 78952 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-12-17

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; Commonwealth of Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative... Quality, 629 East Main Street, Richmond, Virginia 23219. FOR FURTHER INFORMATION CONTACT: James B. Topsale...

  18. 75 FR 78916 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-12-17

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants, Commonwealth of Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative... 19103. Copies of the State submittal are available at the Virginia Department of Environmental Quality...

  19. 78 FR 40087 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2013-07-03

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; District of Columbia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator Units AGENCY: Environmental...) section 111(d)/129 negative declaration for the District of Columbia for hospital/medical/infectious waste...

  20. 75 FR 73967 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-11-30

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants, State of Delaware; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative Declaration... Environmental Control, 89 Kings Highway, P.O. Box 1401, Dover, Delaware 19903. FOR FURTHER INFORMATION CONTACT...

  1. 75 FR 73996 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-11-30

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; State of Delaware; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative Declaration... Resources and Environmental Control, 89 Kings Highway, P.O. Box 1401, Dover, Delaware 19903. FOR FURTHER...

  2. Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

    Energy Technology Data Exchange (ETDEWEB)

    Dwyer, P.A.

    1991-10-01

    This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

  3. Monitoring plan for routine organic air emissions at the Radioactive Waste Management Complex Waste Storage Facilities

    International Nuclear Information System (INIS)

    Galloway, K.J.; Jolley, J.G.

    1994-06-01

    This monitoring plan provides the information necessary to perform routine organic air emissions monitoring at the Waste Storage Facilities located at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The Waste Storage Facilities include both the Type I and II Waste Storage Modules. The plan implements a dual method approach where two dissimilar analytical methodologies, Open-Path Fourier Transform Infrared Spectroscopy (OP-FTIR) and ancillary SUMMA reg-sign canister sampling, following the US Environmental Protection Agency (EPA) analytical method TO-14, will be used to provide qualitative and quantitative volatile organic concentration data. The Open-Path Fourier Transform Infrared Spectroscopy will provide in situ, real time monitoring of volatile organic compound concentrations in the ambient air of the Waste Storage Facilities. To supplement the OP-FTIR data, air samples will be collected using SUMMA reg-sign, passivated, stainless steel canisters, following the EPA Method TO-14. These samples will be analyzed for volatile organic compounds with gas chromatograph/mass spectrometry analysis. The sampling strategy, procedures, and schedules are included in this monitoring plan. The development of this monitoring plan is driven by regulatory compliance to the Resource Conservation and Recovery Act, State of Idaho Toxic Air Pollutant increments, Occupational Safety and Health Administration. The various state and federal regulations address the characterization of the volatile organic compounds and the resultant ambient air emissions that may originate from facilities involved in industrial production and/or waste management activities

  4. Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

    International Nuclear Information System (INIS)

    Dwyer, P.A.

    1991-10-01

    This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material

  5. 78 FR 34918 - Direct Final Approval of Sewage Sludge Incinerators State Plan for Designated Facilities and...

    Science.gov (United States)

    2013-06-11

    ... Approval of Sewage Sludge Incinerators State Plan for Designated Facilities and Pollutants; Indiana AGENCY... to control air pollutants from ``Sewage Sludge Incinerators'' (SSI). The Indiana Department of... unit,'' in part, as any device that combusts sewage sludge for the purpose of reducing the volume of...

  6. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-12-01

    The present decommissioning regulations contained in Sections 50.33(f) and 50.82 of 10 CFR part 50 require applicants for power reactor operating licenses to demonstrate that they can obtain the funds needed to meet both operating costs and estimated costs of shutdown and decommissioning. The development of detailed, specific decommissioning plans for nuclear power plants is not currently required until the licensee seeks to terminate his operating license. Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase the need for future decommissionings, the NRC staff began an in-depth review and reevaluation of NRC's regulatory approach to decommissioning in 1975. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. In response to comments from the public and states, and to information gained during the initial stage of execution of the plan, several modifications of the plan are now required. The revised overall report sets forth in detail the current NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  7. Software quality assurance plan for the National Ignition Facility integrated computer control system

    International Nuclear Information System (INIS)

    Woodruff, J.

    1996-11-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This Software Quality Assurance Plan (SQAP) applies to the activities of the Integrated Computer Control System (ICCS) organization and its subcontractors. The Plan describes the activities implemented by the ICCS section to achieve quality in the NIF Project's controls software and implements the NIF Quality Assurance Program Plan (QAPP, NIF-95-499, L-15958-2) and the Department of Energy's (DOE's) Order 5700.6C. This SQAP governs the quality affecting activities associated with developing and deploying all control system software during the life cycle of the NIF Project

  8. Calculation of parameters for inspection planning and evaluation: mixed-oxide fuel fabrication facilities

    International Nuclear Information System (INIS)

    Reardon, P.T.; Mullen, M.F.

    1982-08-01

    As part of Task C.35 (Calculation of Parameters for Inspection Planning and Evaluation) of the US Program of Technical Assistance to IAEA Safeguards, Pacific Northwest Laboratory has performed some quantitative analyses of IAEA inspection activities for mixed-oxide fuel fabrication facilities. There were four distinct efforts involved in this task. These were as follows: show the effect on a material balance verification of using two variables measurement methods in some strata; perform additional calculations for the reference facility described in STR-89; modify the INSPECT computer programs to be used as an after-inspection analysis tool, as well as a preinspection planning tool; provide written comments and explantations of text and graphs of the first draft of STR-89, Safeguards Considerations for Mixed-Oxide Fuel Element Fabrication Facilities, by W. Bahm, T. Shea, and D. Tolchenkov, System Studies Section, IAEA

  9. The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan

    Energy Technology Data Exchange (ETDEWEB)

    DEFFENBAUGH, M.L.

    2000-08-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement

  10. Work plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S&M) and as quickly and economical as possible. Implementation and completion of the deactivation project will further reduce the risks to the environment and to public safety and health. Furthermore, completion of the project will result in significant S&M cost savings in future years. The IFDP work plan defines the project schedule, the cost estimate, and the technical approach for the project. A companion document, the IFDP management plan, has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has adopted the strategy of deactivating the simple facilities first, to reduce the scope of the project and to gain experience before addressing more difficult facilities. A decision support system is being developed to identify the activities that best promote the project mission and result in the largest cost savings. This work plan will be reviewed and revised annually. Deactivation of IFDP facilities was initiated in FY 1994 and will be completed in FY 1999. The schedule for deactivation of facilities is shown. The total cost of the project is estimated to be $36M. The costs are summarized. Upon completion of deactivation, annual S&M costs of these facilities will be reduced from the current level of $5M per year to less than $1M per year.

  11. Work plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-08-01

    The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S and M) and as quickly and economical as possible. Implementation and completion of the deactivation project will further reduce the risks to the environment and to public safety and health. Furthermore, completion of the project will result in significant S and M cost savings in future years. The IFDP work plan defines the project schedule, the cost estimate, and the technical approach for the project. A companion document, the EFDP management plan, has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has adopted the strategy of deactivating the simple facilities first, to reduce the scope of the project and to gain experience before addressing more difficult facilities. A decision support system is being developed to identify the activities that best promote the project mission and result in the largest cost savings. This work plan will be reviewed and revised annually. Deactivation of EFDP Facilities was initiated in FY 1994 and will be completed in FY 2000. The schedule for deactivation of facilities is shown. The total cost of the project is estimated to be $51M. The costs are summarized. Upon completion of deactivation, annual S and M costs of these facilities will be reduced from the current level of $5M per year to less than $1M per year

  12. Planning, Management and Organizational Aspects of the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2013-08-01

    Many old reactors and other nuclear facilities worldwide are being actively dismantled or are candidates for decommissioning in the near term. A significant number of these facilities are located in Member States having little experience or expertise in planning and implementing state of the art decommissioning projects. Planning, management and organization are critical for the success of such projects. The main objective of IAEA technical activities related to decommissioning is to promote the exchange of lessons learned, thereby contributing to successful planning and implementation of decommissioning projects. Imperative for success is a better understanding of the decision making process, the comparison and selection of decommissioning plans and organizational provisions, and relevant issues affecting the entire decommissioning process. Topics addressed in this publication include details on development of the decommissioning plan, structuring of key project tasks, organizing the project management team, identifying key staffing positions and determining required workforce skills, and managing the transition from an operational phase to the decommissioning phase. It is expected that this project, and in particular the papers collected in this publication, will draw Member States' attention to the practicality and achievability of timely planning and smooth management of decommissioning projects, especially for smaller projects. Concluding reports summarizing the work undertaken under the aegis of a coordinated research project (CRP) on planning, management and organizational aspects in the decommissioning of nuclear facilities, and presented at the third and final research coordination meeting (RCM) held in Da Lat, Vietnam, 5-9 September 2011, are included in this publication. Operating experience and lessons learned during full scale applications, as well as national programmes and plans, are among the most significant achievements of the CRP and have been

  13. Planning, Management and Organizational Aspects of the Decommissioning of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Many old reactors and other nuclear facilities worldwide are being actively dismantled or are candidates for decommissioning in the near term. A significant number of these facilities are located in Member States having little experience or expertise in planning and implementing state of the art decommissioning projects. Planning, management and organization are critical for the success of such projects. The main objective of IAEA technical activities related to decommissioning is to promote the exchange of lessons learned, thereby contributing to successful planning and implementation of decommissioning projects. Imperative for success is a better understanding of the decision making process, the comparison and selection of decommissioning plans and organizational provisions, and relevant issues affecting the entire decommissioning process. Topics addressed in this publication include details on development of the decommissioning plan, structuring of key project tasks, organizing the project management team, identifying key staffing positions and determining required workforce skills, and managing the transition from an operational phase to the decommissioning phase. It is expected that this project, and in particular the papers collected in this publication, will draw Member States' attention to the practicality and achievability of timely planning and smooth management of decommissioning projects, especially for smaller projects. Concluding reports summarizing the work undertaken under the aegis of a coordinated research project (CRP) on planning, management and organizational aspects in the decommissioning of nuclear facilities, and presented at the third and final research coordination meeting (RCM) held in Da Lat, Vietnam, 5-9 September 2011, are included in this publication. Operating experience and lessons learned during full scale applications, as well as national programmes and plans, are among the most significant achievements of the CRP and have been

  14. Site Safety Plan for Lawrence Livermore National Laboratory CERCLA investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bainer, R.; Duarte, J.

    1993-07-01

    The safety policy of LLNL is to take every reasonable precaution in the performance of work to protect the environment and the health and safety of employees and the public, and to prevent property damage. With respect to hazardous agents, this protection is provided by limiting human exposures, releases to the environment, and contamination of property to levels that are as low as reasonably achievable (ALARA). It is the intent of this Plan to supply the broad outline for completing environmental investigations within ALARA guidelines. It may not be possible to determine actual working conditions in advance of the work; therefore, planning must allow the opportunity to provide a range of protection based upon actual working conditions. Requirements will be the least restrictive possible for a given set of circumstances, such that work can be completed in an efficient and timely fashion. Due to the relatively large size of the LLNL Site and the different types of activities underway, site-specific Operational Safety Procedures (OSPs) will be prepared to supplement activities not covered by this Plan. These site-specific OSPs provide the detailed information for each specific activity and act as an addendum to this Plan, which provides the general plan for LLNL Main Site operation.

  15. Development and use of consolidated criteria for evaluation of emergency preparedness plans for DOE facilities

    International Nuclear Information System (INIS)

    Lerner, K.; Kier, P.H.; Baldwin, T.E.

    1995-01-01

    Emergency preparedness at US Department of Energy (DOE) facilities is promoted by development and quality control of response plans. To promote quality control efforts, DOE has developed a review document that consolidates requirements and guidance pertaining to emergency response planning from various DOE and regulatory sources. The Criteria for Evaluation of Operational Emergency Plans (herein referred to as the Criteria document) has been constructed and arranged to maximize ease of use in reviewing DOE response plans. Although developed as a review instrument, the document also serves as a de facto guide for plan development, and could potentially be useful outside the scope of its original intended DOE clientele. As regulatory and DOE requirements are revised and added in the future, the document will be updated to stay current

  16. Transition plan: Project C-018H, 200-E Area Effluent Treatment Facility

    International Nuclear Information System (INIS)

    Connor, M.D.

    1994-01-01

    The purpose of this transition plan is to ensure an orderly transfer of project information to operations to satisfy Westinghouse Hanford Company (WHC) operational requirements and objectives, and ensure safe and efficient operation of Project C-018H, the 200-E Area Effluent Treatment Facility (ETF). This plan identifies the deliverables for Project C-018H upon completion of construction and turnover to WHC for operations, and includes acceptance criteria to objectively assess the adequacy of the contract deliverables in relation to present requirements. The scope of this plan includes a general discussion of the need for complete and accurate design basis documentation and design documents as project deliverables. This plan also proposes that a configuration management plan be prepared to protect and control the transferred design documents and reconstitute the design basis and design requirements, in the event that the deliverables and project documentation received from the contractor are less than adequate at turnover

  17. Federal Facility Compliance Act: Conceptual Site Treatment Plan for Lawrence Livermore National Laboratory, Livermore, California

    International Nuclear Information System (INIS)

    1993-10-01

    The Department of Energy (DOE) is required by section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (the Act), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The Act requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the State or EPA for approval, approval with modification, or disapproval. The Lawrence Livermore National Laboratory (LLNL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the Act and is being provided to California, the US Environmental Protection Agency (EPA), and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix 1.1 of this document. Please note that Appendix 1.1 appears as Appendix A, pages A-1 and A-2 in this document

  18. Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    This Waste Encapsulation Storage Facility (WESF) Dangerous Waste Training Plan (DWTP) applies to personnel who perform work at, or in support of WESF. The plan, along with the names of personnel, may be given to a regulatory agency inspector upon request. General workers, subcontractors, or visiting personnel who have not been trained in the management of dangerous wastes must be accompanied by an individual who meets the requirements of this training plan. Dangerous waste management includes handling, treatment, storage, and/or disposal of dangerous and/or mixed waste. Dangerous waste management units covered by this plan include: less-than-90-day accumulation area(s); pool cells 1-8 and 12 storage units; and process cells A-G storage units. This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units and the Less-than-90-Day Accumulation Areas

  19. Hazardous Waste Cerification Plan: Hazardous Waste Handling Facility, Lawrence Berkeley Laboratory

    International Nuclear Information System (INIS)

    1992-02-01

    The purpose of this plan is to describe the organization and methodology for the certification of hazardous waste (HW) handled in the Lawrence Berkeley Laboratory (LBL) Hazardous Waste Handling Facility (HWHF). The plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end- product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; and executive summary of the Quality Assurance Program Plan (QAPP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. The plan provides guidance from the HWHF to waste generators, waste handlers, and the Systems Group Manager to enable them to conduct their activities and carry out their responsibilities in a manner that complies with several requirements of the Federal Resource Conservation and Resource Recovery Act (RCRA), the Federal Department of Transportation (DOT), and the State of California, Code of Regulations (CCR), Title 22

  20. Planning of public healthcare facility using a location allocation modelling: A case study

    Science.gov (United States)

    Shariff, S. Sarifah Radiah; Moin, Noor Hasnah; Omar, Mohd

    2014-09-01

    Finding the correct location of any facility and determining the demands which are to be assigned to it is very crucial in public health service. This is to ensure that the public gain maximum benefits. This article analyzes the previous location decisions of public primary healthcare (PHC) facilities in the district of Kuala Langat, Malaysia. With total population of 220214 (in 2010), the PHC in the district is currently served by 28 facilities. The percentages of total population covered (in 2007) within the maximum allowable distance of 3km and 5km are 69.7 percent and 77.8 percent respectively. This is very low compared to the Malaysian National Health Policy of Health for All or 100 percent coverage. The determination of health facility location should be planned carefully to further increase effective primary health service to the nation that is required for economic sustainability.

