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Sample records for safety plan revision

  1. Revised GCFR safety program plan

    International Nuclear Information System (INIS)

    Kelley, A.P.; Boyack, B.E.; Torri, A.

    1980-05-01

    This paper presents a summary of the recently revised gas-cooled fast breeder reactor (GCFR) safety program plan. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). Finally, the means by which the plan is being implemented are discussed

  2. Tank farm health and safety plan. Revision 2

    International Nuclear Information System (INIS)

    Mickle, G.D.

    1995-01-01

    This Tank Farm Health and Safety Plan (HASP) for the conduct of all operations and work activities at the Hanford Site 200 Area Tank Farms is provided in order to minimize health and safety risks to workers and other onsite personnel. The HASP accomplishes this objective by establishing requirements, providing general guidelines, and conveying farm and facility-specific hazard communication information. The HASP, in conjunction with the job-specific information required by the HASP, is provided also as a reference for use during the planning of work activities at the tank farms. This HASP applies to Westinghouse Hanford Company (WHC), other prime contractors to the U.S. Department of Energy (DOE), and subcontractors to WHC who may be involved in tank farm work activities. This plan is intended to be both a requirements document and a useful reference to aid tank farm workers in understanding the safety and health issues that are encountered in routine and nonroutine work activities. The HASP defines the health and safety responsibilities of personnel working at the tank farms. It has been prepared in recognition of and is consistent with National Institute of Safety and Health (NIOSH), and Occupational Safety and Health Administration (OSHA)/Unlimited State Coast Guard (USCG)/U.S. Environmental Protection Agency (EPA), Occupational Safety and Health Guidance Manual for Hazardous Waste Site Activities (NIOSH 1985); WHC-CM-4-3, Industrial Safety Manual, Volume 4, open-quotes Health and Safety Programs for Hazardous Waste Operations;close quotes 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response; WHC-CM-1-1, Management Policies; and WHC-CM-1-3, Management Requirements and Procedures. When differences in governing regulations or policies exist, the more stringent requirements shall apply until the discrepancy can be resolved

  3. Tank farm health and safety plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Mickle, G.D.

    1995-03-29

    This Tank Farm Health and Safety Plan (HASP) for the conduct of all operations and work activities at the Hanford Site 200 Area Tank Farms is provided in order to minimize health and safety risks to workers and other onsite personnel. The HASP accomplishes this objective by establishing requirements, providing general guidelines, and conveying farm and facility-specific hazard communication information. The HASP, in conjunction with the job-specific information required by the HASP, is provided also as a reference for use during the planning of work activities at the tank farms. This HASP applies to Westinghouse Hanford Company (WHC), other prime contractors to the U.S. Department of Energy (DOE), and subcontractors to WHC who may be involved in tank farm work activities. This plan is intended to be both a requirements document and a useful reference to aid tank farm workers in understanding the safety and health issues that are encountered in routine and nonroutine work activities. The HASP defines the health and safety responsibilities of personnel working at the tank farms. It has been prepared in recognition of and is consistent with National Institute of Safety and Health (NIOSH), and Occupational Safety and Health Administration (OSHA)/Unlimited State Coast Guard (USCG)/U.S. Environmental Protection Agency (EPA), Occupational Safety and Health Guidance Manual for Hazardous Waste Site Activities (NIOSH 1985); WHC-CM-4-3, Industrial Safety Manual, Volume 4, {open_quotes}Health and Safety Programs for Hazardous Waste Operations;{close_quotes} 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response; WHC-CM-1-1, Management Policies; and WHC-CM-1-3, Management Requirements and Procedures. When differences in governing regulations or policies exist, the more stringent requirements shall apply until the discrepancy can be resolved.

  4. Seismic safety margin research program. Program plan, Revision I

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.

    1978-01-01

    The overall objective of the SSMRP is to develop mathematical models that realistically predict the probability of radioactive releases from seismically induced events in nuclear power plants. These models will be used for four purposes: (1) To perform sensitivity studies to determine the weak links in seismic methodology. The weak links will then be improved by research and development. (2) To estimate the probability of release for a plant. It is believed that the major difficulty in the program will be to obtain acceptably small confidence limits on the probability of release. (3) To estimate the conservatisms in the Standard Review Plan (SRP) seismic design methodology. This will be done by comparing the results of the SRP methodology and the methodology resulting from the research and development in (1). (4) To develop an improved seismic design methodology based on probability. The Phase I objective proposed in this report is to develop mathematical models which will accomplish the purposes No. 1 and No. 2 with simplified assumptions such as linear elastic analysis, limited assessment on component fragility (considering only accident sequences leading to core melt), and simplified safety system

  5. Seismic safety margin research program. Program plan, Revision II

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.; Johnson, J.J.; Dong, R.G.

    1978-01-01

    The document has been prepared pursuant to the second meeting of the Senior Research Review Group of the Seismic Safety Margin Research Program (SSMRP), which was held on June 15, 16, 1978. The major portion of the material contained in the document is descriptions of specific subtasks to be performed on the SSMRP. This is preceded by a brief discussion of the objective of the SSMRP and the approach to be used. Specific subtasks to be performed in Phase I of the SSMRP are as follows: (1) plant/site selection, (2) seismic input, (3) soil structure interaction, (4) structural building response, (5) structural sub-system response, (6) fragility, (7) system analysis, and (8) Phase II task definition

  6. Standard Review Plan for the review of safety analysis reports for nuclear power plants, Revision No. 7 to Section 9

    International Nuclear Information System (INIS)

    1978-03-01

    Revision No. 1 to Section 9 of the Standard Review Plan incorporates changes that have been developed since the original issuance in September 1975, many of which are editorial in nature, to reflect current staff practice in the review of safety analysis reports for nuclear power plants

  7. Safety Evaluation Report on Tennessee Valley Authority: Revised Corporate Nuclear Performance Plan

    International Nuclear Information System (INIS)

    1987-07-01

    The TVA Corporate Nuclear Performance Plan addresses those corporate concerns identified by the NRC staff. Because much of the TVA corporate plan is programmatic, its effectiveness depends on its implementation, and the NRC staff plans to closely monitor this implementation. The NRC staff will address site-specific concerns in subsequent SERs on each volume of the Nuclear Performance Plan. On the basis of its review, the NRC staff finds TVA's revised Corporate Nuclear Performance Plan (Revision 4) acceptable. The NRC staff concludes that the organization and staffing of TVA's Office of Nuclear Power and the programmatic improvements in place or under way are sufficient, if implemented properly, to resolve the problems at the corporate level that led to issuance of the 10 CFR 50.54(f) letter dated September 17, 1985, and to support continuing TVA nuclear activities, including plant operations. 19 refs., 3 figs

  8. Site safety plan for Lawrence Livermore National Laboratory CERCLA investigations at site 300. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Kilmer, J.

    1997-08-01

    Various Department of Energy Orders incorporate by reference, health and safety regulations promulgated by the Occupational Safety and Health Administration (OSHA). One of the OSHA regulations, 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response, requires that site safety plans are written for activities such as those covered by work plans for Site 300 environmental investigations. Based upon available data, this Site Safety Plan (Plan) for environmental restoration has been prepared specifically for the Lawrence Livermore National Laboratory Site 300, located approximately 15 miles east of Livermore, California. As additional facts, monitoring data, or analytical data on hazards are provided, this Plan may need to be modified. It is the responsibility of the Environmental Restoration Program and Division (ERD) Site Safety Officer (SSO), with the assistance of Hazards Control, to evaluate data which may impact health and safety during these activities and to modify the Plan as appropriate. This Plan is not `cast-in-concrete.` The SSO shall have the authority, with the concurrence of Hazards Control, to institute any change to maintain health and safety protection for workers at Site 300.

  9. Savannah River Site management response plan for chemical safety vulnerability field assessment. Revision 1

    International Nuclear Information System (INIS)

    Kahal, E.J.; Murphy, S.L.; Salaymeh, S.R.

    1994-09-01

    As part of the U.S. Department of Energy's (DOE) initiative to identify potential chemical safety vulnerabilities in the DOE complex, the Chemical Safety Vulnerability Core Working Group issued a field verification assessment report. While the report concluded that Savannah River Site (SRS) is moving in a positive direction, the report also identified five chemical safety vulnerabilities with broad programmatic impact that are not easily nor quickly remedied. The May 1994 SRS Management Response Plan addressed the five SRS vulnerabilities identified in the field assessment report. The SRS response plan listed observations supporting the vulnerabilities and any actions taken or planned toward resolution. Many of the observations were resolved by simple explanations, such as the existence of implementation plans for Safety Analysis Report updates. Recognizing that correcting individual observations does not suffice in remedying the vulnerabilities, a task team was assembled to address the broader programmatic issues and to recommend corrective actions

  10. High-heat tank safety issue resolution program plan. Revision 2

    International Nuclear Information System (INIS)

    Wang, O.S.