  1. The planning of decommissioning activities within nuclear facilities - Generating a Baseline Decommissioning Plan

    International Nuclear Information System (INIS)

    Meek, N.C.; Ingram, S.; Page, J.

    2003-01-01

    BNFL Environmental Services has developed planning tools to meet the emerging need for nuclear liabilities management and decommissioning engineering both in the UK and globally. It can provide a comprehensive baseline planning service primarily aimed at nuclear power stations and nuclear plant. The paper develops the following issues: Decommissioning planning; The baseline decommissioning plan;The process; Work package; Compiling the information; Deliverables summary; Customer Benefits; - Planning tool for nuclear liability life-cycle management; - Robust and reliable plans based upon 'real' experience; - Advanced financial planning; - Ascertaining risk; - Strategy and business planning. The following Deliverables are mentioned:1. Site Work Breakdown Structure; 2. Development of site implementation strategy from the high level decommissioning strategy; 3. An end point definition for the site; 4. Buildings, operational systems and plant surveys; 5. A schedule of condition for the site; 6. Development of technical approach for decommissioning for each work package; 7. Cost estimate to WBS level 5 for each work package; 8. Estimate of decommissioning waste arisings for each work package; 9. Preparation of complete decommissioning programme in planning software to suit client; 10. Risk modelling of work package and overall project levels; 11. Roll up of costs into an overall cost model; 12. Cash flow, waste profiling and resource profiling against the decommissioning programme; 13. Preparation and issue of Final Report. Finally The BDP process is represented by a flowchart listing the following stages: [Power Station project assigned] → [Review project and conduct Characterisation review of power station] → [Identify work packages] → [Set up WBS to level 3] → [Assign work packages] → [Update WBS to level 4] →[Develop cost model] → [Develop logic network] → [Develop risk management procedure] ] → [Develop project strategy document]→ [Work package

  2. Corrective Action Investigation Plan for Corrective Action Unit 232: Area 25 Sewage Lagoons, Nevada Test Site, Nevada, Revision 0

    International Nuclear Information System (INIS)

    1999-01-01

    The Corrective Action Investigation Plan for Corrective Action Unit 232, Area 25 Sewage Lagoons, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U.S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U. S. Department of Defense. Corrective Action Unit 232 consists of Corrective Action Site 25-03-01, Sewage Lagoon. Corrective Action Unit 232, Area 25 Sewage Lagoons, received sanitary effluent from four buildings within the Test Cell ''C'' Facility from the mid-1960s through approximately 1996. The Test Cell ''C'' Facility was used to develop nuclear propulsion technology by conducting nuclear test reactor studies. Based on the site history collected to support the Data Quality Objectives process, contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, Resource Conservation and Recovery Act metals, petroleum hydrocarbons, polychlorinated biphenyls, pesticides, herbicides, gamma emitting radionuclides, isotopic plutonium, isotopic uranium, and strontium-90. A detailed conceptual site model is presented in Section 3.0 and Appendix A of this Corrective Action Investigation Plan. The conceptual model serves as the basis for the sampling strategy. Under the Federal Facility Agreement and Consent Order, the Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of corrective action alternatives in the Corrective Action Decision Document

  3. 7 CFR Appendix D to Subpart E of... - Alcohol Production Facilities Planning, Performing, Development and Project Control

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 14 2010-01-01 2009-01-01 true Alcohol Production Facilities Planning, Performing... of Part 1980—Alcohol Production Facilities Planning, Performing, Development and Project Control (I..., without recourse to the Government, for the settlement and satisfaction of all contractual and...

  4. Surveillance and Maintenance Plan for the Plutonium Uranium Extraction (PUREX) Facility

    International Nuclear Information System (INIS)

    Woods, P.J.

    1998-05-01

    This document provides a plan for implementing surveillance and maintenance (S ampersand M) activities to ensure the Plutonium Uranium Extraction (PUREX) Facility is maintained in a safe, environmentally secure, and cost-effective manner until subsequent closure during the final disposition phase of decommissioning. This plan has been prepared in accordance with the guidelines provided in the U.S. Department of Energy (DOE), Office of Environmental Management (EM) Decommissioning Resource Manual (DOE/EM-0246) (DOE 1995), and Section 8.6 of TPA change form P-08-97-01 to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology, et al. 1996). Specific objectives of the S ampersand M program are: Ensure adequate containment of remaining radioactive and hazardous material. Provide security control for access into the facility and physical safety to surveillance personnel. Maintain the facility in a manner that will minimize potential hazards to the public, the environment, and surveillance personnel. Provide a plan for the identification and compliance with applicable environmental, safety, health, safeguards, and security requirements

  5. Horonobe Underground Research Laboratory Project. Plans for surface-based investigations. Phase 1

    International Nuclear Information System (INIS)

    Goto, Junichi; Hama, Katsuhiro

    2003-10-01

    The Horonobe Underground Research Laboratory Project is an investigation project which is planned over 20 years. The investigations are conducted in the three phases: investigations from surface (Phase 1), investigations during construction of the underground facility (Phase 2) and investigations using the facility (Phase 3). Taking into account the results from 'H12: Project of Establish the Scientific and Technical Basis for HLW Disposal in Japan - Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan-' (JNC, 2000), research and development goals for the Horonobe URL project were re-defined as follows; a) Development of investigation technologies for the geological environment, b) Development of monitoring technologies for the geological environment, c) Study on the long-term stability of the geological environment, d) Development of the basis for engineering technologies in deep underground, e) Verification of technologies for engineered barriers, f) Development of detailed designing technologies of the repositories, and g) Improvement of safety assessment methodologies. Investigations for the goals a) to d) and e) to g) are conducted in the 'Geoscientific Research' and 'Research and Development on Geological Disposal', respectively. In Phase 1, a 'laboratory construction area' of a few kilometers square is selected based on the results from early stage investigations. Subsequent investigations are concentrated in the selected area and its periphery. Acquisition of data by surface-based investigations, modeling of the geological environment and predictions of changes in the geological environment caused by the construction of the underground facility, are conducted in a) Development of investigation technologies for the geological environment. Development and installation of monitoring equipments and data acquisition prior to the construction of the underground facility fall under b) Development of monitoring technologies

  6. Project Management Plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1995-04-01

    The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition suitable for an extended period of minimum surveillance and maintenance (S ampersand M) and as quickly and economically as possible. Implementation and completion of the deactivation project will further reduce the already small risks to the environment and to public safety and health. Furthermore, the project should result in significant S ampersand M cost savings in the future. The IFDP management plan has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has adopted a strategy to deactivate the simple facilities first, to reduce the scope of the project, and to gain experience before addressing more difficult facilities. A decision support system is being developed to identify those activities, that best promote the project mission and result in largest cost savings. The Work Plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory (Energy Systems 1994) defines the project schedule, the cost estimate, and the technical approach for the project

  7. Investigation of plasma–surface interaction at plasma beam facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kurnaev, V., E-mail: kurnaev@plasma.mephi.ru [National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe sh. 31, 115409 Moscow (Russian Federation); Vizgalov, I.; Gutorov, K. [National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe sh. 31, 115409 Moscow (Russian Federation); Tulenbergenov, T.; Sokolov, I.; Kolodeshnikov, A.; Ignashev, V.; Zuev, V.; Bogomolova, I. [Institute of Atomic Energy, National Nuclear Center the Republic of Kazakhstan, Street Krasnoarmejsky, 10, 071100 Kurchatov (Kazakhstan); Klimov, N. [SRC RF TRINITI, ul. Pushkovykh, vladenie 12, Troitsk, 142190 Moscow (Russian Federation)

    2015-08-15

    The new Plasma Beam Facility (PBF) has been put into operation for assistance in testing of plasma faced components at Material Science Kazakhstan Tokamak (KTM). PBF includes a powerful electron gun (up to 30 kV, 1 A) and a high vacuum chamber with longitudinal magnetic field coils (up to 0.2 T). The regime of high vacuum electron beam transportation is used for thermal tests with power density at the target surface up to 10 GW/m{sup 2}. The beam plasma discharge (BPD) regime with a gas-puff is used for generation of intensive ion fluxes up to 3 ⋅ 10{sup 22} m{sup −2} s{sup −1}. Initial tests of the KTM PBF’s capabilities were carried out: various discharge regimes, carbon deposits cleaning, simultaneous thermal and ion impacts on radiation cooled refractory targets. With a water-cooled target the KTM PBF could be used for high heat flux tests of materials (validated by the experiment with W mock-up at the PR-2 PBF)

  8. Investigation for the ecology in areas nearby a nuclear facility

    International Nuclear Information System (INIS)

    Qin Suyun; Zhou Caiyun; Zhou Zirong; Chen Wenying; Zhen Zhijiang

    1995-03-01

    Studies were undertaken for the general ecological environment around the evaporating ponds and Gobi desert areas receiving the low and very low level radioactive waste water from a nuclear facility and for the transport of radionuclides in food chains were undertaken. On basis of obtained results the following conclusions were made: (1) In consequence of controlled releases of low level radioactive waste water, a steady specific ecosystem had formed. (2) Concentration of radionuclides in sediments, soils, terrestrial and aquatic wild plants and animals, agricultural products irrigated with very low level radioactive waste water, and tissues of sheep pastured in very low level radioactive water drainage areas, were higher significantly than that of non-contaminated areas. (3) Radioactive waste water discharging might result in potential exposure to members of residents. The critical radionuclide was 137 Cs, and the critical pathway was ingesting polluted waterfowls of evaporating pond. On basis of very conservative assessing the maximum intake of 137 Cs of individual of local resident was 1.0 x 10 4 Bq·a -1 corresponding to 50% of ALI of individual of population. Maximum amount of redistribution of radioactive material as a result of carrying by migrating birds under extreme conditions might be about 10 7 Bq·a -1 . (16 refs., 9 tabs., 1 fig.)

  9. Investigations concerning fire-induced accidents in nuclear facilities

    International Nuclear Information System (INIS)

    Lamuth, P.; Lernout, L.A.; Bonneval, F.; Cottaz, M.

    1996-01-01

    In the context of fire protection in technical buildings of French nuclear facilities, three principles have been adopted: prevention, detection and fire-fighting. Their implementation makes it possible on the one hand to limit the fire ignition and the fire growth, and on the other hand to prevent fire extent which would lead to unavailability of several safety related equipment. Although progress has been made in this direction, the fire risks have still not been eliminated. It is therefore essential to evaluate the fire effects and to assess their consequences. To this end, three main R and D programs have been conducted into fires. Part I sets out the fire PSA methodology used for a 900 MWe PWR. Part II gives an outline of two fire and ventilation computer codes useful for the fire PSA. Finally, part III gives an outline of the tests already performed and those currently under way in the two laboratories of the Institut de Protection et de Surete Nucleaire (IPSN) in order to qualify the codes and provide useful information for the safety assessment. (author)

  10. Investigation for the ecology in areas nearby a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Suyun, Qin; Caiyun, Zhou; Zirong, Zhou; Wenying, Chen; Zhijiang, Zhen [Ministry of Nuclear Industry, Taiyuan, SX (China). Inst. of Radiation Protection

    1995-03-01

    Studies were undertaken for the general ecological environment around the evaporating ponds and Gobi desert areas receiving the low and very low level radioactive waste water from a nuclear facility and for the transport of radionuclides in food chains were undertaken. On basis of obtained results the following conclusions were made: (1) In consequence of controlled releases of low level radioactive waste water, a steady specific ecosystem had formed. (2) Concentration of radionuclides in sediments, soils, terrestrial and aquatic wild plants and animals, agricultural products irrigated with very low level radioactive waste water, and tissues of sheep pastured in very low level radioactive water drainage areas, were higher significantly than that of non-contaminated areas. (3) Radioactive waste water discharging might result in potential exposure to members of residents. The critical radionuclide was {sup 137}Cs, and the critical pathway was ingesting polluted waterfowls of evaporating pond. On basis of very conservative assessing the maximum intake of {sup 137}Cs of individual of local resident was 1.0 x 10{sup 4} Bq{center_dot}a{sup -1} corresponding to 50% of ALI of individual of population. Maximum amount of redistribution of radioactive material as a result of carrying by migrating birds under extreme conditions might be about 10{sup 7} Bq{center_dot}a{sup -1}. (16 refs., 9 tabs., 1 fig.).