    1994-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank 241-C-106. The heat source of approximately 110,000 Btu/hr is the radioactive decay of the stored waste material (primarily 90 Sr) inadvertently transferred into the tank in the later 1960s. Currently, forced ventilation, with added water to promote thermal conductivity and evaporation cooling, is used for heat removal. The method is very effective and economical. At this time, the only viable solution identified to permanently resolve this safety issue is the removal of heat-generating waste in the tank. This solution is being aggressively pursued as the only remediation method to this safety issue, and tank 241-C-106 has been selected as the first single-shell tank for retrieval. The current cooling method and other alternatives are addressed in this program as means to mitigate this safety issue before retrieval. This program plan has three parts. The first part establishes program objectives and defines safety issue, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and other alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. A table of best-estimate schedules for the key tasks is also included in this program plan

  11. Demonstration testing and evaluation of in situ soil heating. Health and safety plan (Revision 2)

    Energy Technology Data Exchange (ETDEWEB)

    Dev, H.

    1994-12-28

    This document is the Health and Safety Plan (HASP) for the demonstration of IITRI`s EM Treatment Technology. In this process, soil is heated in situ by means of electrical energy for the removal of hazardous organic contaminants. This process will be demonstrated on a small plot of contaminated soil located in the Pit Area of Classified Burial Ground K-1070-D, K-25 Site, Oak Ridge, TN. The purpose of the demonstration is to remove organic contaminants present in the soil by heating to a temperature range of 85{degrees} to 95{degrees}C. The soil will be heated in situ by applying 60-Hz AC power to an array of electrodes placed in boreholes drilled through the soil. In this section a brief description of the process is given along with a description of the site and a listing of the contaminants found in the area.

  12. Demonstration testing and evaluation of in situ soil heating. Health and safety plan (Revision 2)

    International Nuclear Information System (INIS)

    Dev, H.

    1994-01-01

    This document is the Health and Safety Plan (HASP) for the demonstration of IITRI's EM Treatment Technology. In this process, soil is heated in situ by means of electrical energy for the removal of hazardous organic contaminants. This process will be demonstrated on a small plot of contaminated soil located in the Pit Area of Classified Burial Ground K-1070-D, K-25 Site, Oak Ridge, TN. The purpose of the demonstration is to remove organic contaminants present in the soil by heating to a temperature range of 85 degrees to 95 degrees C. The soil will be heated in situ by applying 60-Hz AC power to an array of electrodes placed in boreholes drilled through the soil. In this section a brief description of the process is given along with a description of the site and a listing of the contaminants found in the area

  13. Philippines revises power plans

    Energy Technology Data Exchange (ETDEWEB)

    Hayes, D.

    1988-02-01

    Following an unexpected surge in electricity demand the Philippines has revised its medium term power development programme. The sharp increase in electricity consumption follows three years of slack demand due to civil disturbances before the end of the Macros administration and the election of Corazon Aquino as President in 1986. Originally, the Aquino government's medium term power development plans called for about 500MW of generating capacity to be installed between 1986 and 1992. The three proposed plants were scheduled for commissioning in 1991 and 1992. However, a spurt in power demand growth during the past nine months has caused concern among industrialists that power shortages could occur by the end of the decade. So additional capacity will be installed to prevent an anticipated shortfall in electricity supplies by the early 1990s.

  14. Site specific health and safety plan, 100-HR-3 pump and treat. Revision 1

    International Nuclear Information System (INIS)

    Tuttle, B.G.

    1996-06-01

    The 100-HR-3 Operable Unit encompasses groundwater contamination underlying the 100-D and 100-H Areas. The primary contaminate is chromium VI. The sources of chromium contamination resulted from the use of sodium dichromate during past reactor operations. The purpose of the 100-HR-3 Pump-and-Treat system is to pump contaminated groundwater through aboveground ion exchange resin and then return the treated waster to the aquifer. This plan covers operation, maintenance, repairs, and pump removal/installation

  15. Site specific health and safety plan, 100-HR-3 pump and treat. Revision 2

    International Nuclear Information System (INIS)

    St John, C.H.

    1997-09-01

    The 100-HR-3 Pump and Treat system is a groundwater remedial action to remove Hexavalent Chromium (Cr+6) from the groundwater underlying the 100-HR-3 Operable Unit. This plan covers operation, maintenance, repairs, resin exchange and equipment removal/installation. The 100-HR-3 Operable Unit addresses groundwater underlying the 100-D Area. The primary groundwater contaminant is Chromium +6. The chromium contamination resulted from the use of sodium dichromate during past reactor operations. Sodium dichromate was used to treat reactor coolant water during reactor operations. The purpose of this Pump and Treat system is to pump contaminated groundwater through above ground ion exchange resin and then return treated water to aquifer. Chromium levels extracted from the wells are anticipated to range in the low parts per billion (∼50 ppb) which is the drinking water limit for Cr+6

  16. Safety case plan 2008

    International Nuclear Information System (INIS)

    2008-07-01

    Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy) Posiva is preparing to submit the construction license application for a spent fuel repository by the end of the year 2012. The long-term safety section supporting the license application is based on a safety case, which, according to the internationally adopted definition, is a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. In 2005, Posiva presented a plan to prepare such a safety case. The present report provides a revised plan of the safety case contents mentioned above. The update of the safety case plan takes into account the recommendations made by the Radiation and Nuclear Safety Authority (STUK) about improving the focus and further developing the plan. Accordingly, particular attention is given to the quality management of the safety case work, the management of uncertainties and the scenario methodology. The quality management is based on the ISO 9001:2000 standard process thinking enhanced with special features arising from STUK's YVL Guides. The safety case production process is divided into four main sub-processes. The conceptualisation and methodology sub-process defines the framework for the assessment. The critical data handling and modelling sub-process links Posiva's main technical and scientific activities to the production of the safety case. The assessment sub-process analyses the consequences of the evolution of the disposal system in various scenarios, classified either as part of the expected evolution or as disruptive scenarios. The compliance and confidence sub-process is responsible for final evaluation of compliance of the assessment results with the regulatory criteria and the overall confidence in the safety case. As in the previous safety case plan, the safety case will be based on several reports, but

  17. Engineering task plan for the annual revision of the rotary mode core sampling system safety equipment list

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    This Engineering Task Plan addresses an effort to provide an update to the RMCS Systems 3 and 4 SEL and DCM in order to incorporate the changes to the authorization basis implemented by HNF-SD-WM-BIO-001, Rev. 0 (Draft), Addendum 5 , Safety Analysis for Rotary Mode Core Sampling. Responsibilities, task description, cost estimate, and schedule are presented

  18. Preliminary Study on the Revision of Nuclear Safety Policy Statement

    International Nuclear Information System (INIS)

    Lee, Y. E.; Lee, S. H.; Chang, H. S.; Choi, K. S.; Jung, S. J.

    2011-01-01

    Nuclear safety policy in Korea is currently declared in the Nuclear Safety Charter as the highest tier document and safety principles and directions are announced in the Nuclear Safety Policy Statement. As the circumstances affecting on the nuclear safety policy change, it needs to revise the Statement. This study aims to develop the revised Nuclear Safety Policy Statement to declare that securing safety is a prerequisite to the utilization of nuclear energy, and that all workers in nuclear industry and regulatory body must adhere to the principle of priority to safety. As a result, two different types of revision are being prepared as of August. One is based on the spirit of Nuclear Safety Charter as well as the direction of future-oriented safety policies including the changes in the environment after declaration of the Statement. The other is to declare the fundamental safety objective and safety principles as the top philosophy of national nuclear safety policy by adopting the '10 Safety Principles in IAEA Safety Fundamental' instead of the current Charter. Both versions of revision are subject to further in-depth discussion. However once the revision is finalized and declared, it would be useful to accomplish effectively the organizational responsibilities and to enhance the public confidence in nuclear safety by performing the regulatory activities in a planned and systematic manner and promulgating the government's dedication to priority to safety

  19. Revision of Krsko NPP Quality Assurance Plan

    International Nuclear Information System (INIS)

    Biscan, R.; Fifnja, I.; Kavsek, D.

    2012-01-01

    International standards from nuclear power plant operation area are being frequently upgraded and revised in accordance with the continuous improvement philosophy. This philosophy applies also to the area of Quality Assurance, which has also undergone significant improvement since the early 1950s. Besides just nuclear industry, there are also other international quality standards that are being continuously developed and revised, bringing needs for upgrades also in the nuclear application. Since the beginning of Krsko NPP construction, the overall Quality Assurance program and its applicable procedures were in place to assure that all planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements to quality, are in place. The overall requirements for quality as one of the major objectives for Krsko NPP operation are also set forth in the Updated Safety Analyses Report, the document that serves as a base for operating license. During more than 30 years of Krsko NPP operation, the quality requirements and related documents were revised and upgraded in several attempts. The latest revision 6 of QD-1, Quality Assurance Plan was issued during the year 2011. The bases for the revision were: Changes of the Slovenian regulatory requirements (ZVISJV, JV5, JV9?), Changes of Krsko NPP licensing documents (USAR section 13?), SNSA inspection requirements, Changes of international standards (IAEA, ISO?), Conclusions of first PSR, Implementation of ISO standards in Krsko NPP (ISO14001, ISO17025), Changes of plant procedures, etc. One of the most obvious changes was the enlargement of the QA Plan scope to cover interdisciplinary areas defined in the plant management program MD-1, such as Safety culture, Self-assessment, Human performance, Industrial Safety etc. The attachment of the QA Plan defining relationships between certain standards was also updated to provide matrix for better correlation of requirements of

  20. Maine highway safety plan

    Science.gov (United States)

    2010-01-01

    Each September 1, the MeBHS must provide NHTSA a comprehensive plan to reduce : traffic crashes and resulting deaths, injuries and property damage. The Highway Safety : Plan (HSP) serves as Maines application for available federal funds for these ...

  1. Environmental Monitoring Plan, Revision 6

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos, G M; Bertoldo, N A; Blake, R G; Campbell, C G; Grayson, A R; Nelson, J C; Revelli, M A; Rosene, C A; Wegrecki, T; Williams, R A; Wilson, K R; Jones, H E

    2012-03-02

    The purpose of environmental monitoring is to promote the early identification of, and response to, potential adverse environmental impacts associated with Lawrence Livermore National Laboratory (LLNL) operations. Environmental monitoring supports the Integrated Safety Management System (ISMS), International Organization for Standardization (ISO) 14001 Environmental Management Systems standard, and U. S. Department of Energy (DOE) Order 458.1, Radiation Protection of the Public and the Environment. Specifically, environmental monitoring enables LLNL to detect, characterize, and respond to releases from LLNL activities; assess impacts; estimate dispersal patterns in the environment; characterize the pathways of exposure to members of the public; characterize the exposures and doses to individuals and to the population; and to evaluate the potential impacts to the biota in the vicinity of LLNL. Environmental monitoring is also a major component of compliance demonstration for permits and other regulatory requirements. The Environmental Monitoring Plan (EMP) addresses the sample collection and analytical work supporting environmental monitoring to ensure the following: (1) A consistent system for collecting, assessing, and documenting environmental data of known and documented quality; (2) A validated and consistent approach for sampling and analysis of samples to ensure laboratory data meets program-specific needs and requirements within the framework of a performance-based approach for analytical laboratory work; and (3) An integrated sampling approach to avoid duplicative data collection. LLNL prepares the EMP because it provides an organizational framework for ensuring that environmental monitoring work, which is integral to the implementation of LLNL's Environmental Management System, is conducted appropriately. Furthermore, the Environmental Monitoring Plan helps LLNL ensure compliance with DOE Order 231.1 Change 2, Environment, Safety and Health Reporting

  2. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    International Nuclear Information System (INIS)

    Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J.

    2000-10-01

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process

  3. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    Energy Technology Data Exchange (ETDEWEB)

    Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J

    2000-10-01

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process.

  4. Environmental Monitoring Plan, Revision 5

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos, G M; Blake, R G; Bertoldo, N A; Campbell, C G; Coty, J; Folks, K; Grayson, A R; Jones, H E; Nelson, J C; Revelli, M A; Wegrecki, T; Williams, R A; Wilson, K

    2010-01-27

    The purpose of environmental monitoring is to promote the early identification of, and response to, potential adverse environmental impacts associated with Lawrence Livermore National Laboratory (LLNL) operations. Environmental monitoring supports the Integrated Safety Management System (ISMS), International Organization for Standardization (ISO) 14001 Environmental Management Systems standard, and U. S. Department of Energy (DOE) Order 450.1A, Environmental Protection Program. Specifically, in conformance with DOE Order 450.1A, Attachment 1, paragraph 1(b)(5), environmental monitoring enables LLNL to detect, characterize, and respond to releases from LLNL activities; assess impacts; estimate dispersal patterns in the environment; characterize the pathways of exposure to members of the public; characterize the exposures and doses to individuals and to the population; and to evaluate the potential impacts to the biota in the vicinity of LLNL. Environmental monitoring also serves to demonstrate compliance with permits and other regulatory requirements. The Environmental Monitoring Plan (EMP) addresses the sample collection and analytical work supporting environmental monitoring to ensure the following: (1) A consistent system for collecting, assessing, and documenting environmental data of known and documented quality. (2) A validated and consistent approach for sampling and analysis of samples to ensure laboratory data meets program-specific needs and requirements within the framework of a performance-based approach for analytical laboratory work. (3) An integrated sampling approach to avoid duplicative data collection. Until its cancellation in January 2003, DOE Order 5400.1 required the preparation of an environmental monitoring plan. Neither DOE Order 450.1A nor the ISO 14001 standard are as prescriptive as DOE Order 5400.1, in that neither expressly requires an EMP. However, LLNL continues to prepare the EMP because it provides an organizational framework for

  5. Revised Safety Instruction 41 (IS41 REV.)

    CERN Multimedia

    SC Secretariat

    2005-01-01

    Please note that the Revised Safety Instruction No. 41 (IS41 REV.), entitled 'The use of plastic and other non-metallic materials at CERN with respect to fire safety and radiation resistance' is available on the web at the following url: https://edms.cern.ch/document/335806/LAST_RELEASED Paper copies can also be obtained from the SC Unit Secretariat, e-mail: sc.secretariat@cern.ch SC Secretariat

  6. Nuclear safety guide. TID-7016, Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-01-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

  7. Nuclear safety guide. TID-7016, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, J T [ed.

    1978-05-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information.

  8. Fusion safety program plan

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.; Herring, J.S.

    1980-09-01

    The program plan consists of research that has been divided into 13 different areas. These areas focus on the radioactive inventories that are expected in fusion reactors, the energy sources potentially available to release a portion of these inventories, and analysis and design techniques to assess and ensure that the safety risks associated with operation of magnetic fusion facilities are acceptably low. The document presents both long-term program requirements that must be fulfilled as part of the commercialization of fusion power and a five-year plan for each of the 13 different program areas. Also presented is a general discussion of magnetic fusion reactor safety, a method for establishing priorities in the program, and specific priority ratings for each task in the five-year plan

  9. Plan-Belief Revision in Jason

    DEFF Research Database (Denmark)

    Jensen, Andreas Schmidt; Villadsen, Jørgen

    2015-01-01

    When information is shared between agents of unknown reliability, it is possible that their belief bases become inconsistent. In such cases, the belief base must be revised to restore consistency, so that the agent is able to reason. In some cases the inconsistent information may be due to use of...... of incorrect plans. We extend work by Alechina et al. to revise belief bases in which plans can be dynamically added and removed. We present an implementation of the algorithm in the AgentSpeak implementation Jason....

  10. Nuclear safety guide: TID--7016, Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-01-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. Revision 2 of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams experienced in the field. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors

  11. DWPF waste form compliance plan (Draft Revision)

    International Nuclear Information System (INIS)

    Plodinec, M.J.; Marra, S.L.

    1991-01-01

    The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan

  12. Environmental, Safety, and Health Plan for the remedial investigation/feasibility study at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Revision 1, Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Davis, C. M.; El-Messidi, O. E.; Cowser, D. K.; Kannard, J. R.; Carvin, R. T.; Will, III, A. S.; Clark, Jr., C.; Garland, S. B.

    1993-05-01

    This Environmental, Safety, and Health (ES&H) Plan presents the concepts and methodologies to be followed during the remedial investigation/feasibility study (RI/FS) for Oak Ridge National Laboratory (ORNL) to protect the health and safety of employees, the public, and the environment. This ES&H Plan acts as a management extension for ORNL and Martin Marietta Energy Systems, Inc. (Energy Systems) to direct and control implementation of the project ES&H program. The subsections that follow describe the program philosophy, requirements, quality assurance measures, and methods for applying the ES&H program to individual waste area grouping (WAG) remedial investigations. Hazardous work permits (HWPs) will be used to provide task-specific health and safety requirements.