  11. Monte Carlo investigation of collapsed versus rotated IMRT plan verification.

    Science.gov (United States)

    Conneely, Elaine; Alexander, Andrew; Ruo, Russell; Chung, Eunah; Seuntjens, Jan; Foley, Mark J

    2014-05-08

    IMRT QA requires, among other tests, a time-consuming process of measuring the absorbed dose, at least to a point, in a high-dose, low-dose-gradient region. Some clinics use a technique of measuring this dose with all beams delivered at a single gantry angle (collapsed delivery), as opposed to the beams delivered at the planned gantry angle (rotated delivery). We examined, established, and optimized Monte Carlo simulations of the dosimetry for IMRT verification of treatment plans for these two different delivery modes (collapsed versus rotated). The results of the simulations were compared to the treatment planning system dose calculations for the two delivery modes, as well as to measurements taken. This was done in order to investigate the validity of the use of a collapsed delivery technique for IMRT QA. The BEAMnrc, DOSXYZnrc, and egs_chamber codes were utilized for the Monte Carlo simulations along with the MMCTP system. A number of different plan complexity metrics were also used in the analysis of the dose distributions in a bid to qualify why verification in a collapsed delivery may or may not be optimal for IMRT QA. Following the Alfonso et al. formalism, the kfclin,frefQclin,Q correction factor was calculated to correct the deviation of small fields from the reference conditions used for beam calibration. We report on the results obtained for a cohort of 20 patients. The plan complexity was investigated for each plan using the complexity metrics of homogeneity index, conformity index, modulation complexity score, and the fraction of beams from a particular plan that intersect the chamber when performing the QA. Rotated QA gives more consistent results than the collapsed QA technique. The kfclin,frefQclin,Qfactor deviates less from 1 for rotated QA than for collapsed QA. If the homogeneity index is less than 0.05 then the kfclin,frefQclin,Q factor does not deviate from unity by more than 1%. A value this low for the homogeneity index can only be obtained

  12. Readiness assessment plan for the Radioactive Mixed Waste Land Disposal Facility (Trench 31)

    International Nuclear Information System (INIS)

    Irons, L.G.

    1994-01-01

    This document provides the Readiness Assessment Plan (RAP) for the Project W-025 (Radioactive Mixed Waste Land Disposal Facility) Readiness Assessment (RA). The RAP documents prerequisites to be met by the operating organization prior to the RA. The RAP is to be implemented by the RA Team identified in the RAP. The RA Team is to verify the facility's compliance with criteria identified in the RAP. The criteria are based upon the open-quotes Core Requirementsclose quotes listed in DOE Order 5480.31, open-quotes Startup and Restart of Nuclear Facilitiesclose quotes

  13. Quality assurance project plan for the UMTRA technical assistance contractor hydrochemistry facility. Final report

    International Nuclear Information System (INIS)

    1993-07-01

    The Uranium Mill Tailings Remedial Action (UMTRA) hydrochemistry facility is used to perform a limited but important set of services for the UMTRA Project. Routine services include support of field-based hydrological and geochemical operations and water sampling activities. Less commonly, the hydrology and geochemistry staff undertake special studies and site characterization studies at this facility. It is also used to train hydrologists, geochemists, and groundwater sampling crews. A review of this Quality Assurance Project Plan (QAPP) shall be accomplished once each calendar year. This review will be targeted to be accomplished not sooner than 6 months and not later than 18 months after the last review

  14. Unsaturated zone investigation at the radioactive waste storage facility site

    Energy Technology Data Exchange (ETDEWEB)

    Skuratovic, Zana; Mazeika, Jonas; Petrosius, Rimantas; Jakimaviciute-Maseliene, Vaidote [Nature Research Centre, Akademijos St. 2, LT-08412, Vilnius (Lithuania); Klizas, Petras; Mokrik, Robert [Vilnius University, M.K. Ciurlionio St. 21/27, LT-03101 Vilnius (Lithuania)

    2014-07-01

    Unsaturated zone is an important part of water circulation cycle and an integral part of many hydrological and hydrogeological factors and processes. The soils of unsaturated zone are regarded as the first natural barrier to a large extent able to limit the spread of contaminants. Nuclear waste disposal site (Maisiagala radioactive waste storage facility site) was analysed in terms of the moisture movement through the unsaturated zone. Extensive data sets of the hydraulic properties, water content and isotope composition have been collected and summarized. The main experimental and observational tasks included the collection of soil samples; determination of the physical properties and the hydraulic conductivity values of soil samples, moisture extraction from the soil sample for isotopic studies; observation of the groundwater dynamics at the Maisiagala piezometer; groundwater sampling for isotopic analysis ({sup 3}H, {sup 18}O/{sup 16}O, {sup 2}H/{sup 1}H ); and monthly precipitation isotopic analysis. Distribution features of globally widespread radionuclide tritium ({sup 3}H) and the water molecule tracer isotopes in precipitation, unsaturated zone soil moisture profiles and groundwater were determined. It was used the well-known unsaturated flow and transport model of HYDRUS-1D (Simunek et al., 2008). In this study, van Genuchten equations for the retention and conductivity estimations have been used. The retention characteristics and van Genuchten model parameters were estimated internally by HYDRUS based on the empirical equations involved in the program. Basic inputs of the tritium transport simulation are the tritium input function and meteorological variables (precipitation and potential evapotranspiration). In order to validate the representativeness of the hydraulic parameters, the model has been used to estimate the tritium distribution in the unsaturated zone, which properly represents the dynamics of the unsaturated zone. The uniformity of the daily

  15. Status and Plans for a Superconducting RF Accelerator Test Facility at Fermilab

    International Nuclear Information System (INIS)

    Andrews, R.; Baffes, C.M.; Carlson, K.; Chase, B.; Church, M.D.; Harms, E.R.; Klebaner, A.L.; Leibfritz, J.R.; Martinez, A.; Nagaitsev, S.; Nobrega, L.E.

    2012-01-01

    The Advanced Superconducting Test Accelerator (ASTA) is being constructed at Fermilab. The existing New Muon Lab (NML) building is being converted for this facility. The accelerator will consist of an electron gun, injector, beam acceleration section consisting of 3 TTF-type or ILC-type cryomodules, multiple downstream beam lines for testing diagnostics and conducting various beam tests, and a high power beam dump. When completed, it is envisioned that this facility will initially be capable of generating a 750 MeV electron beam with ILC beam intensity. An expansion of this facility was recently completed that will provide the capability to upgrade the accelerator to a total beam energy of 1.5 GeV. Two new buildings were also constructed adjacent to the ASTA facility to house a new cryogenic plant and multiple superconducting RF (SRF) cryomodule test stands. In addition to testing accelerator components, this facility will be used to test RF power systems, instrumentation, and control systems for future SRF accelerators such as the ILC and Project-X. This paper describes the current status and overall plans for this facility.

  16. Production planning and control for semiconductor wafer fabrication facilities modeling, analysis, and systems

    CERN Document Server

    Mönch, Lars; Mason, Scott J

    2012-01-01

    Over the last fifty-plus years, the increased complexity and speed of integrated circuits have radically changed our world. Today, semiconductor manufacturing is perhaps the most important segment of the global manufacturing sector. As the semiconductor industry has become more competitive, improving planning and control has become a key factor for business success. This book is devoted to production planning and control problems in semiconductor wafer fabrication facilities. It is the first book that takes a comprehensive look at the role of modeling, analysis, and related information systems

  17. Mixed waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

    International Nuclear Information System (INIS)

    1995-01-01

    The purpose of this plan is to describe the organization and methodology for the certification of mixed waste handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. Mixed waste is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington

  18. An alternative format for Category I fuel cycle facility physical protection plans

    International Nuclear Information System (INIS)

    Dwyer, P.A.

    1992-06-01

    This document provides an alternative format for physical protection plans designed to meet the requirements of Title 10 of the Code of Federal Regulations, Sections 73.20, 73.45, and 73.46. These requirements apply to licensees who operate Category I fuel cycle facilities. Such licensees are authorized to use or possess a formula quantity of strategic special nuclear material. The format described is an alternative to that found under Regulatory Guide 5.52, Rev. 2 ''Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power Plants).''

  19. Investigation of analytical and experimental behavior of nuclear facility ventilation systems

    International Nuclear Information System (INIS)

    Smith, P.R.; Ricketts, C.I.; Andrae, R.W.; Bolstad, J.W.; Horak, H.L.; Martin, R.A.; Tang, P.K.; Gregory, W.S.

    1979-01-01

    The behavior of nuclear facility ventilation systems subjected to both natural and man-caused accidents is being investigated. The purpose of the paper is to present a program overview and highlight recent results of the investigations. The program includes both analytical and experimental investigations. Computer codes for predicting accident-induced gas dynamics and test facilities to obtain supportive experimental data to define structural integrity and confinement effectiveness of ventilation system components are described. A unique test facility and recently obtained structural limits for high efficiency particulate air filters are reported

  20. The Benefits of Incorporating Shipping Containers into the Climate Change Adaption Plans at NASA Wallops Flight Facility

    Science.gov (United States)

    Hamilton, Carl Kenneth Gonzaga

    2017-01-01

    The National Aeronautics and Space Administration has several centers and facilities located near the coast that are undoubtedly susceptible to climate change. One of those facilities is Wallops Flight Facility on the Eastern Shore of Virginia which is separated into three areas: Main Base, Mainland, and the Island. Wallops Island has numerous buildings and assets that are vulnerable to flood inundation, intense storms, and storm surge. The shoreline of Wallops Island is prone to beach erosion and is slated for another beach replenishment project in 2019. In addition, current climate projections for NASAs centers and facilities, conducted by the Climate Adaptation Science Investigators, warn of inevitable increases in annual temperature, precipitation, sea level rise, and extreme events such as heat waves. The aforementioned vulnerabilities Wallops Island faces in addition to the projections of future climate change reveal an urgency for NASA to adjust how new buildings at its centers and facilities near the coast are built to adapt to the inevitable effects of climate change. Although the agency has made strides to mitigate the effects of climate change by incorporating L.E.E.D. into new buildings that produce less greenhouse gas, the strides for the agency to institute clear climate adaptation policies for the buildings at its centers and facilities near the coast seem to lag behind. As NASA continues to formulate formidable climate change adaptation plans for its centers and facilities, an architectural trend that should be examined for its potential to replace several old buildings at Wallops Island is shipping containers buildings. Shipping containers or Intermodal Steel Building Units offer an array of benefits such as strength, durability, versatility, modular, and since they can be upcycled, they are also eco-friendly. Some disadvantages of shipping containers are they contain harmful chemicals, insulation must be added, fossil fuels must be used to

  1. Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

  2. Implementation plan for the Defense Nuclear Facilities Safety Board Recommendation 90-7

    International Nuclear Information System (INIS)

    Borsheim, G.L.; Cash, R.J.; Dukelow, G.T.

    1992-12-01

    This document revises the original plan submitted in March 1991 for implementing the recommendations made by the Defense Nuclear Facilities Safety Board in their Recommendation 90-7 to the US Department of Energy. Recommendation 90-7 addresses safety issues of concern for 24 single-shell, high-level radioactive waste tanks containing ferrocyanide compounds at the Hanford Site. The waste in these tanks is a potential safety concern because, under certain conditions involving elevated temperatures and low concentrations of nonparticipating diluents, ferrocyanide compounds in the presence of oxidizing materials can undergo a runaway (propagating) chemical reaction. This document describes those activities underway by the Hanford Site contractor responsible for waste tank safety that address each of the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7. This document also identifies the progress made on these activities since the beginning of the ferrocyanide safety program in September 1990. Revised schedules for planned activities are also included

  3. Managing commercial low-level radioactive waste beyond 1992: Transportation planning for a LLW disposal facility

    International Nuclear Information System (INIS)

    Quinn, G.J.

    1992-01-01

    This technical bulletin presents information on the many activities and issues related to transportation of low-level radioactive waste (LLW) to allow interested States to investigate further those subjects for which proactive preparation will facilitate the development and operation of a LLW disposal facility. The activities related to transportation for a LLW disposal facility are discussed under the following headings: safety; legislation, regulations, and implementation guidance; operations-related transport (LLW and non-LLW traffic); construction traffic; economics; and public involvement

  4. State Environmental Policy Act (SEPA) environmental checklist forms for 304 Concretion Facility Closure Plan

    International Nuclear Information System (INIS)

    1993-11-01

    The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 304 Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 304 Facility, the history of materials and waste managed, and the procedures that will be followed to close the 304 Facility. The 304 Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5

  5. State Environmental Policy Act (SEPA) environmental checklist forms for 304 Concretion Facility Closure Plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 304 Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 304 Facility, the history of materials and waste managed, and the procedures that will be followed to close the 304 Facility. The 304 Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

  6. Emergency planning and response: An independent safety assessment of Department of Energy nuclear reactor facilities

    International Nuclear Information System (INIS)

    Knuth, D.; Boyd, R.

    1981-02-01

    The Department of Energy (DOE) has formed a Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee to assess the implications of the recommendations contained in the President's Commission Report on the Three Mile Island (TMI) Accident (the Kemeny Commission report) that are applicable to DOE's nuclear reactor operations. Thirteen DOE nuclear reactors have been reviewed. The assessments of the 13 facilities are based on information provided by the individual operator organizations and/or cognizant DOE Field Offices. Additional clarifying information was supplied in some, but not all, instances. This report indicates how these 13 reactor facilities measure up in light of the Kemeny and other TMI-related studies and recommendations, particularly those that have resulted in upgraded Nuclear Regulatory Commission (NRC) requirements in the area of emergency planning and response

  7. Operations and Maintenance Concept Plan for the Immobilized High Level Waste (IHLW) Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    JANIN, L.F.

    2000-08-30

    This O&M Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design.

  8. Operations and Maintenance Concept Plan for the Immobilized High-Level Waste (IHLW) Interim Storage Facility

    International Nuclear Information System (INIS)

    JANIN, L.F.

    2000-01-01

    This OandM Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design

  9. Waste receiving and processing facility module 1 data management system software project management plan

    International Nuclear Information System (INIS)

    Clark, R.E.

    1994-01-01

    This document provides the software development plan for the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store, and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal

  10. National Ignition Facility quality assurance plan for laser materials and optical technology

    International Nuclear Information System (INIS)

    Wolfe, C.R.