  13. Nuclear safety guide TID-7016 Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1980-01-01

    The present revision of TID-7016 Nuclear Safety Guide is discussed. This Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available, information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

  14. Operations program plan: Revision 3

    International Nuclear Information System (INIS)

    1988-07-01

    This document, the Operations Program Plan (OPP), has been developed as the seven-year master plan for operation of WIPP. The OPP was authorized by the Albuquerque Field Office of the Department of Energy (DOE-AL) and that organization's WIPP Project Office (DOE-WPO) in Carlsbad, New Mexico. The OPP is the directive from the DOE-WPO Project Manager as to how the WIPP is to be managed, operated, and administered. As the top tier management document for WIPP, the OPP establishes organizational responsibilities and an organizational structure for the Waste Isolation Division (WID) of Westinghouse Electric Corporation. The OPP sets policy and tone for conducting WIPP operations; it requires and specifically authorizes implementing documents (e.g., manuals). It has also proven instrumental in the budgeting and planning process, most particularly in expediting the preparation of specific budgets and detailed schedules for each of the numerous work packages. The OPP is also used to communicate information about WIPP operations

  15. Nuclear Regulatory Commission Human Factors Program Plan. Revision 2

    International Nuclear Information System (INIS)

    1986-04-01

    This document is the Second Annual Revision to the NRC Human Factors Program Plan. The first edition was published in August 1983. Revision 1 was published in July of 1984. Purpose of the NRC Human Factors Program is to ensure that proper consideration is given to human factors in the design and operation of nuclear power plants. This document describes the plans of the Office of Nuclear Reactor Regulation to address high priority human factors concerns of importance to reactor safety in FY 1986 and FY 1987. Revision 2 of the plan incorporates recent Commission decisions and policies bearing on the human factors aspects of reactor safety regulation. With a few exceptions, the principal changes from prior editions reflect a shift from developing new requirements to staff evaluation of industry progress in resolving human factors issues. The plan addresses seven major program elements: (1) Training, (2) Licensing Examinations, (3) Procedures, (4) Man-Machine Interface, (5) Staffing and Qualifications, (6) Management and Organization, and (7) Human Performance

  16. DWPF Development Plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Holtzscheiter, E.W.

    1994-05-09

    The DWPF Development Plan is based on an evaluation process flowsheet and related waste management systems. The scope is shown in Figure 1 entitled ``DWPF Process Development Systems.`` To identify the critical development efforts, each system has been analyzed to determine: The identification of unresolved technology issues. A technology issue (TI) is one that requires basic development to resolve a previously unknown process or equipment problem and is managed via the Technology Assurance Program co-chaired by DWPF and SRTC. Areas that require further work to sufficiently define the process basis or technical operating envelop for DWPF. This activity involves the application of sound engineering and development principles to define the scope of work required to complete the technical data. The identification of the level of effort and expertise required to provide process technical consultation during the start-up and demonstration of this first of a kind plant.

  17. DWPF Development Plan. Revision 1

    International Nuclear Information System (INIS)

    Holtzscheiter, E.W.

    1994-01-01

    The DWPF Development Plan is based on an evaluation process flowsheet and related waste management systems. The scope is shown in Figure 1 entitled ''DWPF Process Development Systems.'' To identify the critical development efforts, each system has been analyzed to determine: The identification of unresolved technology issues. A technology issue (TI) is one that requires basic development to resolve a previously unknown process or equipment problem and is managed via the Technology Assurance Program co-chaired by DWPF and SRTC. Areas that require further work to sufficiently define the process basis or technical operating envelop for DWPF. This activity involves the application of sound engineering and development principles to define the scope of work required to complete the technical data. The identification of the level of effort and expertise required to provide process technical consultation during the start-up and demonstration of this first of a kind plant

  18. 76 FR 32321 - Approval and Promulgation of Air Quality Implementation Plans; Pennsylvania; Revision to the...

    Science.gov (United States)

    2011-06-06

    ...) Program--Quality Assurance Protocol for the Safety Inspection Program in Non-I/M Counties AGENCY... approve revisions to the Pennsylvania State Implementation Plan (SIP). The revision consists of a change... prior SIP-approved I/M program to change the duration of the timing of quality assurance audits...

  19. Revised Severe Accident Research Program plan, FY 1990--1992

    International Nuclear Information System (INIS)

    1989-08-01

    For the past 10 years, since the Three Mile Island accident, the NRC has sponsored an active research program on light-water-reactor severe accidents as part of a multi-faceted approach to reactor safety. This report describes the revised Severe Accident Research Program (SARP) and how the revisions are designed to provide confirmatory information and technical support to the NRC staff in implementing the staff's Integration Plan for Closure of Severe Accident Issues as described in SECY-88-147. The revised SARP addresses both the near-term research directed at providing a technical basis upon which decisions on important containment performance issues can be made and the long-term research needed to confirm and refine our understanding of severe accidents. In developing this plan, the staff recognized that the overall goal is to reduce the uncertainties in the source term sufficiently to enable the staff to make regulatory decisions on severe accident issues. However, the staff also recognized that for some issues it may not be practical to attempt to further reduce uncertainties, and some regulatory decisions or conclusions will have to be made with full awareness of existing uncertainties. 2 figs., 1 tab

  20. US Nuclear Regulatory Commission Human Factors Program Plan. Revision 1

    International Nuclear Information System (INIS)

    1984-09-01

    The purpose of the NRC Human Factors Program Plan (NUREG-0985) is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This revised plan addresses nuclear power plants (NPPs) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, THE NRC Action Plan developed as a result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention; (3) conduct of developmental activities specified in NUREG-0985 during FY-83; and (4) the impact of Section 306 of the Nuclear Waste Policy Act of 1982, PL 97-425. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-84 through FY-86 time frame

  1. Waste Management Program management plan. Revision 1

    International Nuclear Information System (INIS)

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL

  2. Waste Management Program management plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management`s objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL.

  3. Seismic safety research program plan

    International Nuclear Information System (INIS)

    1985-06-01

    This plan describes the safety issues, regulatory needs, and the research necessary to address these needs. The plan also discusses the relationship between current and proposed research within the NRC and research sponsored by other government agencies, universities, industry groups, professional societies, and foreign sources

  4. Planning for Campus Safety

    Science.gov (United States)

    Dessoff, Alan

    2009-01-01

    From natural disasters to criminal violence, facilities officers are often called on to address campus safety and security issues beyond their usual responsibilities. Their experiences in coping with unanticipated events have produced a catalogue of lessons learned that can help them and their peers at other institutions who might face the same…

  5. Revised health and safety compliance model for the Ghanaian ...

    African Journals Online (AJOL)

    The construction industry in Ghana is faced with employees' negligence in obeying rules and regulations, and acts that conflict with health and safety. The purpose of the paper was to present the revised health and safety (H&S) compliance model for the construction industry based on a developed theoretical six factor ...

  6. Chemical Hygiene and Safety Plan

    Energy Technology Data Exchange (ETDEWEB)

    Berkner, K.

    1992-08-01

    The objective of this Chemical Hygiene and Safety Plan (CHSP) is to provide specific guidance to all LBL employees and contractors who use hazardous chemicals. This Plan, when implemented, fulfills the requirements of both the Federal OSHA Laboratory Standard (29 CFR 1910.1450) for laboratory workers, and the Federal OSHA Hazard Communication Standard (29 CFR 1910.1200) for non-laboratory operations (e.g., shops). It sets forth safety procedures and describes how LBL employees are informed about the potential chemical hazards in their work areas so they can avoid harmful exposures and safeguard their health. Generally, communication of this Plan will occur through training and the Plan will serve as a the framework and reference guide for that training.

  7. Safety research basic plan of JNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Japan Nuclear Cycle Development Institute (JNC) formally succeeded to Power Reactor and Nuclear Fuel Development Corporation (PNC) on October, 1 1998. This report describes the basic plan for major program of JNC which consists of two parts: management philosophy of the new institute and the latest revised medium term program. In the first part, the primary mission of JNC is to perform its R and D concentrating on fast breeder reactor and its fuel cycle, and treatment and disposal of high-level radioactive wastes, while at the same time giving special consideration to safety. In the second, individual programs in the new basic plan are discussed in detail. The outline and schedule of each program are also attached in the table form. (H. Itami)

  8. Carlsbad Area Office strategic plan, March 1995. Revision 1

    International Nuclear Information System (INIS)

    1995-03-01

    This edition of the Carlsbad Area Office Strategic Plan captures the US Department of Energy's (DOE's) new focus, and supersedes the edition issued previously (DOE, 1993a). This revision reflects: a revised strategy designed to demonstrate compliance with environmental regulations earlier than the previous course of action; and a focus on establishment of standardized transuranic waste characterization and acceptance criteria for disposal facilities

  9. 76 FR 32333 - Approval and Promulgation of Air Quality Implementation Plans; Pennsylvania; Revision to the...

    Science.gov (United States)

    2011-06-06

    ...) Program--Quality Assurance Protocol for the Safety Inspection Program in Non-I/M Counties AGENCY... Implementation Plan (SIP) revision submitted by the Commonwealth of Pennsylvania for the purpose of changing the...). Specifically, the Commonwealth is amending a provision of its prior SIP-approved I/M program to amend the...

  10. 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

  11. 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.

  12. Nuclear safety research master plan

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

    2001-06-01

    The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

  13. 75 FR 6413 - Office of New Reactors; Proposed Revision to Standard Review Plan, Section 14.3.12 on Physical...

    Science.gov (United States)

    2010-02-09

    ... Standard Review Plan, Section 14.3.12 on Physical Security Hardware Inspections, Tests, Analyses, and.... SUMMARY: The NRC is soliciting public comment on NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' on a proposed Revision 1 to Standard Review Plan (SRP...