    1996-05-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This subtier Quality Assurance Plan (QAP) applies to activities of the Laser Materials ampersand Optical Technology (LM ampersand OT) organization and its subcontractors. It responds to the NIF Quality Assurance Program Plan (QAPP, L-15958-2, NIF-95-499) and Department of Energy (DOE) Order 5700.6C. This Plan is organized according to 10 Quality Assurance (QA) criteria and subelements of a management system as outlined in the NIF QAPP. This Plan describes how those QA requirements are met. This Plan is authorized by the Associate Project Leader for the LM ampersand OT organization, who has assigned responsibility to the Optics QA engineer to maintain this plan, with the assistance of the NIF QA organization. This Plan governs quality-affecting activities associated with: design; procurement; fabrication; testing and acceptance; handling and storage; and installation of NIF Project optical components into mounts and subassemblies

  11. Surfaced-based investigations plan, Volume 4: Yucca Mountain Project

    International Nuclear Information System (INIS)

    1988-12-01

    This document represents a detailed summary of design plans for surface-based investigations to be conducted for site characterization of the Yucca Mountain site. These plans are current as of December 1988. The description of surface-based site characterization activities contained in this document is intended to give all interested parties an understanding of the current plans for site characterization of Yucca Mountain. The maps presented in Volume 4 are products of the Geographic Information System (GIS) being used by the Yucca Mountain Project. The ARC/INFO GIS software, developed by Environmental Systems Research Institute, was used to digitize and process these SBIP maps. The maps were prepared using existing US Geological Survey (USGS) maps as a planimetric base. Roads and other surface features were interpreted from a variety of sources and entered into the GIS. Sources include the USGS maps, 1976 USGS orthophotoquads and aerial photography, 1986 and 1987 aerial photography, surveyed coordinates of field sites, and a combination of various maps, figures, descriptions and approximate coordinates of proposed locations for future activities

  12. Resource Conservation and Recovery Act industrial site environmental restoration site characterization plan. Area 6 Decontamination Pond Facility. Revision 1

    International Nuclear Information System (INIS)

    1996-08-01

    This plan presents the strategy for the characterization of the Area 6 Decontamination Pond Facility at the Nevada Test Site which will be conducted for the US Department of Energy, Nevada Operations Office, Environmental Restoration Division. The objectives of the planned activities are to: obtain sufficient, sample analytical data from which further assessment, remediation, and/or closure strategies may be developed for the site; obtain sufficient, sample analytical data for management of investigation-derived waste. The scope of the characterization may include surface radiation survey(s), surface soil sampling, subsurface soil boring (i.e., drilling), and sampling of soil in and around the pond; in situ sampling of the soil within subsurface soil borings; and sample analysis for both site characterization and waste management purposes

  13. A spatial national health facility database for public health sector planning in Kenya in 2008

    Directory of Open Access Journals (Sweden)

    Gething Peter W

    2009-03-01

    Full Text Available Abstract Background Efforts to tackle the enormous burden of ill-health in low-income countries are hampered by weak health information infrastructures that do not support appropriate planning and resource allocation. For health information systems to function well, a reliable inventory of health service providers is critical. The spatial referencing of service providers to allow their representation in a geographic information system is vital if the full planning potential of such data is to be realized. Methods A disparate series of contemporary lists of health service providers were used to update a public health facility database of Kenya last compiled in 2003. These new lists were derived primarily through the national distribution of antimalarial and antiretroviral commodities since 2006. A combination of methods, including global positioning systems, was used to map service providers. These spatially-referenced data were combined with high-resolution population maps to analyze disparity in geographic access to public health care. Findings The updated 2008 database contained 5,334 public health facilities (67% ministry of health; 28% mission and nongovernmental organizations; 2% local authorities; and 3% employers and other ministries. This represented an overall increase of 1,862 facilities compared to 2003. Most of the additional facilities belonged to the ministry of health (79% and the majority were dispensaries (91%. 93% of the health facilities were spatially referenced, 38% using global positioning systems compared to 21% in 2003. 89% of the population was within 5 km Euclidean distance to a public health facility in 2008 compared to 71% in 2003. Over 80% of the population outside 5 km of public health service providers was in the sparsely settled pastoralist areas of the country. Conclusion We have shown that, with concerted effort, a relatively complete inventory of mapped health services is possible with enormous potential for

  14. A spatial national health facility database for public health sector planning in Kenya in 2008.

    Science.gov (United States)

    Noor, Abdisalan M; Alegana, Victor A; Gething, Peter W; Snow, Robert W

    2009-03-06

    Efforts to tackle the enormous burden of ill-health in low-income countries are hampered by weak health information infrastructures that do not support appropriate planning and resource allocation. For health information systems to function well, a reliable inventory of health service providers is critical. The spatial referencing of service providers to allow their representation in a geographic information system is vital if the full planning potential of such data is to be realized. A disparate series of contemporary lists of health service providers were used to update a public health facility database of Kenya last compiled in 2003. These new lists were derived primarily through the national distribution of antimalarial and antiretroviral commodities since 2006. A combination of methods, including global positioning systems, was used to map service providers. These spatially-referenced data were combined with high-resolution population maps to analyze disparity in geographic access to public health care. The updated 2008 database contained 5,334 public health facilities (67% ministry of health; 28% mission and nongovernmental organizations; 2% local authorities; and 3% employers and other ministries). This represented an overall increase of 1,862 facilities compared to 2003. Most of the additional facilities belonged to the ministry of health (79%) and the majority were dispensaries (91%). 93% of the health facilities were spatially referenced, 38% using global positioning systems compared to 21% in 2003. 89% of the population was within 5 km Euclidean distance to a public health facility in 2008 compared to 71% in 2003. Over 80% of the population outside 5 km of public health service providers was in the sparsely settled pastoralist areas of the country. We have shown that, with concerted effort, a relatively complete inventory of mapped health services is possible with enormous potential for improving planning. Expansion in public health care in Kenya has

  15. Analysis Methods for Extracting Knowledge from Large-Scale WiFi Monitoring to Inform Building Facility Planning

    DEFF Research Database (Denmark)

    Ruiz-Ruiz, Antonio; Blunck, Henrik; Prentow, Thor Siiger

    2014-01-01

    realistic data to inform facility planning. In this paper, we propose analysis methods to extract knowledge from large sets of network collected WiFi traces to better inform facility management and planning in large building complexes. The analysis methods, which build on a rich set of temporal and spatial......The optimization of logistics in large building com- plexes with many resources, such as hospitals, require realistic facility management and planning. Current planning practices rely foremost on manual observations or coarse unverified as- sumptions and therefore do not properly scale or provide....... Spatio-temporal visualization tools built on top of these methods enable planners to inspect and explore extracted information to inform facility-planning activities. To evaluate the methods, we present results for a large hospital complex covering more than 10 hectares. The evaluation is based on Wi...

  16. Readiness plan, Hanford 300 Area Treated Effluent Disposal Facility: Revision 1

    International Nuclear Information System (INIS)

    Storm, S.J.

    1994-01-01

    The 300 Area Treated Effluent Disposal Facility (TEDF) is designed for the collection, treatment, and eventual disposal of liquid waste from the 300 Area Process Sewer (PS) system. The PS currently discharges water to the 300 Area Process Trenches. Facilities supported total 54 buildings, including site laboratories, inactive buildings, and support facilities. Effluent discharges to the process sewer from within these facilities include heating, ventilation, and air conditioning systems, heat exchangers, floor drains, sinks, and process equipment. The wastewaters go through treatment processes that include iron coprecipitation, ion exchange and ultraviolet oxidation. The iron coprecipitation process is designed to remove general heavy metals. A series of gravity filters then complete the clarification process by removing suspended solids. Following the iron coprecipitation process is the ion exchange process, where a specific resin is utilized for the removal of mercury. The final main unit operation is the ultraviolet destruction process, which uses high power ultraviolet light and hydrogen peroxide to destroy organic molecules. The objective of this readiness plan is to provide the method by which line management will prepare for a Readiness Assessment (RA) of the TEDF. The self-assessment and RA will assess safety, health, environmental compliance and management readiness of the TEDF. This assessment will provide assurances to both WHC and DOE that the facility is ready to start-up and begin operation

  17. The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)

    International Nuclear Information System (INIS)

    1994-12-01

    The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration

  18. Corrective action investigation plan: Cactus Spring Waste Trenches. Revision 2

    International Nuclear Information System (INIS)

    1997-02-01

    This Correction Action Investigation Plan (CAIP) contains environmental sample collection objectives and logic for the CAU No. 426, which includes the Cactus Spring Waste Trenches, CAS No. RG-08-001-RG-CS. The Cactus Spring Waste Trenches are located at the Tonopah Test Range (TTR) which is part of the Nellis Air Force Range, approximately 255 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada, by air. The purpose of this investigation is to generate sufficient data to establish the types of waste buried in the trenches, identify the presence and nature of contamination, determine the vertical extent of contaminant migration below the Cactus Spring Waste Trenches, and determine the appropriate course of action for the site. The potential courses of action for the site are clean closure, closure in place (with or without remediation), or no further action

  19. Participative Facility Planning for Obstetrical and Neonatal Care Processes: Beginning of Life Process

    Directory of Open Access Journals (Sweden)

    Jori Reijula

    2016-01-01

    Full Text Available Introduction. Old hospitals may promote inefficient patient care processes and safety. A new, functionally planned hospital presents a chance to create an environment that supports streamlined, patient-centered healthcare processes and adapts to users’ needs. This study depicts the phases of a facility planning project for pregnant women and newborn care processes (beginning of life process at Turku University Hospital. Materials and Methods. Project design reports and meeting documents were utilized to assess the beginning of life process as well as the work processes of the Women’s and Children’s Hospital. Results. The main elements of the facility design (FD project included rigorous preparation for the FD phase, functional planning throughout the FD process, and setting key values: (1 family-centered care, (2 Lean thinking and Lean tools as the framework for the FD process, (3 safety, and (4 cooperation. Conclusions. A well-prepared FD project with sufficient insight into functional planning, Lean thinking, and user-centricity seemed to facilitate the actual FD process. Although challenges occurred, the key values were not forgone and were successfully incorporated into the new hospital building.

  20. Radiological, technical and financial planning for decommissioning of small nuclear facilities in Sweden - 16177

    International Nuclear Information System (INIS)

    Lindskog, Staffan; Sjoeblom, Rolf

    2009-01-01

    On November 1 2008, a new ordinance came into force in Sweden. It extends the implementation of nuclear liability to all nuclear facilities and companies, regardless of size. The Government has authorized the Swedish Radiation Safety Authority (SSM) to issue further regulation as warranted and appropriate, and commissioned the same Authority to oversee the implementation. Consequently, SSM is presently conducting research in order to establish a basis for the implementation of the ordinance to smaller facilities and enterprises. The goal is to enable finance to be assured in an efficient manner so that any burden on the companies is as small as possible. Thus, 'functional requirements' are identified, and used as a basis for various investigations. The aspects include technical and cost calculation prerequisites, as well as various domains of law: the environmental code, radiation and nuclear safety, financial reporting, and criminal law. It is found that the basis for the differentiation among the facility operators and owners should be the cost and the associated uncertainty. Thus, a cost calculation will have to be carried out by all. It should be based on available standards and guidance documents. It is found that this is a requirement that already exists elsewhere in the legislation, and thus no additional burden is imposed on the companies. It is found that segregated funds is the preferred option for long-term liabilities. Securities are suitable for short-term liabilities provided that the economy of the company in question is sound. Securities might also be used for long-term liabilities to cover uncertainty. It is proposed that a de minimis limit of at least kSEK 25 (about keuros 2,4 and k$ 3,4) is used. An important reason for this is that lower limits might be incompatible with the rules for financial reporting. It is also proposed that securities might be used also for long-term commitments if the total environmental liability does not exceed 1

  1. Software quality assurance plan for the National Ignition Facility integrated computer control system

    Energy Technology Data Exchange (ETDEWEB)

    Woodruff, J.

    1996-11-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This Software Quality Assurance Plan (SQAP) applies to the activities of the Integrated Computer Control System (ICCS) organization and its subcontractors. The Plan describes the activities implemented by the ICCS section to achieve quality in the NIF Project`s controls software and implements the NIF Quality Assurance Program Plan (QAPP, NIF-95-499, L-15958-2) and the Department of Energy`s (DOE`s) Order 5700.6C. This SQAP governs the quality affecting activities associated with developing and deploying all control system software during the life cycle of the NIF Project.

  2. First-dollar cost-sharing for skilled nursing facility care in medicare advantage plans.

    Science.gov (United States)

    Keohane, Laura M; Grebla, Regina C; Rahman, Momotazur; Mukamel, Dana B; Lee, Yoojin; Mor, Vincent; Trivedi, Amal

    2017-08-29

    The initial days of a Medicare-covered skilled nursing facility (SNF) stay may have no cost-sharing or daily copayments depending on beneficiaries' enrollment in traditional Medicare or Medicare Advantage. Some policymakers have advocated imposing first-dollar cost-sharing to reduce post-acute expenditures. We examined the relationship between first-dollar cost-sharing for a SNF stay and use of inpatient and SNF services. We identified seven Medicare Advantage plans that introduced daily SNF copayments of $25-$150 in 2009 or 2010. Copays began on the first day of a SNF admission. We matched these plans to seven matched control plans that did not introduce first-dollar cost-sharing. In a difference-in-differences analysis, we compared changes in SNF and inpatient utilization for the 172,958 members of intervention and control plans. In intervention plans the mean annual number of SNF days per 100 continuously enrolled inpatients decreased from 768.3 to 750.6 days when cost-sharing changes took effect. Control plans experienced a concurrent increase: 721.7 to 808.1 SNF days per 100 inpatients (adjusted difference-in-differences: -87.0 days [95% CI (-112.1,-61.9)]). In intervention plans, we observed no significant changes in the probability of any SNF service use or the number of inpatient days per hospitalized member relative to concurrent trends among control plans. Among several strategies Medicare Advantage plans can employ to moderate SNF use, first-dollar SNF cost-sharing may be one influential factor. Not applicable.

  3. Work plan for the High Ranking Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-03-01

    The High Ranking Facilities Deactivation Project (HRFDP), commissioned by the US Department of Energy Nuclear Materials and Facility Stabilization Program, is to place four primary high-risk surplus facilities with 28 associated ancillary facilities at Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition as rapidly and economically as possible. The facilities will be deactivated and left in a condition suitable for an extended period of minimized surveillance and maintenance (S and M) prior to decontaminating and decommissioning (D and D). These four facilities include two reactor facilities containing spent fuel. One of these reactor facilities also contains 55 tons of sodium with approximately 34 tons containing activated sodium-22, 2.5 tons of lithium hydride, approximately 100 tons of potentially contaminated lead, and several other hazardous materials as well as bulk quantities of contaminated scrap metals. The other two facilities to be transferred include a facility with a bank of hot cells containing high levels of transferable contamination and also a facility containing significant quantities of uranyl nitrate and quantities of transferable contamination. This work plan documents the objectives, technical requirements, and detailed work plans--including preliminary schedules, milestones, and conceptual FY 1996 cost estimates--for the Oak Ridge National Laboratory (ORNL). This plan has been developed by the Environmental Restoration (ER) Program of Lockheed Martin Energy Systems (Energy Systems) for the US Department of Energy (DOE) Oak Ridge Operations Office (ORO)

  4. Work plan for the High Ranking Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    The High Ranking Facilities Deactivation Project (HRFDP), commissioned by the US Department of Energy Nuclear Materials and Facility Stabilization Program, is to place four primary high-risk surplus facilities with 28 associated ancillary facilities at Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition as rapidly and economically as possible. The facilities will be deactivated and left in a condition suitable for an extended period of minimized surveillance and maintenance (S and M) prior to decontaminating and decommissioning (D and D). These four facilities include two reactor facilities containing spent fuel. One of these reactor facilities also contains 55 tons of sodium with approximately 34 tons containing activated sodium-22, 2.5 tons of lithium hydride, approximately 100 tons of potentially contaminated lead, and several other hazardous materials as well as bulk quantities of contaminated scrap metals. The other two facilities to be transferred include a facility with a bank of hot cells containing high levels of transferable contamination and also a facility containing significant quantities of uranyl nitrate and quantities of transferable contamination. This work plan documents the objectives, technical requirements, and detailed work plans--including preliminary schedules, milestones, and conceptual FY 1996 cost estimates--for the Oak Ridge National Laboratory (ORNL). This plan has been developed by the Environmental Restoration (ER) Program of Lockheed Martin Energy Systems (Energy Systems) for the US Department of Energy (DOE) Oak Ridge Operations Office (ORO).