  14. Safety Education in Driving. 2nd Revision.

    Science.gov (United States)

    Ohio State Univ., Columbus. Vocational Instructional Materials Lab.

    Intended for driving instruction students, this publication contains instructional materials for safety education. It contains six sections on facts and figures; defensive driving; safety devices; restraints; emergency situations; and other highway users. Each section consists of reading material followed by an activity or activities. A total of…

  15. Tank safety screening data quality objective. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, J.W.

    1995-04-27

    The Tank Safety Screening Data Quality Objective (DQO) will be used to classify 149 single shell tanks and 28 double shell tanks containing high-level radioactive waste into safety categories for safety issues dealing with the presence of ferrocyanide, organics, flammable gases, and criticality. Decision rules used to classify a tank as ``safe`` or ``not safe`` are presented. Primary and secondary decision variables used for safety status classification are discussed. The number and type of samples required are presented. A tabular identification of each analyte to be measured to support the safety classification, the analytical method to be used, the type of sample, the decision threshold for each analyte that would, if violated, place the tank on the safety issue watch list, and the assumed (desired) analytical uncertainty are provided. This is a living document that should be evaluated for updates on a semiannual basis. Evaluation areas consist of: identification of tanks that have been added or deleted from the specific safety issue watch lists, changes in primary and secondary decision variables, changes in decision rules used for the safety status classification, and changes in analytical requirements. This document directly supports all safety issue specific DQOs and additional characterization DQO efforts associated with pretreatment and retrieval. Additionally, information obtained during implementation can assist in resolving assumptions for revised safety strategies, and in addition, obtaining information which will support the determination of error tolerances, confidence levels, and optimization schemes for later revised safety strategy documentation.

  16. Active sites environmental monitoring Program - Program Plan: Revision 2

    International Nuclear Information System (INIS)

    Morrissey, C.M.; Hicks, D.S.; Ashwood, T.L.; Cunningham, G.R.

    1994-05-01

    The Active Sites Environmental Monitoring Program (ASEMP), initiated in 1989, provides early detection and performance monitoring of active low-level-waste (LLW) and transuranic (TRU) waste facilities at Oak Ridge National Laboratory (ORNL). Several changes have recently occurred in regard to the sites that are currently used for waste storage and disposal. These changes require a second set of revisions to the ASEMP program plan. This document incorporates those revisions. This program plan presents the organization and procedures for monitoring the active sites. The program plan also provides internal reporting levels to guide the evaluation of monitoring results

  17. 42 CFR 456.523 - Revised UR plan.

    Science.gov (United States)

    2010-10-01

    ... control over the utilization of services; and (2) Conducts reviews in a way that improves the quality of...) MEDICAL ASSISTANCE PROGRAMS UTILIZATION CONTROL Utilization Review Plans: FFP, Waivers, and Variances for Hospitals and Mental Hospitals Ur Plan: Remote Facility Variances from Time Requirements § 456.523 Revised...

  18. 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…

  19. Perspectives on reactor safety. Revision 1

    International Nuclear Information System (INIS)

    Haskin, F.E.; Hodge, S.A.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  20. Perspectives on reactor safety. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  1. 78 FR 18936 - Revision to the California State Implementation Plan, South Coast Air Quality Management Plan

    Science.gov (United States)

    2013-03-28

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0920; FRL-9779-1] Revision to the California State Implementation Plan, South Coast Air Quality Management Plan AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: EPA is proposing to approve a revision to the South...

  2. Human Factors and Safety Culture in Maritime Safety (revised

    Directory of Open Access Journals (Sweden)

    Heinz Peter Berg

    2013-09-01

    Full Text Available As in every industry at risk, the human and organizational factors constitute the main stakes for maritime safety. Furthermore, several events at sea have been used to develop appropriate risk models. The investigation on maritime accidents is, nowadays, a very important tool to identify the problems related to human factor and can support accident prevention and the improvement of maritime safety. Part of this investigation should in future also be near misses. Operation of ships is full of regulations, instructions and guidelines also addressing human factors and safety culture to enhance safety. However, even though the roots of a safety culture have been established, there are still serious barriers to the breakthrough of the safety management. One of the most common deficiencies in the case of maritime transport is the respective monitoring and documentation usually lacking of adequacy and excellence. Nonetheless, the maritime area can be exemplified from other industries where activities are ongoing to foster and enhance safety culture.

  3. Radiation protection planning and management during revision

    International Nuclear Information System (INIS)

    Gewehr, K.

    1984-01-01

    During the operation of nuclear power plants it is normally possible for the in-house personnel to take care of arising radiation protection problems. However, in the comparatively short revision phases, the duties of radiation protection become much more varied. Additional trained radiation protection crews are needed at short notice. This is also the time in which the largest contributions are made to the annual cumulated doses of the personnel. Recent guidelines and rules trying to reduce the radiation exposure of personnel concentrate on this very point. The article outlines the radiation protection activities performed by the service personnel in the course of a steam generator check. (orig.) [de

  4. Civilian radioactive waste management program plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy`s site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program`s ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program`s mission and vision, and summarizes the Program`s broad strategic objectives. Chapter 2 describes the Program`s approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program`s organization chart; the Commission`s regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms.

  5. Civilian radioactive waste management program plan. Revision 2

    International Nuclear Information System (INIS)

    1998-07-01

    This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy's site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program's ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program's mission and vision, and summarizes the Program's broad strategic objectives. Chapter 2 describes the Program's approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program's organization chart; the Commission's regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms

  6. DOE explosives safety manual. Revision 7

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    This manual prescribes the Department of Energy (DOE) safety rules used to implement the DOE safety policy for operations involving explosives. This manual is applicable to all DOE facilities engaged in operations of development, manufacturing, handling, storage, transportation, processing, or testing of explosives, pyrotechnics and propellants, or assemblies containing these materials. The standards of this manual deal with the operations involving explosives, pyrotechnics and propellants, and the safe management of such operations. The design of all new explosives facilities shall conform to the requirements established in this manual and implemented in DOE 6430.1A, ``General Design Criteria Manual.`` It is not intended that existing physical facilities be changed arbitrarily to comply with these provisions, except as required by law. Existing facilities that do not comply with these standards may continue to be used for the balance of their functional life, as long as the current operation presents no significantly greater risk than that assumed when the facility was originally designed and it can be demonstrated clearly that a modification to bring the facility into compliance is not feasible. However, in the case of a major renovation, the facility must be brought into compliance with current standards. The standards are presented as either mandatory or advisory. Mandatory standards, denoted by the words ``shall,`` ``must,`` or ``will,`` are requirements that must be followed unless written authority for deviation is granted as an exemption by the DOE. Advisory standards denoted by ``should`` or ``may`` are standards that may be deviated from with a waiver granted by facility management.

  7. SSC San Diego Strategic Plan. Revision 2

    National Research Council Canada - National Science Library

    2000-01-01

    .... As an organization, we believe that strategic planning provides a critically needed context for adopting dynamic, agile processes to better use our corporate resources and meet our customers' needs...

  8. 100-D Ponds closure plan. Revision 1

    International Nuclear Information System (INIS)

    Petersen, S.W.

    1997-09-01

    The 100-D Ponds is a Treatment, Storage, and Disposal (TSD) unit on the Hanford Facility that received both dangerous and nonregulated waste. This Closure Plan (Rev. 1) for the 100-D Ponds TSD unit consists of a RCRA Part A Dangerous Waste Permit Application (Rev. 3), a RCRA Closure Plan, and supporting information contained in the appendices to the plan. The closure plan consists of eight chapters containing facility description, process information, waste characteristics, and groundwater monitoring data. There are also chapters containing the closure strategy and performance standards. The strategy for the closure of the 100-D Ponds TSD unit is clean closure. Appendices A and B of the closure plan demonstrate that soil and groundwater beneath 100-D Ponds are below cleanup limits. All dangerous wastes or dangerous waste constituents or residues associated with the operation of the ponds have been removed, therefore, human health and the environment are protected. Discharges to the 100-D Ponds, which are located in the 100-DR-1 operable unit, were discontinued in June 1994. Contaminated sediment was removed from the ponds in August 1996. Subsequent sampling and analysis demonstrated that there is no contamination remaining in the ponds, therefore, this closure plan is a demonstration of clean closure

  9. WASTE CERTIFICATION PROGRAM PLAN - REVISION 7

    International Nuclear Information System (INIS)

    MORGAN, LK

    2002-01-01

    The primary changes that have been made to this revision reflect the relocation of the Waste Certification Official (WCO) organizationally from the Quality Services Division (QSD) into the Laboratory Waste Services (LWS) Organization. Additionally, the responsibilities for program oversight have been differentiated between the QSD and LWS. The intent of this effort is to ensure that those oversight functions, which properly belonged to the WCO, moved with that function; but retain an independent oversight function outside of the LWS Organization ensuring the potential for introduction of organizational bias, regarding programmatic and technical issues, is minimized. The Waste Certification Program (WCP) itself has been modified to allow the waste certification function to be performed by any of the personnel within the LWS Waste Acceptance/Certification functional area. However, a single individual may not perform both the technical waste acceptance review and the final certification review on the same 2109 data package. Those reviews must be performed by separate individuals in a peer review process. There will continue to be a designated WCO who will have lead programmatic responsibility for the WCP and will exercise overall program operational oversite as well as determine the overall requirements of the certification program. The quality assurance organization will perform independent, outside oversight to ensure that any organizational bias does not degrade the integrity of the waste certification process. The core elements of the previous WCP have been retained, however, the terms and process structure have been modified.. There are now two ''control points,'' (1) the data package enters the waste certification process with the signature of the Generator Interface/Generator Interface Equivalent (GI/GIE), (2) the package is ''certified'', thus exiting the process. The WCP contains three steps, (1) the technical review for waste acceptance, (2) a review of the

  10. 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

  11. 78 FR 61251 - The National Public Transportation Safety Plan, the Public Transportation Agency Safety Plan, and...