  5. Capacity Planning for Batch and Perfusion Bioprocesses Across Multiple Biopharmaceutical Facilities

    Science.gov (United States)

    Siganporia, Cyrus C; Ghosh, Soumitra; Daszkowski, Thomas; Papageorgiou, Lazaros G; Farid, Suzanne S

    2014-01-01

    Production planning for biopharmaceutical portfolios becomes more complex when products switch between fed-batch and continuous perfusion culture processes. This article describes the development of a discrete-time mixed integer linear programming (MILP) model to optimize capacity plans for multiple biopharmaceutical products, with either batch or perfusion bioprocesses, across multiple facilities to meet quarterly demands. The model comprised specific features to account for products with fed-batch or perfusion culture processes such as sequence-dependent changeover times, continuous culture constraints, and decoupled upstream and downstream operations that permit independent scheduling of each. Strategic inventory levels were accounted for by applying cost penalties when they were not met. A rolling time horizon methodology was utilized in conjunction with the MILP model and was shown to obtain solutions with greater optimality in less computational time than the full-scale model. The model was applied to an industrial case study to illustrate how the framework aids decisions regarding outsourcing capacity to third party manufacturers or building new facilities. The impact of variations on key parameters such as demand or titres on the optimal production plans and costs was captured. The analysis identified the critical ratio of in-house to contract manufacturing organization (CMO) manufacturing costs that led the optimization results to favor building a future facility over using a CMO. The tool predicted that if titres were higher than expected then the optimal solution would allocate more production to in-house facilities, where manufacturing costs were lower. Utilization graphs indicated when capacity expansion should be considered. © 2013 The Authors Biotechnology Progress published by Wiley Periodicals, Inc. on behalf of American Institute of Chemical Engineers Biotechnol. Prog., 30:594–606, 2014 PMID:24376262

  6. Waste Management facilities cost information: System Cost Model Software Quality Assurance Plan. Revision 2

    International Nuclear Information System (INIS)

    Peterson, B.L.; Lundeen, A.S.

    1996-02-01

    In May of 1994, Lockheed Idaho Technologies Company (LITCO) in Idaho Falls, Idaho and subcontractors developed the System Cost Model (SCM) application. The SCM estimates life-cycle costs of the entire US Department of Energy (DOE) complex for designing; constructing; operating; and decommissioning treatment, storage, and disposal (TSD) facilities for mixed low-level, low-level, transuranic, and mixed transuranic waste. The SCM uses parametric cost functions to estimate life-cycle costs for various treatment, storage, and disposal modules which reflect planned and existing facilities at DOE installations. In addition, SCM can model new facilities based on capacity needs over the program life cycle. The SCM also provides transportation costs for truck and rail, which include transport of contact-handled, remote-handled, and alpha (transuranic) wastes. The user can provide input data (default data is included in the SCM) including the volume and nature of waste to be managed, the time period over which the waste is to be managed, and the configuration of the waste management complex (i.e., where each installation's generated waste will be treated, stored, and disposed). Then the SCM uses parametric cost equations to estimate the costs of pre-operations (designing), construction costs, operation management, and decommissioning these waste management facilities. For the product to be effective and useful the SCM users must have a high level of confidence in the data generated by the software model. The SCM Software Quality Assurance Plan is part of the overall SCM project management effort to ensure that the SCM is maintained as a quality product and can be relied on to produce viable planning data. This document defines tasks and deliverables to ensure continued product integrity, provide increased confidence in the accuracy of the data generated, and meet the LITCO's quality standards during the software maintenance phase. 8 refs., 1 tab

  7. Capacity planning for batch and perfusion bioprocesses across multiple biopharmaceutical facilities.

    Science.gov (United States)

    Siganporia, Cyrus C; Ghosh, Soumitra; Daszkowski, Thomas; Papageorgiou, Lazaros G; Farid, Suzanne S

    2014-01-01

    Production planning for biopharmaceutical portfolios becomes more complex when products switch between fed-batch and continuous perfusion culture processes. This article describes the development of a discrete-time mixed integer linear programming (MILP) model to optimize capacity plans for multiple biopharmaceutical products, with either batch or perfusion bioprocesses, across multiple facilities to meet quarterly demands. The model comprised specific features to account for products with fed-batch or perfusion culture processes such as sequence-dependent changeover times, continuous culture constraints, and decoupled upstream and downstream operations that permit independent scheduling of each. Strategic inventory levels were accounted for by applying cost penalties when they were not met. A rolling time horizon methodology was utilized in conjunction with the MILP model and was shown to obtain solutions with greater optimality in less computational time than the full-scale model. The model was applied to an industrial case study to illustrate how the framework aids decisions regarding outsourcing capacity to third party manufacturers or building new facilities. The impact of variations on key parameters such as demand or titres on the optimal production plans and costs was captured. The analysis identified the critical ratio of in-house to contract manufacturing organization (CMO) manufacturing costs that led the optimization results to favor building a future facility over using a CMO. The tool predicted that if titres were higher than expected then the optimal solution would allocate more production to in-house facilities, where manufacturing costs were lower. Utilization graphs indicated when capacity expansion should be considered. © 2014 The Authors Biotechnology Progress published by Wiley Periodicals, Inc. on behalf of American Institute of Chemical Engineers.

  8. Marine Planning for Potential Wave Energy Facility Placement Amongst a Crowded Sea of Existing Resource Uses

    Science.gov (United States)

    Feist, B. E.; Fuller, E.; Plummer, M. L.

    2016-12-01

    Conversion to renewable energy sources is a logical response to increasing pressure to reduce greenhouse gas emissions. Ocean wave energy is the least developed renewable energy source, despite having the highest energy per unit area. While many hurdles remain in developing wave energy, assessing potential conflicts and evaluating tradeoffs with existing uses is essential. Marine planning encompasses a broad array of activities that take place in and affect large marine ecosystems, making it an ideal tool for evaluating wave energy resource use conflicts. In this study, we focus on the potential conflicts between wave energy conversion (WEC) facilities and existing marine uses in the context of marine planning, within the California Current Large Marine Ecosystem. First, we evaluated wave energy facility development using the Wave Energy Model (WEM) of the Integrated Valuation of Ecosystem Services and Trade-offs (InVEST) toolkit. Second, we ran spatial analyses on model output to identify conflicts with existing marine uses including AIS based vessel traffic, VMS and observer based measures of commercial fishing effort, and marine conservation areas. We found that regions with the highest wave energy potential were distant from major cities and that infrastructure limitations (cable landing sites) restrict integration with existing power grids. We identified multiple spatial conflicts with existing marine uses; especially shipping vessels and various commercial fishing fleets, and overlap with marine conservation areas varied by conservation designation. While wave energy generation facilities may be economically viable in the California Current, this viability must be considered within the context of the costs associated with conflicts that arise with existing marine uses. Our analyses can be used to better inform placement of WEC devices (as well as other types of renewable energy facilities) in the context of marine planning by accounting for economic tradeoffs

  9. Waste Management facilities cost information: System Cost Model Software Quality Assurance Plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, B.L.; Lundeen, A.S.

    1996-02-01

    In May of 1994, Lockheed Idaho Technologies Company (LITCO) in Idaho Falls, Idaho and subcontractors developed the System Cost Model (SCM) application. The SCM estimates life-cycle costs of the entire US Department of Energy (DOE) complex for designing; constructing; operating; and decommissioning treatment, storage, and disposal (TSD) facilities for mixed low-level, low-level, transuranic, and mixed transuranic waste. The SCM uses parametric cost functions to estimate life-cycle costs for various treatment, storage, and disposal modules which reflect planned and existing facilities at DOE installations. In addition, SCM can model new facilities based on capacity needs over the program life cycle. The SCM also provides transportation costs for truck and rail, which include transport of contact-handled, remote-handled, and alpha (transuranic) wastes. The user can provide input data (default data is included in the SCM) including the volume and nature of waste to be managed, the time period over which the waste is to be managed, and the configuration of the waste management complex (i.e., where each installation`s generated waste will be treated, stored, and disposed). Then the SCM uses parametric cost equations to estimate the costs of pre-operations (designing), construction costs, operation management, and decommissioning these waste management facilities. For the product to be effective and useful the SCM users must have a high level of confidence in the data generated by the software model. The SCM Software Quality Assurance Plan is part of the overall SCM project management effort to ensure that the SCM is maintained as a quality product and can be relied on to produce viable planning data. This document defines tasks and deliverables to ensure continued product integrity, provide increased confidence in the accuracy of the data generated, and meet the LITCO`s quality standards during the software maintenance phase. 8 refs., 1 tab.

  10. Guidance for the design and management of a maintenance plan to assure safety and improve the predictability of a DOE nuclear irradiation facility. Final report

    International Nuclear Information System (INIS)

    Booth, R.S.; Kryter, R.C.; Shepard, R.L.; Smith, O.L.; Upadhyaya, B.R.; Rowan, W.J.

    1994-10-01

    A program is recommended for planning the maintenance of DOE nuclear facilities that will help safety and enhance availability throughout a facility's life cycle. While investigating the requirements for maintenance activities, a major difference was identified between the strategy suitable for a conventional power reactor and one for a research reactor facility: the latter should provide a high degree of predicted availability (referred to hereafter as ''predictability'') to its users, whereas the former should maximize total energy production. These differing operating goals necessitate different maintenance strategies. A strategy for scheduling research reactor facility operation and shutdown for maintenance must balance safety, reliability,and predicted availability. The approach developed here is based on three major elements: (1) a probabilistic risk analysis of the balance between assured reliability and predictability (presented in Appendix C), (2) an assessment of the safety and operational impact of maintenance activities applied to various components of the facility, and (3) a data base of historical and operational information on the performance and requirements for maintenance of various components. These factors are integrated into a set of guidelines for designing a new highly maintainable facility, for preparing flexible schedules for improved maintenance of existing facilities, and for anticipating the maintenance required to extend the life of an aging facility. Although tailored to research reactor facilities, the methodology has broader applicability and may therefore be used to improved the maintenance of power reactors, particularly in anticipation of peak load demands

  11. Effects of Caps on Cost Sharing for Skilled Nursing Facility Services in Medicare Advantage Plans.

    Science.gov (United States)

    Keohane, Laura M; Rahman, Momotazur; Thomas, Kali S; Trivedi, Amal N

    2018-03-12

    To evaluate a federal regulation effective in 2011 that limited how much that Medicare Advantage (MA) plans could charge for the first 20 days of care in a skilled nursing facility (SNF). Difference-in-differences retrospective analysis comparing SNF utilization trends from 2008-2012. Select MA plans. Members of 27 plans with mandatory cost sharing reductions (n=132,000) and members of 21 plans without such reductions (n=138,846). Mean monthly number of SNF admissions and days per 1,000 members; annual proportion of MA enrollees exiting the plan. In plans with mandated cost sharing reductions, cost sharing for the first 20 days of SNF care decreased from an average of $2,039 in 2010 to $992 in 2011. In adjusted analyses, plans with mandated cost-sharing reductions averaged 158.1 SNF days (95% confidence interval (CI)=153.2-163.1 days) per 1,000 members per month before the cost sharing cap. This measure increased by 14.3 days (95% CI=3.8-24.8 days, p=0.009) in the 2 years after cap implementation. However, increases in SNF utilization did not significantly differ between plans with and without mandated cost-sharing reductions (adjusted between-group difference: 7.1 days per 1,000 members, 95% CI=-6.5-20.8, p=.30). Disenrollment patterns did not change after the cap took effect. When a federal regulation designed to protect MA members from high out-of-pocket costs for postacute care took effect, the use of SNF services did not change. © 2018, Copyright the Authors Journal compilation © 2018, The American Geriatrics Society.

  12. Test plan: Gas-threshold-pressure testing of the Salado Formation in the WIPP underground facility

    International Nuclear Information System (INIS)

    Saulnier, G.J. Jr.