    Science.gov (United States)

    2013-10-03

    ...-0030] RIN 2132-AB20; 2132-AB07 The National Public Transportation Safety Plan, the Public Transportation Agency Safety Plan, and the Public Transportation Safety Certification Training Program; Transit... Public Transportation Safety Program (National Safety Program) and the requirements of the new transit...

  12. 76 FR 13511 - Approval and Promulgation of Air Quality Implementation Plans; Virginia; Revisions to the Open...

    Science.gov (United States)

    2011-03-14

    ... Promulgation of Air Quality Implementation Plans; Virginia; Revisions to the Open Burning Regulations AGENCY... approve revisions to the Virginia State Implementation Plan (SIP). The revisions recodify the open burning... approving these revisions to Virginia's open burning regulations in accordance with the requirements of the...

  13. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

  14. Revision of the Euratom basic safety standards directive-current status

    International Nuclear Information System (INIS)

    Mundig, S.

    2011-01-01

    The European Commission is currently developing a revised Euratom Basic Safety Standards (BSS) Directive covering two major objectives: the consolidation of existing Euratom Radiation Protection legislation and the revision of the Euratom BSS. The consolidation will merge the following five Directives into one single Directive: the BSS Directive, the Medical Exposures Directive, the Public Information Directive, the Outside Workers Directive and the Directive on the Control of high-activity sealed radioactive sources and orphan sources. The revision of the Euratom BSS will take account of the latest recommendations by the International Commission on Radiological Protection and shall improve clarity of the requirements where appropriate. It is planned to introduce more binding requirements on natural radiation sources, on criteria for exemption and clearance, and on the cooperation between Member States for emergency planning and response. The provisions for regulatory control of planned exposure situations foresee a graded approach commensurate to the magnitude and likelihood of exposures from a practice. Finally, the new BSS shall take account of recent scientific developments. One additional goal is to achieve greater harmonisation between the Euratom BSS and the international BSS. While the requirements on the protection of workers, apprentices and students remain nearly unchanged, the revised BSS will clarify the roles and responsibilities of services and experts involved in technical and practical aspects of radiation protection, such as the occupational health services, the dosimetry services, the radiation protection expert and the medical physics expert. The requirements in the BSS on individual monitoring of category A workers remain unchanged, but the existing guidance on individual monitoring was revised and updated-the technical recommendations for monitoring individuals occupationally exposed to external radiation are published by the European

  15. Operating and Assurance Program Plan. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The LBL Operating and Assurance Program (OAP) is a management system and a set of requirements designed to maintain the level of performance necessary to achieve LBL`s programmatic and administrative objectives effectively and safely through the application of quality assurance and related conduct of operations and maintenance management principles. Implement an LBL management philosophy that supports and encourages continual improvement in performance and quality at the Laboratory. Provide an integrated approach to compliance with applicable regulatory requirements and DOE orders. The OAP is intended to meet the requirements of DOE Order 5700.6C, Quality Assurance. The Program also contains management system elements of DOE Orders 5480.19, Conduct of Operations Requirements for DOE Facilities; 5480.25, Safety of Accelerator Facilities; and 4330.4A, Maintenance Management Program, and is meant to integrate these elements into the overall LBL approach to Laboratory management. The requirements of this program apply to LBL employees and organizations, and to contractors and facility users as managed by their LBL sponsors. They are also applicable to external vendors and suppliers as specified in procurement documents and contracts.

  16. Technical Assistance Contractor management plan. Revision 1

    International Nuclear Information System (INIS)

    1995-08-01

    The Technical Assistance Contractor (TAC) for the Uranium Mill Tailings Remedial Action (UMTRA) Project comprises Jacobs Engineering Group Inc. (JEG) as the prime contractor and three teaming partner subcontractors: Roy F. Weston, Inc. (RFW), AGRA Earth and Environmental, Inc. (AGRA), and Geraghty and Miller, Inc. (G and M). The TAC contract's scope is to provide technical, analytical, environmental, engineering, design, inspection, and management support services to the US Department of Energy (DOE) for both Surface and Ground Water Projects. The TAC team supports the DOE in completing surface remedial action and initiating ground water remediation work for start-up, characterization, compliance planning, design, construction oversight, and remedial operations. The TAC provides the DOE UMTRA Project Team with a dedicated management, scientific, and technical resource base in Albuquerque, New Mexico, which is supplemented by corporate resources. A carefully developed and maintained staff of technical experts is available to assess, analyze, develop, and execute cost-effective solutions to the demanding technical and institutional problems presented by the UMTRA Project

  17. Technical Assistance Contractor management plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    The Technical Assistance Contractor (TAC) for the Uranium Mill Tailings Remedial Action (UMTRA) Project comprises Jacobs Engineering Group Inc. (JEG) as the prime contractor and three teaming partner subcontractors: Roy F. Weston, Inc. (RFW), AGRA Earth and Environmental, Inc. (AGRA), and Geraghty and Miller, Inc. (G and M). The TAC contract`s scope is to provide technical, analytical, environmental, engineering, design, inspection, and management support services to the US Department of Energy (DOE) for both Surface and Ground Water Projects. The TAC team supports the DOE in completing surface remedial action and initiating ground water remediation work for start-up, characterization, compliance planning, design, construction oversight, and remedial operations. The TAC provides the DOE UMTRA Project Team with a dedicated management, scientific, and technical resource base in Albuquerque, New Mexico, which is supplemented by corporate resources. A carefully developed and maintained staff of technical experts is available to assess, analyze, develop, and execute cost-effective solutions to the demanding technical and institutional problems presented by the UMTRA Project.

  18. 78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

    Science.gov (United States)

    2013-06-10

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

  19. 9 CFR 108.6 - Revision of plot plans, blueprints, and legends.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Revision of plot plans, blueprints... FACILITY REQUIREMENTS FOR LICENSED ESTABLISHMENTS § 108.6 Revision of plot plans, blueprints, and legends... changes affecting the workflow are to be made. The licensee shall: (a) Prepare revised plot plans...

  20. Planning integration FY 1996 program plan. Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    This Multi-Year Program Plan (MAP) Planning Integration Program, Work Breakdown Structure (WBS) Element 1.8.2, is the primary management tool to document the technical, schedule, and cost baseline for work directed by the US Department of Energy (DOE), Richland Operations Office (RL). As an approved document, it establishes an agreement between RL and the performing contractors for the work to be performed. It was prepared by Westinghouse Hanford Company (WHC) and Pacific Northwest Laboratory (PNL). The MYPPs for the Hanford Site programs are to provide a picture from fiscal year (FY) 1996 through FY 2002. At RL Planning and Integration Division (PID) direction, only the FY 1996 Planning Integration Program work scope has been planned and presented in this MAP. Only those known significant activities which occur after FY 1996 are portrayed in this MAP. This is due to the uncertainty of who will be accomplishing what work scope when, following the award of the Management and Integration (M ampersand I) contract

  1. Planned activities to improve safety

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 6 of the document contains some details about the planed activities to safety improvements

  2. ERD UMTRA Project quality assurance program plan, Revision 7

    International Nuclear Information System (INIS)

    1995-09-01

    This document is the revised Quality Assurance Program Plan (QAPP) dated September, 1995 for the Environmental Restoration Division (ERD) Uranium Mill Tailings Remedial Action Project (UMTRA). Quality Assurance requirements for the ERD UMTRA Project are based on the criteria outlined in DOE Order 5700.6C or applicable sections of 10 CFR 830.120. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the ERD UMTRA Project and its contractors

  3. EM Health and Safety Plan Guidelines

    Energy Technology Data Exchange (ETDEWEB)

    1994-12-01

    This document contains information about the Health and Safety Plan Guidelines. Topics discussed include: Regulatory framework; key personnel; hazard assessment; training requirements; personal protective equipment; extreme temperature disorders or conditions; medical surveillance; exposure monitoring/air sampling; site control; decontamination; emergency response/contingency plan; emergency action plan; confined space entry; and spill containment.