    1992-03-01

    Performance assessment for the disposal of radioactive waste from the United States defense program in the WIPP underground facility must assess the role of post-closure was generation by waste degradation and the subsequent pressurization of the facility. be assimilated by the host formation will Whether or not the generated gas can be assimilated by the host formation will determine the ability of the gas to reach or exceed lithostatic pressure within the repository. The purpose of this test plan is (1) to present a test design to obtain realistic estimates of gas-threshold pressure for the Salado Formation WIPP underground facility including parts of the formation disturbed by the underground of the Salado, and (2) to provide a excavations and in the far-field or undisturbed part framework for changes and amendments to test objectives, practices, and procedures. Because in situ determinations of gas-threshold pressure in low-permeability media are not standard practice, the methods recommended in this testplan are adapted from permeability-testing and hydrofracture procedures. Therefore, as the gas-threshold-pressure testing program progresses, personnel assigned to the program and outside observers and reviewers will be asked for comments regarding the testing procedures. New and/or improved test procedures will be documented as amendments to this test plan, and subject to similar review procedures

  13. Planning and management for the decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    Many research reactors and other small nuclear facilities throughout the world date from the original nuclear research programmes in the Member States. Consequently, a large number of these plants have either been retired from service or will soon reach the end of their useful lives and are likely to become significant decommissioning tasks for those Members States. In recognition of this situation and in response to considerable interest shown by Member States, the IAEA has produced this document on planning and management for the decommissioning of research reactors and other small nuclear facilities. While not directed specifically at large nuclear installations, it is likely that much of the information presented will also be of interest to those involved in the decommissioning of such facilities. Current views, information and experience on the planning and management of decommissioning projects in Member States were collected and assessed during a Technical Committee Meeting held by the IAEA in Vienna from 29 July to 2 August 1991. It was attended by 22 participants from 14 Member States and one international organization. 28 refs, 2 figs, 3 tabs

  14. Nevada Nuclear Waste Storage Investigations: Quality Assurance Plan

    International Nuclear Information System (INIS)

    1980-08-01

    The Nevada Nuclear Waste Storage Investigations (NNWSI) were established by DOE/NV to evaluate the geohydrologic setting and underground rock masses of the Nevada Test Site (NTS) and contiguous areas to determine whether a suitable site exists for constructing a repository for isolating highly radioactive solid wastes. Since the results of these evaluations will impact possible risks to public health and safety, a quality assurance program which conforms to the criteria given in the Code of Federal Regulations is needed to control the quality aspects of the work. This Quality Assurance Plan (QAP) describes the general quality assurance program for the overall NNWSI project under which the quality assurance programs of the individual participating organizations and support contractors are to operate. The details of how each of these groups will meet the criteria will differ among participating organizations and support contractors, and those details are given in the QAPP's listed in Appendix A. It is the purpose of this plan to show the commonality of quality assurance programs in effect within the project and to define how each element fits into the entire picture to give total quality assurance coverage for the NNWSI Project

  15. Quadrant I RCRA Facility investigation work plan: Health and safety plan

    International Nuclear Information System (INIS)

    1990-01-01

    This report describes occupational health and safety issues at the Portsmouth Gaseous Diffusion Plant. Health effects from exposure to chemicals, vapors, drilling and sampling activities, as well as from ionizing radiations and protective measures are discussed

  16. Nevada Nuclear Waste Storage Investigations. FY 1979 project plan

    International Nuclear Information System (INIS)

    1979-03-01

    This document presents the management and cost for the Nevada Nuclear Waste Storage Investigations (disposal of high-level wastes at Nevada Test Site) and provides a complete description of the overall project, management structure, technical approach, and work breakdown structure. The document is organized into five major sections. Section I summarizes the history of the project and indicates a potential future course of action. FY 1979 project work is briefly described in Section II. Section III outlines the delegated responsibilities of all project management functions. A list of critical questions that guide the technical approach of the project are presented in Section IV. Section V contains subtask work plans which outline the work in detail for this fiscal year

  17. 200 Area effluent treatment facility process control plan 98-02

    International Nuclear Information System (INIS)

    Le, E.Q.

    1998-01-01

    This Process Control Plan (PCP) provides a description of the background information, key objectives, and operating criteria defining Effluent Treatment Facility (ETF) Campaign 98-02 as required per HNF-IP-0931 Section 37, Process Control Plans. Campaign 98-62 is expected to process approximately 18 millions gallons of groundwater with an assumption that the UP-1 groundwater pump will be shut down on June 30, 1998. This campaign will resume the UP-1 groundwater treatment operation from Campaign 97-01. The Campaign 97-01 was suspended in November 1997 to allow RCRA waste in LERF Basin 42 to be treated to meet the Land Disposal Restriction Clean Out requirements. The decision to utilize ETF as part of the selected interim remedial action of the 200-UP-1 Operable Unit is documented by the Declaration of the Record of Decision, (Ecology, EPA and DOE 1997). The treatment method was chosen in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), the Hanford Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement or TPA), and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP)

  18. Planning, managing and organizing the decommissioning of nuclear facilities: Lessons learned

    International Nuclear Information System (INIS)

    2004-05-01

    This publication is intended to encourage the development and improvement of decommissioning planning and management techniques, with the focus on organizational aspects, reduce the duplication of efforts by different parties by transfer of experience and know-how, and provide useful results for those Member States planning or implementing decommissioning projects. In general it can be stated that any decommissioning project can be completed without any deleterious effects on the safety of the workforce and the public or any identifiable impact on the environment. However, timeliness and cost-effectiveness are not always optimal. It has been noted on several occasions that the major weakness in decommissioning projects (as well as in other industrial projects) is often not the lack of technologies, but rather poor planning and management. This publication intends to stimulate awareness of the need for early and efficient planning and to foster developments in management and organization in association with planned or ongoing decommissioning projects. A companion report on Organization and Management for Decommissioning of Large Nuclear Facilities was published by the IAEA in 2000 (Technical Report Series (TRS) No. 399). That TRS provides generic guidance on organizational and management aspects. This TECDOC is complementary to the existing report in that it highlights practical experience - in particular, typical issues, evidence of poor management, undue delays, and lack of timely funding - and distils lessons learned from this experience

  19. Transcript of the workshop to discuss plans for a National High Intensity Radioactive Nuclear Beam Facility

    International Nuclear Information System (INIS)

    Nitschke, J.M.

    1989-01-01

    Following the ''First International Conference on Radioactive Nuclear Beams'' in Berkeley, a workshop was held on October 19, 1989 at the Lawrence Berkeley Laboratory to discuss plans for a National High Intensity Radioactive Nuclear Beam (RNB) Facility. The purpose of the workshop was -- after having discussed during the conference the physics question that can be addressed with RNBs -- to evaluate more concretely the possibilities for actually constructing such a facility in this country. It is becoming increasingly apparent that facility producing beams of radioactive nuclei with extreme neutron-to-proton ratios is of high scientific interest and technically feasible. It would allow the study of nuclear structure and astrophysical reactions very far from the line of stable nuclei, and could provide new possibilities of reaching the long-sought island of stability of superheavy nuclei. Such facilities are under advanced consideration in Japan and at CERN in Europe. This paper contains a slightly edited transcript of the tape recording that was made of the workshop

  20. Strategy and plan for siting and licensing a Rocky Mountain low-level radioactive waste facility

    International Nuclear Information System (INIS)

    Whitman, M.

    1983-09-01

    In 1979, the States of Nevada and Washington temporarily closed their commercial low-level radioactive waste (LLW) disposal facilities and South Carolina, the only other state hosting such a facility, restricted the amount of waste it would accept. All three states then announced that they did not intend to continue the status quo of accepting all of the country's commercial low-level radioactive waste. Faced with this situation, other states began considering alternative LLW management and disposal options. In the Rocky Mountain region, this evolved into discussions for the development of an interstate compact to manage low-level waste. Inherent in this management plan was a strategy to site and license a new LLW disposal facility for the Rocky Mountain region. The Rocky Mountain Low-Level Radioactive Waste Compact was negotiated over the course of a year, with final agreement on the language of the compact agreed to in early 1982. States eligible to join the compact are Arizona, Colorado, Nevada, New Mexico, Utah, and Wyoming. Colorado adopted the compact into law in 1982, and Nevada, New Mexico and Wyoming adopted it in 1983. Utah has joined the Northwest Compact, although it may decide to join the Rocky Mountain Compact after a new disposal facility is developed for the region. Arizona has taken no action on the Rocky Mountain Compact

  1. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    International Nuclear Information System (INIS)

    Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

    1999-01-01

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  2. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Hall, L.R.

    1995-05-30

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1.

  3. The TRIUMF thermal neutron facility as planned for operation by 1978

    International Nuclear Information System (INIS)

    Arrott, A.S.; Templeton, T.L.; Thorson, I.M.; Blaby, R.E.; Burgerjon, J.J.

    1977-08-01

    The concepts of the thermal neutron facility have been considerably modified since they were first put forth in 1971. The move has been toward simplification. This report describes the basic vacuum tank structure, its surrounding steel shielding and the concrete structure. The vacuum tank contains a target, moderator and reflector and has ports for the extraction of thermal neutron beams. It also has capabilities for producing mesons and for irradiation of targets in the primary proton beam. The system has been designed with flexibility for modification to meet possible future demands for irradiation facilities, radiography, or pulsed operation. The targets can be easily changed, and it is planned to do this to meet the heat transfer problems as they arise on going to higher beam currents. Feasibility studies for Pb-Bi and Pb targets have been carried out. The Pb target was chosen because of safety considerations and simpler design. (author)

  4. Calculation of parameters for inspection planning and evaluation: low enriched uranium conversion and fuel fabrication facilities

    International Nuclear Information System (INIS)

    Reardon, P.T.; Mullen, M.F.; Harms, N.L.

    1981-02-01

    As part of Task C.35 (Calculation of Parameters for Inspection Planning and Evaluation) of the US Program of Technical Assistance to IAEA Safeguards, Pacific Northwest Laboratory has performed some quantitative analyses of IAEA inspection activities at low-enriched uranium (LEU) conversion and fuel fabrication facilities. This report presents the results and conclusions of those analyses. Implementation of IAEA safeguards at LEU conversion and fuel fabrication facilities must take into account a variety of practical problems and constraints. One of the key concerns is the problem of flow verification, especially product verification. The objective of this report is to help put the problem of flow verification in perspective by presenting the results of some specific calculations of inspection effort and probability of detection for various product measurement strategies. In order to provide quantitative information about the advantages and disadvantages of the various strategies, eight specific cases were examined

  5. Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    TRINER, G.C.

    1999-01-01

    The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  6. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    International Nuclear Information System (INIS)

    Hall, L.R.

    1995-01-01

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1

  7. Planning Tools For Estimating Radiation Exposure At The National Ignition Facility

    International Nuclear Information System (INIS)

    Verbeke, J.; Young, M.; Brereton, S.; Dauffy, L.; Hall, J.; Hansen, L.; Khater, H.; Kim, S.; Pohl, B.; Sitaraman, S.

    2010-01-01

    A set of computational tools was developed to help estimate and minimize potential radiation exposure to workers from material activation in the National Ignition Facility (NIF). AAMI (Automated ALARA-MCNP Interface) provides an efficient, automated mechanism to perform the series of calculations required to create dose rate maps for the entire facility with minimal manual user input. NEET (NIF Exposure Estimation Tool) is a web application that combines the information computed by AAMI with a given shot schedule to compute and display the dose rate maps as a function of time. AAMI and NEET are currently used as work planning tools to determine stay-out times for workers following a given shot or set of shots, and to help in estimating integrated doses associated with performing various maintenance activities inside the target bay. Dose rate maps of the target bay were generated following a low-yield 10 16 D-T shot and will be presented in this paper.

  8. Surveillance and Maintenance Plan for the 202-S Reduction Oxidation (REDOX) Facility

    International Nuclear Information System (INIS)

    McGuire, J.J.

    1999-01-01

    This document provides a plan for implementing surveillance and maintenance (S and M) activities to ensure the 202-S Reduction Oxidation (REDOX) Facility is maintained in a safe, environmentally secure, and cost effective manner until subsequent closure during the final disposition phase of decommissioning. Specific objectives of the S and M program are to ensure adequate confinement of hazardous substances, to provide physical safety and security controls, to maintain the facilities in a manner that will minimize potential hazards to the public and workers, to provide adequate frequency of inspections to identify potential hazards, to maintain selected systems or equipment that will be essential for decommissioning activities in a shutdown but standby or operational mode, if economically justified, and to provide a mechanism for the identification and compliance with applicable environmental, safety and health, and safeguard and security requirements

  9. Planning, Management and Organizational Aspects of the Decommissioning of a Hot Cell Facility

    Energy Technology Data Exchange (ETDEWEB)

    Strufe, N. [Danish Decommissioning, Roskilde (Denmark)

    2013-08-15

    This CRP project document ''Planning, Management and Organizational Aspects in Decommissioning of a Hot Cell Facility'' aims to describe the establishment of a management organization that ensures that the DD Hot Cell Project is properly and safely conducted and that staff members, who are seconded to the project, have a strong feeling of ownership and being an integral part of the project. The objectives of the decommissioning project of the hot cell facility is to decontaminate the facility and to remove items that cannot be decontaminated on site, in order for the entire hot cell building to become useable for other purposes without any radiological restrictions. The project requires proper communication and coordination with all stakeholders on-site, comprehensive work plans and strict control of the individual working areas and operations. A project of this type obviously requires a strong and well managed and coordinated project organization. DD has established a management system - KMS. The purposes of the KMS are twofold. The system aims to secure the fulfilment of the conditions and requirements of quality set by the nuclear authorities. The system also aims to provide the basis for a rational and economically feasible operation with a high level of safety. One of the main lessons learned in this project is clear that is to ensure that the necessary resources are available and the required expertise is allocated timely for the performance of the project(s) a strong coordination and great flexibility within the DD organization is required. This document describes the approach and considerations from the project management point of view. The document initially gives an introduction to the hot cell decommissioning project followed by issues of the general considerations and planning of the project within the DD, including aspects on organisation, quality assurance and coordination. (author)

  10. The Abbott School Construction Program: Report on the NJ Department of Education Proposed Regulations on Long-Range Facilities Plans

    Science.gov (United States)

    Ponessa, Joan

    2004-01-01

    This report on Long Range Facilities Plans (LRFPs) analyzes regulations proposed by the New Jersey Department of Education (NJDOE) to implement the Educational Facilities Construction and Financing Act. (EFCFA). EFCFA, which authorizes and governs New Jersey's public school construction program, was enacted in July 2000 to implement the State…

  11. SNL Five-Year Facilities & Infrastructure Plan FY2015-2019

    Energy Technology Data Exchange (ETDEWEB)

    Cipriani, Ralph J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-12-01

    Sandia’s development vision is to provide an agile, flexible, safer, more secure, and efficient enterprise that leverages the scientific and technical capabilities of the workforce and supports national security requirements in multiple areas. Sandia’s Five-Year Facilities & Infrastructure Planning program represents a tool to budget and prioritize immediate and short-term actions from indirect funding sources in light of the bigger picture of proposed investments from direct-funded, Work for Others and other funding sources. As a complementary F&I investment program, Sandia’s indirect investment program supports incremental achievement of the development vision within a constrained resource environment.

  12. Review of past experiments at the FELIX facility and future plans for ITER applications

    International Nuclear Information System (INIS)

    Hua, T.Q.; Turner, L.R.

    1993-01-01

    FELIX is an experimental test facility at Argonne National Laboratory (ANL) for the study of electromagnetic effects in first wall, blanket, shield systems of fusion reactors. From 1983 to 1986 five major test series, including static and dynamic tests, were conducted and are reviewed in this paper. The dynamic tests demonstrated an important coupling effect between eddy currents and motion in a conducting structure. Recently the U.S. has proposed to the ITER Joint Central Team to use FELIX for testing mock-up components to study electromagnetic effects encountered during plasma disruptions and other off-normal events. The near and long term plans for ITER applications are discussed. (author)

  13. Heater test planning for the near surface test facility at the Hanford reservation

    International Nuclear Information System (INIS)

    DuBois, A.; Binnall, E.; Chan, T.; McEvoy, M.; Nelson, P.; Remer, J.

    1979-03-01

    The underground test facility NSTF being constructed at Gable Mountain, is the site for a group of experiments designed to evaluate the thermo-mechanical suitability of a deep basalt stratum as a permanent repository for nuclear waste. Thermo-mechanical modeling was performed to help design the instrumentation arrays for the three proposed heater tests (two full scale tests and one time scale test) and predict the thermal environment of the heaters and instruments. The modeling does not reflect recent RHO revisions to the in situ heater experiment plan. Heaters, instrumentation, and data acquisition system designs and recommendations were adapted from those used in Sweden

  14. Shuttle Flight Operations Contract Generator Maintenance Facility Land Use Control Implementation Plan (LUCIP)

    Science.gov (United States)

    Applegate, Joseph L.

    2014-01-01

    This Land Use Control Implementation Plan (LUCIP) has been prepared to inform current and potential future users of the Kennedy Space Center (KSC) Shuttle Flight Operations Contract Generator Maintenance Facility (SFOC; SWMU 081; "the Site") of institutional controls that have been implemented at the Site1. Although there are no current unacceptable risks to human health or the environment associated with the SFOC, an institutional land use control (LUC) is necessary to prevent human health exposure to antimony-affected groundwater at the Site. Controls will include periodic inspection, condition certification, and agency notification.

  15. Planning and managing future space facility projects. [management by objectives and group dynamics

    Science.gov (United States)

    Sieber, J. E.; Wilhelm, J. A.; Tanner, T. A.; Helmreich, R. L.; Burgenbauch, S. F.

    1979-01-01

    To learn how ground-based personnel of a space project plan and organize their work and how such planning and organizing relate to work outcomes, longitudinal study of the management and execution of the Space Lab Mission Development Test 3 (SMD 3) was performed at NASA Ames Research Center. A view of the problems likely to arise in organizations and some methods of coping with these problems are presented as well as the conclusions and recommendations that pertain strictly to SMD 3 management. Emphasis is placed on the broader context of future space facility projects and additional problems that may be anticipated. A model of management that may be used to facilitate problem solving and communication - management by objectives (MBO) is presented. Some problems of communication and emotion management that MBO does not address directly are considered. Models for promoting mature, constructive and satisfying emotional relationships among group members are discussed.

  16. Proposed plan for the Tank 105-C Hazardous Waste Management Facility. Revision 1

    International Nuclear Information System (INIS)

    Miles, W.C. Jr.

    1994-01-01

    This Proposed Plan was developed to describe the remedial action selected at the Tank 105-C Hazardous Waste Management Facility (HWMF) source-specific unit within the C-Area Fundamental Study Area (FSA) at the Savannah River Site (SRS) and to fulfill Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. This 8,400 gallon capacity tank was certified and accepted closed according to a closure plan approved by the state of South Carolina under the Resource Conservation and Recovery Act (RCRA) authority in January 1991. As a result of the closure, previously performed under RCRA, the unit poses no current or potential threat to human health or the environment. Accordingly, no further remedial action is necessary under CERCLA

  17. Demonstration tools for the facility/land use planning process at Rocky Flats

    International Nuclear Information System (INIS)

    Ryan, K.B.

    1994-01-01

    The new mission for the Rocky Flats Site states, open-quotes Manage waste and materials, clean up and convert the Rocky Flats Site to beneficial use in a manner that is safe, environmentally and socially responsible, physical secure, and cost-effective.close quotes. In addition, community recognition and support is encouraged and expected. To accomplish this ambitious mission of converting to another use and incorporating stakeholder input, many tools must be developed. These tools must be clearly understandable and readily available, with the hope and plan that similar outcomes will be much more apparent if the same or similar tools are applied by all decision markers, both internal and external. Since the task is monumental and extremely complex, establishing and understanding these available tools early in the planning process is important. All decision makers must be identified and the availability of the tools should be shared to eliminate redundancy and expedite the planning process. Most documents utilized for decision making are very technical in nature. Since numerous and varied stakeholders will be involved, these documents must be socialized or open-quotes detechnicalized.close quotes This paper discusses developing internal and universally acceptable demonstration tools for explaining how facilities and land will be analyzed for constraints and opportunities during the planning process

  18. Corrective Action Investigation Plan for Corrective Action Unit 232: Area 25 Sewage Lagoons, Nevada Test Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    USDOE/NV

    1999-05-01

    The Corrective Action Investigation Plan for Corrective Action Unit 232, Area 25 Sewage Lagoons, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U.S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U. S. Department of Defense. Corrective Action Unit 232 consists of Corrective Action Site 25-03-01, Sewage Lagoon. Corrective Action Unit 232, Area 25 Sewage Lagoons, received sanitary effluent from four buildings within the Test Cell ''C'' Facility from the mid-1960s through approximately 1996. The Test Cell ''C'' Facility was used to develop nuclear propulsion technology by conducting nuclear test reactor studies. Based on the site history collected to support the Data Quality Objectives process, contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, Resource Conservation and Recovery Act metals, petroleum hydrocarbons, polychlorinated biphenyls, pesticides, herbicides, gamma emitting radionuclides, isotopic plutonium, isotopic uranium, and strontium-90. A detailed conceptual site model is presented in Section 3.0 and Appendix A of this Corrective Action Investigation Plan. The conceptual model serves as the basis for the sampling strategy. Under the Federal Facility Agreement and Consent Order, the Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of corrective action alternatives in the Corrective Action Decision Document.

  19. Project management plan for the isotopes facilities deactivation project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-08-01

    Purpose of the deactivation project is to place former isotopes production facilities at ORNL in a safe, stable, and environmentally sound condition suitable for an extended period of minimum surveillance and maintenance. This management plan was prepared to document project objectives, define organizational relationships and responsibilities, and outline the management control systems. The project has adopted the strategy of deactivating the simple facilities first. The plan provides a road map for the quality assurance program and identifies other documents supporting the Isotopes Facilities Deactivation Project

  20. Planning Considerations for a Mars Sample Receiving Facility: Summary and Interpretation of Three Design Studies

    Science.gov (United States)

    Beaty, David W.; Allen, Carlton C.; Bass, Deborah S.; Buxbaum, Karen L.; Campbell, James K.; Lindstrom, David J.; Miller, Sylvia L.; Papanastassiou, Dimitri A.

    2009-10-01

    It has been widely understood for many years that an essential component of a Mars Sample Return mission is a Sample Receiving Facility (SRF). The purpose of such a facility would be to take delivery of the flight hardware that lands on Earth, open the spacecraft and extract the sample container and samples, and conduct an agreed-upon test protocol, while ensuring strict containment and contamination control of the samples while in the SRF. Any samples that are found to be non-hazardous (or are rendered non-hazardous by sterilization) would then be transferred to long-term curation. Although the general concept of an SRF is relatively straightforward, there has been considerable discussion about implementation planning. The Mars Exploration Program carried out an analysis of the attributes of an SRF to establish its scope, including minimum size and functionality, budgetary requirements (capital cost, operating costs, cost profile), and development schedule. The approach was to arrange for three independent design studies, each led by an architectural design firm, and compare the results. While there were many design elements in common identified by each study team, there were significant differences in the way human operators were to interact with the systems. In aggregate, the design studies provided insight into the attributes of a future SRF and the complex factors to consider for future programmatic planning.

  1. Dual Axis Radiographic Hydrodynamic Test Facility mitigation action plan. Annual report for 1997

    Energy Technology Data Exchange (ETDEWEB)

    Haagenstad, H.T.

    1998-01-15

    This Mitigation Action Plan Annual Report (MAPAR) has been prepared by the US Department of Energy (DOE) as part of implementing the Dual Axis Radiographic Hydrodynamic Test Facility (DARHT) Mitigation Action Plan (MAP). This MAPAR provides a status on specific DARHT facility design- and construction-related mitigation actions that have been initiated in order to fulfill DOE`s commitments under the DARHT MAP. The functions of the DARHT MAP are to (1) document potentially adverse environmental impacts of the Phased Containment Option delineated in the Final EIS, (2) identify commitments made in the Final EIS and ROD to mitigate those potential impacts, and (3) establish Action Plans to carry out each commitment (DOE 1996). The DARHT MAP is divided into eight sections. Sections 1--5 provide background information regarding the NEPA review of the DARHT project and an introduction to the associated MAP. Section 6 references the Mitigation Action Summary Table which summaries the potential impacts and mitigation measures; indicates whether the mitigation is design-, construction-, or operational-related; the organization responsible for the mitigation measure; and the projected or actual completion data for each mitigation measure. Sections 7 and 8 discuss the Mitigation Action Plan Annual Report and Tracking System commitment and the Potential Impacts, Commitments, and Action Plans respectively. Under Section 8, potential impacts are categorized into five areas of concern: General Environment, including impacts to air and water; Soils, especially impacts affecting soil loss and contamination; Biotic Resources, especially impacts affecting threatened and endangered species; Cultural/Paleontological Resources, especially impacts affecting the archeological site known as Nake`muu; and Human Health and Safety, especially impacts pertaining to noise and radiation. Each potential impact includes a brief statement of the nature of the impact and its cause(s). The commitment

  2. Computer mapping and visualization of facilities for planning of D and D operations

    International Nuclear Information System (INIS)

    Wuller, C.E.; Gelb, G.H.; Cramond, R.; Cracraft, J.S.

    1995-01-01

    The lack of as-built drawings for many old nuclear facilities impedes planning for decontamination and decommissioning. Traditional manual walkdowns subject workers to lengthy exposure to radiological and other hazards. The authors have applied close-range photogrammetry, 3D solid modeling, computer graphics, database management, and virtual reality technologies to create geometrically accurate 3D computer models of the interiors of facilities. The required input to the process is a set of photographs that can be acquired in a brief time. They fit 3D primitive shapes to objects of interest in the photos and, at the same time, record attributes such as material type and link patches of texture from the source photos to facets of modeled objects. When they render the model as either static images or at video rates for a walk-through simulation, the phototextures are warped onto the objects, giving a photo-realistic impression. The authors have exported the data to commercial CAD, cost estimating, robotic simulation, and plant design applications. Results from several projects at old nuclear facilities are discussed

  3. Quality Assessment of Family Planning Sterilization Services at Health Care Facilities: Case Record Audit.

    Science.gov (United States)

    Mathur, Medha; Goyal, Ram Chandra; Mathur, Navgeet

    2017-05-01

    Quality of sterilization services is a matter of concern in India because population control is a necessity. Family Planning Sterilization (FPS) services provided at public health care facilities need to be as per Standard Operating Procedures. To assess the quality of FPS services by audit of case records at selected health care facilities. This cross-sectional study was conducted for two and a half year duration at selected public health care facilities of central India by simple random sampling where FPS services were provided. As per the standards of Government of India, case records were audited and compliance was calculated to assess the quality of services. Results of record audit were satisfactory but important criteria like previous contraceptive history and postoperative counselling were found to be deviated from standards. At Primary Health Centres (PHCs) only 89.5% and at Community Health Centres (CHCs) 58.7% of records were having details of previous contraceptive history. Other criteria like mental illness (only 70% at CHCs) assessment were also inadequate. Although informed consent was found to be having 100% compliance in all records. Quality of care in FPS services is the matter of concern in present scenario for better quality of services. This study may enlighten the policy makers regarding improvements needed for providing quality care.

  4. Regional health care planning: a methodology to cluster facilities using community utilization patterns.

    Science.gov (United States)

    Delamater, Paul L; Shortridge, Ashton M; Messina, Joseph P

    2013-08-22

    Community-based health care planning and regulation necessitates grouping facilities and areal units into regions of similar health care use. Limited research has explored the methodologies used in creating these regions. We offer a new methodology that clusters facilities based on similarities in patient utilization patterns and geographic location. Our case study focused on Hospital Groups in Michigan, the allocation units used for predicting future inpatient hospital bed demand in the state's Bed Need Methodology. The scientific, practical, and political concerns that were considered throughout the formulation and development of the methodology are detailed. The clustering methodology employs a 2-step K-means + Ward's clustering algorithm to group hospitals. The final number of clusters is selected using a heuristic that integrates both a statistical-based measure of cluster fit and characteristics of the resulting Hospital Groups. Using recent hospital utilization data, the clustering methodology identified 33 Hospital Groups in Michigan. Despite being developed within the politically charged climate of Certificate of Need regulation, we have provided an objective, replicable, and sustainable methodology to create Hospital Groups. Because the methodology is built upon theoretically sound principles of clustering analysis and health care service utilization, it is highly transferable across applications and suitable for grouping facilities or areal units.

  5. 241-CX-70, 241-CX-71, and 241-CX-72 underground storage tanks at the strontium semiworks facility supplemental information to the Hanford Facility Contingency Plan

    International Nuclear Information System (INIS)

    Ingle, S.J.

    1996-03-01

    This document is a unit-specific contingency plan for the underground storage tanks at the Strontium Semiworks Facility and is intended to be used as a supplement to the Hanford Facility Contingency Plan. This unit-specific plan is to be used to demonstrate compliance with the contingency plan requirements of WAC 173-303 for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units. Radioactive material is contained in three underground storage tanks: 241-CX-70, 241-CX-71, and 241-CX-72. Tank 241-CX-70 has been emptied, except for residual quantities of waste, and has been classified as an elementary neutralization tank under the RCRA. Tanks 241-CX-71 and 241-CX-72 contain radioactive and Washington State-only dangerous waste material, but do not present a significant hazard to adjacent facilities, personnel, or the environment. Currently, dangerous waste management activities are not being applied at the tanks. It is unlikely that any incidents presenting hazards to public health or the environment would occur at the Strontium Semiworks Facility

  6. An Investigation of Telecom Mobile Data Billing Plans

    Directory of Open Access Journals (Sweden)

    Yi-Bing Lin

    2016-08-01

    Full Text Available In the recent years, mobile operators have provided many billing alternatives such as limited and unlimited billing plans, and shared and non-shared data plans for the users with different needs. A non-shared data plan is designed for a single user with a limited monthly data allowance. On the other hand, the monthly data allowance of a shared data plan is shared by a group of users with multiple devices. The mobile operators often conduct the primary price study to compare their billing plans, which shows the relationship between the prices of the billing plans against the fixed amounts of data usage. Although the primary price study can easily and quickly draw the conclusions, it only provides rough billing plan suggestions. In reality, the amounts of data usage are not fixed, and therefore should be measured from commercial mobile networks to reflect the user behaviors on data usage. This paper proposes an analytical approach by using the measured data of Chunghwa Telecom Co., Ltd. (CHT, the largest telecommunications company in Taiwan, to derive the expected payments of various billing plans. The results of the analytical model are more accurate than those of the primary price study, and therefore provide better suggestions for billing plan selection. Other mobile operators can easily use our model to analyze the billing alternatives with their measured data.