  4. Education and training requirements in the revised European Basic Safety Standards Directive

    International Nuclear Information System (INIS)

    Mundigl, S.

    2009-01-01

    The European Commission is currently developing a modified European Basic Safety Standards Directive covering two major objectives: the consolidation of existing European Radiation Protection legislation, and the revision of the European Basic Safety Standards. The consolidation will merge the following five Directives into one single Directive: the Basic Safety Standards Directive, the Medical Exposures Directive, the Public Information Directive, the Outside Workers Directive, and the Directive on the Control of high-activity sealed radioactive sources and orphan sources. The revision of the European Basic Safety Standards will take account of the latest recommendations by the International Commission on Radiological Protection (ICRP) and shall improve clarity of the requirements where appropriate. It is planned to introduce more binding requirements on natural radiation sources, on criteria for clearance, and on the cooperation between Member States for emergency planning and response, as well as a graded approach for regulatory control. One additional goal is to achieve greater harmonisation between the European BSS and the international BSS. Following a recommendation from the Article 31 Group of Experts, the current draft of the modified BSS will highlight the importance of education and training by dedicating a specific title to radiation protection education, training and information. This title will include a general requirement on the Member States to ensure the establishment of an adequate legislative and administrative framework for providing appropriate radiation protection education, training and information. In addition, there will be specific requirements on training in the medical field, on information and training of workers in general, of workers potentially exposed to orphan sources, and to emergency workers. The revised BSS directive will include requirements on the competence of a radiation protection expert (RPE) and of a radiation protection

  5. NPP Krsko Periodic Safety Review action plan

    International Nuclear Information System (INIS)

    Bilic Zabric, T.

    2006-01-01

    In the current, internationally accepted, safety philosophy Periodic Safety Reviews (PSRs) are comprehensive reviews aimed at the verification that an operating NPP remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain an acceptable level of safety. These reviews are complementary to the routine and special safety reviews. They are long time-scale reviews intended to deal with the cumulative effects of plant ageing, modifications, operating experience and technical developments, which are not so easily comprehended over the shorter time-scale routine of safety reviews. The review was completed in 2005 and the next period will see the implementation of the action plan including some plant upgrades. The action plan lists issues that should be implemented at NPP Krsko together with associated milestones. The milestones were assumed based on best estimate resource availability and their ends can be potentially floated. In some cases, multiple corrective measures may be postulated to provide resolution for a given safety issue. The Slovenian Nuclear Safety Administration by decree approved the first periodic safety review and the implementation plan of activities arising from it. The entire implementation plan must be carried out by 15 October 2010. Report on the second periodic safety review must be submitted by the NEK not later than 15 December 2013. (author)

  6. 77 FR 24148 - Revision to the Hawaii State Implementation Plan, Minor New Source Review Program

    Science.gov (United States)

    2012-04-23

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0213; FRL-9661-6] Revision to the Hawaii State Implementation Plan, Minor New Source Review Program AGENCY: Environmental Protection Agency... final action to approve revisions to the Hawaii State Implementation Plan (SIP). These revisions would...

  7. 76 FR 13569 - Approval and Promulgation of Air Quality Implementation Plans; Virginia; Revisions to the Open...

    Science.gov (United States)

    2011-03-14

    ... Promulgation of Air Quality Implementation Plans; Virginia; Revisions to the Open Burning Regulations AGENCY... Implementation Plan (SIP) revision submitted by the Commonwealth of Virginia. The revisions recodify the open... . C. Mail: EPA-R03-OAR-2010-0902, Harold A. Frankford, Air Protection Division, Mailcode 3AP00, U.S...

  8. 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

  9. 77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  10. 77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-09-21

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  11. Cesium legacy safety project management work plan

    International Nuclear Information System (INIS)

    Durham, J.S.

    1998-01-01

    This Management Work Plan (MWP) describes the process flow, quality assurance controls, and the Environment, Safety, and Health requirements of the Cesium Legacy Safety Project. This MWP provides an overview of the project goals and methods for repackaging the non-conforming Type W overpacks and packaging the CsCl powder and pellets. This MWP is not intended to apply to other activities associated with the CsCl Legacy Safety Program (i.e., clean out of South Cell)

  12. 29 CFR 1915.502 - Fire safety plan.

    Science.gov (United States)

    2010-07-01

    ... implement a written fire safety plan that covers all the actions that employers and employees must take to ensure employee safety in the event of a fire. (See Appendix A to this subpart for a Model Fire Safety... safety plan for their employees, and this plan must comply with the host employer's fire safety plan. ...

  13. 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

  14. Seismic safety research program plan

    International Nuclear Information System (INIS)

    1987-05-01

    This document presents a plan for seismic research to be performed by the Structural and Seismic Engineering Branch in the Office of Nuclear Regulatory Research. The plan describes the regulatory needs and related research necessary to address the following issues: uncertainties in seismic hazard, earthquakes larger than the design basis, seismic vulnerabilities, shifts in building frequency, piping design, and the adequacy of current criteria and methods. In addition to presenting current and proposed research within the NRC, the plan discusses research sponsored by other domestic and foreign sources

  15. NRC drug-free workplace plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ``NRC Drug-Free Workplace Plan,`` supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance.

  16. NRC drug-free workplace plan. Revision 1

    International Nuclear Information System (INIS)

    1997-11-01

    On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ''NRC Drug-Free Workplace Plan,'' supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance

  17. Revision of construction plan for advanced thermal demonstration reactor

    International Nuclear Information System (INIS)

    1996-01-01

    The Federation of Electric Power Companies demanded the revision of the construction plan for the advanced thermal demonstration reactor, which is included in the 'Long term plan on the research, development and utilization of atomic energy' decided by the Atomic Energy Commission in 1994, for economical reason. The Atomic Energy Commission carried out the deliberation on this demand. It was found that the cost of construction increases to 580 billion yen, and the cost of electric power generation increases three times as high as that of LWRs. The role as the reactor that utilizes MOX fuel can be substituted by LWRs. The relation of trust with the local town must be considered. In view of these circumstances, it is judged that the stoppage of the construction plan is appropriate. It is necessary to investigate the substitute plan for the stoppage, and the viewpoints of investigating the substitute plan, the examination of the advanced BWR with all MOX fuel core and the method of advancing its construction are considered. On the research and development related to advanced thermal reactors, the research and development contributing to the advance of nuclear fuel recycling are advanced, and the prototype reactor 'Fugen' is utilized. (K.I.)

  18. High-Level Waste Systems Plan. Revision 7 (U)

    International Nuclear Information System (INIS)

    Brooke, J.N.; Gregory, M.V.; Paul, P.; Taylor, G.; Wise, F.E.; Davis, N.R.; Wells, M.N.

    1996-10-01

    This revision of the High-Level Waste (HLW) System Plan aligns SRS HLW program planning with the DOE Savannah River (DOE-SR) Ten Year Plan (QC-96-0005, Draft 8/6), which was issued in July 1996. The objective of the Ten Year Plan is to complete cleanup at most nuclear sites within the next ten years. The two key principles of the Ten Year Plan are to accelerate the reduction of the most urgent risks to human health and the environment and to reduce mortgage costs. Accordingly, this System Plan describes the HLW program that will remove HLW from all 24 old-style tanks, and close 20 of those tanks, by 2006 with vitrification of all HLW by 2018. To achieve these goals, the DWPF canister production rate is projected to climb to 300 canisters per year starting in FY06, and remain at that rate through the end of the program in FY18, (Compare that to past System Plans, in which DWPF production peaked at 200 canisters per year, and the program did not complete until 2026.) An additional $247M (FY98 dollars) must be made available as requested over the ten year planning period, including a one-time $10M to enhance Late Wash attainment. If appropriate resources are made available, facility attainment issues are resolved and regulatory support is sufficient, then completion of the HLW program in 2018 would achieve a $3.3 billion cost savings to DOE, versus the cost of completing the program in 2026. Facility status information is current as of October 31, 1996

  19. UMTRA Project environmental, health, and safety plan

    International Nuclear Information System (INIS)

    1989-02-01

    The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs

  20. Revised technical regulations on radiation protection and safety of 30 September 1975

    International Nuclear Information System (INIS)

    1975-01-01

    These revised technical regulations were made in implementation of Section 4 of Decree No 7/9038 of 30 November 1974 on radiation health and safety and lay down in detail the requirements to be met in Turkey for the use of all types of radiation sources. They set out protection plans and specify the protective equipment to be used as well as the controlled areas, i.e. areas in which radiation sources are used and which must be subject to special safety measures. Finally to obtain a license, users of radiation sources must fill in forms, the models of which are provided, giving their particulars and the specifications of the intended use and activity of the sources. (NEA) [fr

  1. 77 FR 76065 - Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Kendall Warm...