  7. Comprehensive development plans for the low- and intermediate-level radioactive waste disposal facility in Korea and preliminary safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Kang Il; Kim, Jin Hyeong; Kwon, Mi Jin; Jeong, Mi Seon; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-12-15

    The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

  8. Oral medicines for children in the European paediatric investigation plans.

    Directory of Open Access Journals (Sweden)

    Diana A van Riet-Nales

    Full Text Available INTRODUCTION: Pharmaceutical industry is no longer allowed to develop new medicines for use in adults only, as the 2007 Paediatric Regulation requires children to be considered also. The plans for such paediatric development called Paediatric Investigation Plans (PIPs are subject to agreement by the European Medicines Agency (EMA and its Paediatric Committee (PDCO. The aim of this study was to evaluate the key characteristics of oral paediatric medicines in the PIPs and the changes implemented as a result of the EMA/PDCO review. METHODS: All PIPs agreed by 31 December 2011 were identified through a proprietary EMA-database. PIPs were included if they contained an agreed proposal to develop an oral medicine for children 0 to 11 years. Information on the therapeutic area (EMA classification system; target age range (as defined by industry and pharmaceutical characteristics (active substance, dosage form(s as listed in the PIP, strength of each dosage form, excipients in each strength of each dosage form was extracted from the EMA website or the EMA/PDCO assessment reports. RESULTS: A hundred and fifty PIPs were included corresponding to 16 therapeutic areas and 220 oral dosage forms in 431 strengths/compositions. Eighty-two PIPs (37% included tablets, 44 (20% liquids and 35 (16% dosage forms with a specific composition/strength that were stored as a solid but swallowed as a liquid e.g. dispersible tablets. The EMA/PDCO review resulted in an increase of 13 (207 to 220 oral paediatric dosage forms and 44 (387 to 431 dosage forms with a specific composition/strength. For many PIPs, the target age range was widened and the excipient composition and usability aspects modified. CONCLUSION: The EMA/PDCO review realized an increase in the number of requirements for the development of oral dosage forms and a larger increase in the number of dosage forms with a specific composition/strength, both targeting younger children. Changes to their pharmaceutical

  9. Investigation of induced recirculation during planned ventilation system maintenance

    Science.gov (United States)

    Pritchard, C.J.; Scott, D.F.; Noll, J.D.; Voss, B.; Leonis, D.

    2015-01-01

    The Office of Mine Safety and Health Research (OMSHR) investigated ways to increase mine airflow to underground metal/nonmetal (M/NM) mine working areas to improve miners’ health and safety. One of those areas is controlled recirculation. Because the quantity of mine air often cannot be increased, reusing part of the ventilating air can be an effective alternative, if implemented properly, until the capacity of the present system is improved. The additional airflow can be used to provide effective dilution of contaminants and higher flow velocities in the underground mine environment. Most applications of controlled recirculation involve taking a portion of the return air and passing it back into the intake to increase the air volume delivered to the desired work areas. OMSHR investigated a Nevada gold mine where shaft rehabilitation was in progress and one of the two main fans was shut down to allow reduced air velocity for safe shaft work. Underground booster fan operating pressures were kept constant to maintain airflow to work areas, inducing controlled recirculation in one work zone. Investigation into system behavior and the effects of recirculation on the working area during times of reduced primary ventilation system airflow would provide additional information on implementation of controlled recirculation into the system and how these events affect M/NM ventilation systems. The National Institute for Occupational Safety and Health monitored the ventilation district when both main fans were operating and another scenario with one of the units turned off for maintenance. Airflow and contaminants were measured to determine the exposure effects of induced recirculation on miner health. Surveys showed that 19% controlled recirculation created no change in the overall district airflow distribution and a small reduction in district fresh air intake. Total dust levels increased only modestly and respirable dust levels were also low. Diesel particulate matter

  10. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Wickline, Alfred

    2005-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action

  11. ERDA test facilities, East Mesa Test Site. Geothermal resource investigations, Imperial Valley, California

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    Detailed specifications which must be complied with in the construction of the ERDA Test Facilities at the East Mesa Site for geothermal resource investigations in Imperial Valley, California are presented for use by prospective bidders for the construction contract. The principle construction work includes a 700 gpm cooling tower with its associated supports and equipment, pipelines from wells, electrical equipment, and all earthwork. (LCL)

  12. Investigation on candidates of principal facilities for exposure dose to public for the facilities using nuclear material

    International Nuclear Information System (INIS)

    Shimazaki, Yosuke; Sawahata, Hiroaki; Takada, Shoji; Fujimoto, Nozomu

    2015-01-01

    HTTR holds the nuclear fuel material use facilities in its reactor facilities, for the purpose of study on the fracture behavior of fuel and release behavior of fission products, development of high-performance fuel, and measurement of neutron flux. Due to the revision of the 'Act on the regulation of nuclear source material, nuclear fuel material and reactor', the facilities having the 'Important safety-related facilities' among the facilities applicable to the Enforcement Ordinance Article 41 (Article 41 facilities) has come to need to conform to the 'Regulations concerning standards for the location, structure, and equipment of used facilities and others'. In this case, actions such as modification by all possible means are required. The nuclear fuel substance use facilities of HTTR correspond to Article 41 facilities. So, whether it is a candidate for the 'Important safety-related facilities' has been examined. As a result, it is confirmed that the facilities are not correspond to the 'Important safety-related facilities', and it has been concluded that modification measures for the purpose of conforming to this approval standard rule are not necessary as of the present. (A.O.)

  13. Phase I Investigations at the Former CCC/USDA Grain Storage Facility in Montgomery City, Missouri, in 2010-2011

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division. Applied Geoscience and Environmental Restoration Program

    2012-11-01

    This report presents the technical findings of Phase I of Argonne’s studies. The Phase I field investigation was initiated on October 18, 2010. The work was conducted in accord with (1) the final site-specific Phase I Work Plan for Montgomery City (Argonne 2010; approved by the MDNR [2010]); (2) applicable Missouri regulations; and (3) the standard operating procedures, quality assurance/quality control (QA/QC) measures, and general health and safety policies outlined in the Master Work Plan (Argonne 2002) for operations in Kansas, which was reviewed by the MDNR and accepted for current use. A draft master plan specific to work in Missouri and a set of draft standard operating procedures are in review with the MDNR. The site-specific Work Plan for Montgomery City (Argonne 2010) (1) summarizes the pre-existing knowledge base for the Montgomery City investigation site compiled by Argonne and (2) describes the site-specific technical objectives and the intended scope of work developed for the first phase of the investigation. Three primary technical objectives were identified for the Phase I studies, as follows: 1. Update the presently identified inventory and status of private and public drinking water wells in the immediate vicinity of the former CCC/USDA grain storage facility, and sample the identified wells for volatile organic compounds (VOCs) and geochemical analyses. In conjunction with this effort, determine the present sources(s) of drinking water for all residents in an approximate 0.5-mi radius of the former CCC/USDA facility. 2. Investigate for possible evidence of a soil source of carbon tetrachloride contamination in the unconsolidated sediments beneath the former CCC/USDA facility that might affect the underlying bedrock aquifer units. 3. Obtain preliminary information on the site-specific lithologic and hydrologic characteristics of the unconsolidated sediments overlying bedrock at the former CCC/USDA grain storage location. Section 2 of this report

  14. Use of information systems in Air Force medical treatment facilities in strategic planning and decision-making.

    Science.gov (United States)

    Yap, Glenn A; Platonova, Elena A; Musa, Philip F

    2006-02-01

    An exploratory study used Ansoff's strategic planning model as a framework to assess perceived effectiveness of information systems in supporting strategic business plan development at Air Force medical treatment facilities (MTFs). Results showed information systems were most effective in supporting historical trend analysis, strategic business plans appeared to be a balance of operational and strategic plans, and facilities perceived a greater need for new clinical, vice administrative, information systems to support strategic planning processes. Administrators believed information systems should not be developed at the local level and perceived information systems have the greatest impact on improving clinical quality outcomes, followed by ability to deliver cost effective care and finally, ability to increase market share.

  15. D-Side: A Facility and Workforce Planning Group Multi-criteria Decision Support System for Johnson Space Center

    Science.gov (United States)

    Tavana, Madjid

    2005-01-01

    "To understand and protect our home planet, to explore the universe and search for life, and to inspire the next generation of explorers" is NASA's mission. The Systems Management Office at Johnson Space Center (JSC) is searching for methods to effectively manage the Center's resources to meet NASA's mission. D-Side is a group multi-criteria decision support system (GMDSS) developed to support facility decisions at JSC. D-Side uses a series of sequential and structured processes to plot facilities in a three-dimensional (3-D) graph on the basis of each facility alignment with NASA's mission and goals, the extent to which other facilities are dependent on the facility, and the dollar value of capital investments that have been postponed at the facility relative to the facility replacement value. A similarity factor rank orders facilities based on their Euclidean distance from Ideal and Nadir points. These similarity factors are then used to allocate capital improvement resources across facilities. We also present a parallel model that can be used to support decisions concerning allocation of human resources investments across workforce units. Finally, we present results from a pilot study where 12 experienced facility managers from NASA used D-Side and the organization's current approach to rank order and allocate funds for capital improvement across 20 facilities. Users evaluated D-Side favorably in terms of ease of use, the quality of the decision-making process, decision quality, and overall value-added. Their evaluations of D-Side were significantly more favorable than their evaluations of the current approach. Keywords: NASA, Multi-Criteria Decision Making, Decision Support System, AHP, Euclidean Distance, 3-D Modeling, Facility Planning, Workforce Planning.

  16. An Empirical Investigation of Strategic Planning in QS Practices

    OpenAIRE

    Murphy, Roisin

    2012-01-01

    The benefit of engaging in strategic planning has been well documented over several decades of strategic management research. Despite the significant body of existing knowledge in the field, there remains a limited collection of empirically tested research pertaining to strategic planning within professional service firms (PSFs) in construction, particularly from an Irish context. The research is an exploratory study involving in-depth, semi-structured interviews and a widespread survey of...

  17. 1325-N Liquid Waste Disposal Facility Supplemental Information to the Hanford Facility Contingency Plan (DOE/RL-93-75)

    International Nuclear Information System (INIS)

    Edens, V.G.

    1998-03-01

    The 1325-N Liquid Waste Disposal Facility located at the 100-N Area of the Hanford Site started receiving part of the N Reactor liquid radioactive effluent flow in 1983. In September 1985, the 1325-N Facility became the primary liquid waste disposal system for the N Reactor. The facility is located approximately 60 feet above and 2000 feet east of the shore of the Columbia River. Waste stream discharges were ceased in April 1991.Specific information on types of waste discharged to 1325-N are contained within the Part A, Form 3, Permit application of this unit

  18. Acceptance inspection plan 105KE Facility modifications for fuel retrieval subproject

    International Nuclear Information System (INIS)

    Shen, E.J.

    1998-01-01

    The acceptance inspection of construction by Fluor Daniel Hanford (FDH) is performed to provide assurance that fabrication, construction, and installation are in accordance with approved contract documents. Approved contract documents used to perform inspections may include specifications, drawings, and contractor submittals such as fabrication drawings, procedures, etc. The amount or degree of inspection activity is tailored to the project as determined by the project team so that the effort and cost expended are commensurate with the importance of the facility in terms of function and safety. Inspections are documented to provide verification of the acceptability of the work performed. This document identifies the inspections and documentation forms to be provided. It is prepared and implemented with the understanding that the construction contractor is fully responsible for compliance with contract documents and for the quality of work performed. Inspections performed are in accordance with approved procedures. The Manager of Acceptance Inspection is responsible for the implementation of this plan and assignment of personnel for the work. Inspections are conducted by personnel who are qualified and certified, to perform their assigned task. The Acceptance Inspection Plan is organized in the Construction Specification Institute (CSI) format to cross reference design specification sections with sections of the AI Plan. In each AI Plan section the applicable specification section subject will be identified followed by the appropriate inspection requirements. General surveillances will be listed when applicable. Acceptance Inspection Reports are provided to document inspections not documented on a test report (i.e., Soil Test Data, Concrete Test Report, NDE/Weld Record, Leak/Pressure Test Certification, Backflow Device Test Report, Nonconformance Report, Deficiency Report, and/or Contractors testing forms)

  19. Acceptance inspection plan 105KW Facility modifications for fuel retrieval subproject

    International Nuclear Information System (INIS)

    Shen, E.J.

    1998-01-01

    The acceptance inspection of construction by Fluor Daniel Hanford (FDH) is performed to provide assurance that fabrication, construction, and installation are in accordance with approved contract documents. Approved contract documents used to perform inspections may include specifications, drawings, and contractor submittals such as fabrication drawings, procedures, etc. The amount or degree of inspection activity is tailored to the project as determined by the project team so that the effort and cost expended are commensurate with the importance of the facility in terms of function and safety. Inspections are documented to provide verification of the acceptability of the work performed. This document identifies the inspections and documentation forms to be provided. It is prepared and implemented with the understanding that the construction contractor is fully responsible for compliance with contract documents and for the quality of.work performed. Inspections performed are in accordance with approved procedures. The Manager of Acceptance Inspection is responsible for the implementation of this plan and assignment of personnel for the work. Inspections are conducted by personnel who are qualified and certified to perform their assigned task. The Acceptance Inspection Plan is organized in the Construction Specification Institute (CSI) format to cross reference design specification sections with sections of the AI Plan. In each AI Plan section the applicable specification section subject will be identified followed by the appropriate inspection requirements. General surveillances will be listed when applicable. Acceptance Inspection Reports are provided to document inspections not documented on a test report (i.e., Soil Test Data, Concrete Test Report, NDE/Weld Record, Leak/Pressure Test Certification, Backflow Device Test Report, Nonconformance Report, Deficiency Report, and/or Contractors testing forms)

  20. Implementation plan for liquid low-level radioactive waste tank systems for fiscal year 1995 at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-06-01

    This document is the third annual revision of the plans and schedules for implementing the Federal Facility Agreement (FFA) compliance program, originally submitted in 1992 as ES/ER-17 ampersand D1, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This document summarizes the progress that has been made to date in implementing the plans and schedules for meeting the FFA commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that have been removed from service. ORNL has a comprehensive program underway to upgrade the LLLW System as necessary to meet the FFA requirements. The tank systems that are removed from service are being investigated and remediated through the CERCLA process. Waste and risk characterizations have been submitted. Additional data will be prepared and submitted to EPA/TDEC as tanks are taken out of service and as required by the remedial investigation/feasibility study (RI/FS) process. Chapter 1 provides general background information and philosophies that led to the plans and schedules that appear in Chaps. 2 through 5