    Science.gov (United States)

    2012-12-26

    ...] Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Kendall Warm Springs Dace... revised recovery plan for the Kendall Warm Springs dace (Rhinichthys osculus thermalis). This species is... recovery plan. The Kendall Warm Springs dace (Rhinichthys osculus thermalis), found only in one location in...

  2. Approved Site Treatment Plan, Volumes 1 and 2. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    Helmich, E.H.; Molen, G.; Noller, D.

    1996-03-22

    The US Department of Energy, Savannah River Operations Office (DOE-SR), has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume 1. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore, pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE`s requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021. Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW. The Compliance Plan Volume (Volume 1) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume 2) and is provided for information.

  3. Approved Site Treatment Plan, Volumes 1 and 2. Revision 4

    International Nuclear Information System (INIS)

    Helmich, E.H.; Molen, G.; Noller, D.

    1996-01-01

    The US Department of Energy, Savannah River Operations Office (DOE-SR), has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume 1. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore, pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE's requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021. Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW. The Compliance Plan Volume (Volume 1) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume 2) and is provided for information

  4. Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

    International Nuclear Information System (INIS)

    Patterson, M.W.

    1994-10-01

    The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D ampersand D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision

  5. Safety research plan, JFY 2013 edition

    International Nuclear Information System (INIS)

    2013-09-01

    As for the regulatory issues the governments or JNES considered necessary, JNES had updated every year 'safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. 'Safety research plan, JFY 2013 Edition' was compiled aiming at promotion of appropriate reflection and flexible application of research achievements for tacking the regulatory issues taking account of importance and urgency dependent on trend of nuclear safety regulations as well as collective management of safety research and safety survey. 5 new research projects were established with 4 unified research projects and 6 terminated research projects. Finally modified safety research areas, subjects and research projects, JFY 2013 Edition were as follows: design review of nuclear power plant (7 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (one subject having 4 research projects), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 5), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). Safety reviews consisted of 6 projects in 3 areas extracting the regulatory issues. As for urgent research projects on the basis of the disaster at Fukushima Daiichi NPP accident, 7 research projects in 4 urgent subjects were as follows: examination for new safety regulation (4 research projects generalized in the above research projects), development of newly necessary evaluation methods (one research project generalized in the above research project), evaluation of the validity for the work for convergence at Fukushima

  6. 40 CFR 256.03 - State plan submission, adoption, and revision.

    Science.gov (United States)

    2010-07-01

    ... WASTES GUIDELINES FOR DEVELOPMENT AND IMPLEMENTATION OF STATE SOLID WASTE MANAGEMENT PLANS Purpose, General Requirements, Definitions § 256.03 State plan submission, adoption, and revision. (a) To be...

  7. 78 FR 59840 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2013-09-30

    ...] Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management District... of plan. * * * * * (c) * * * (428) * * * (i) * * * (B) Antelope Valley Air Quality Management...) * * * (i) * * * (B) Antelope Valley Air Quality Management District. (1) Rule 431.1, ``Sulfur Content of...

  8. Safety assessment for the 118-B-1 Burial Ground excavation treatability tests. Revision 2

    International Nuclear Information System (INIS)

    Zimmer, J.J.; Frain, J.M.

    1994-12-01

    This revision of the Safety Assessment provides an auditable safety analysis of the hazards for the proposed treatability test activities per DOE-EM-STD-5502-94, DOE Limited Standard, Hazard Baseline Documentation (DOE 1994). The proposed activities are classified as radiological activities and as such, no longer require Operational Safety Limits (OSLs). The OSLS, Prudent Actions, and Institutional and Organization Controls have been removed from this revision and replaced with ''Administrative Actions Important to Safety,'' as determined by the hazards analysis. Those Administrative Actions Important to Safety are summarized in Section 1.1, ''Assessment Summary.''

  9. 78 FR 61329 - Revision of the Land Management Plan for the Nantahala and Pisgah National Forests

    Science.gov (United States)

    2013-10-03

    .... Individuals who use telecommunication devices for the deaf (TDD) may call the Federal Information Relay.... More information on the planning process can also be found on the Nantahala and Pisgah Plan Revision... Forest Planning Rule (36 CFR Part 219), the planning process encompases three-stages: Assessment, plan...

  10. 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

  11. 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

  12. Savannah River Site integrated stabilization management plan. Revision 3

    International Nuclear Information System (INIS)

    Geddes, R.L.; Barone, A.; Shook, H.E.; Varner, C.E.; Rollins, R.

    1996-01-01

    On May 26, 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 94-1. The concern is that the halt in production of materials to be used in nuclear weapons froze the manufacturing pipeline in a state that, for safety reasons, should not be allowed to persist unremediated. This recommendation had eight specific sub-recommendations that dealt with the potential problems. Specifically, the Board expressed concern about certain liquids and solids containing fissile materials and other radioactive substances located in spent fuel storage pools, reactor basins, reprocessing canyons; and various other facilities once used for processing and weapons manufacture. The WSRC and DOE-SR acknowledges and shares the Board's concerns and has developed this Integrated Stabilization Management Plan (ISMP) to aggressively address these urgent problems in a systems engineering approach

  13. Management plan for White Oak Dam. Revision 1

    International Nuclear Information System (INIS)

    Ahmed, S.B.

    1997-03-01

    The purpose is to provide operation and maintenance, periodic inspection, and emergency action plans for White Oak Dam in general accordance with the Federal Emergency Management Agency (FEMA) guidelines for dam safety. It must be understood that operations at the site are primarily for purposes of environmental monitoring, environmental protection and waste management operations control. Effluent is generally allowed to flow from the lake at its natural rate by rising above the broad crested weir notch elevation of 744 feet m.s.l

  14. UMTRA Project Office quality assurance program plan. Revision 6

    International Nuclear Information System (INIS)

    1994-09-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project was established to accomplish remedial actions at inactive uranium mill tailings sites. The UMTRA Project's mission is to stabilize and control the residual radioactive materials at designated sites in a safe and environmentally sound manner so as to minimize or eliminate radiation health hazards to the public. Because these efforts may involve possible risks to public health and safety, a quality assurance (QA) program that conforms to the applicable criteria has been established to control the quality of the work. This document, the Quality Assurance Program Plan (QAPP), brings into one document the essential criteria to be applied on a selective basis, depending upon the nature of the activity being conducted, and describes how those criteria shall be applied to the UMTRA Project. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the UMTRA Project Office and its contractors

  15. DOE Region 6 Radiological Assistance Program plan. Revision 1

    International Nuclear Information System (INIS)

    Jakubowski, F.M.

    1995-11-01

    The US Department of Energy (DOE) has sponsored a Radiological Assistance Program (RAP) since the 1950's. The RAP is designed to make DOE resources available to other DOE facilities, state, tribal, local, private businesses, and individuals for the explicit purpose of assisting during radiological incidents. The DOE has an obligation, through the Atomic Energy Act of 1954, as amended, to provide resources through the Federal Radiological Emergency Response Plan (FRERP, Nov. 1985) in the event of a radiological incident. Toward this end, the RAP program is implemented on a regional basis, and has planned for an incremental response capability with regional coordination between states and DOE response elements. This regional coordination is intended to foster a working relationship between DOE radiological assistance elements and those state, tribal, and local agencies responsible for first response to protect public health and safety

  16. DOE-owned spent nuclear fuel strategic plan. Revision 1

    International Nuclear Information System (INIS)

    1996-09-01

    The Department of Energy (DOE) is responsible for safely and efficiently managing DOE-owned spent nuclear fuel (SNF) and SNF returned to the US from foreign research reactors (FRR). The fuel will be treated where necessary, packaged suitable for repository disposal where practicable, and placed in interim dry storage. These actions will remove remaining vulnerabilities, make as much spent fuel as possible ready for ultimate disposition, and substantially reduce the cost of continued storage. The goal is to complete these actions in 10 years. This SNF Strategic Plan updates the mission, vision, objectives, and strategies for the management of DOE-owned SNF articulated by the SNF Strategic Plan issued in December 1994. The plan describes the remaining issues facing the EM SNF Program, lays out strategies for addressing these issues, and identifies success criteria by which program progress is measured. The objectives and strategies in this plan are consistent with the following Em principles described by the Assistance Secretary in his June 1996 initiative to establish a 10-year time horizon for achieving most program objectives: eliminate and manage the most serious risks; reduce mortgage and support costs to free up funds for further risk reduction; protect worker health and safety; reduce generation of wastes; create a collaborative relationship between DOE and its regulators and stakeholders; focus technology development on cost and risk reduction; and strengthen management and financial control

  17. Sign up to Safety: developing a safety improvement plan.

    Science.gov (United States)

    Dight, Carol; Peters, Hayley

    2015-04-01

    The Sign up to Safety (SutS) programme was launched in June 2014 by health secretary Jeremy Hunt. It focuses on listening to patients, carers and staff, learning from what they say when things go wrong, and then taking action to improve patient safety. The programme aims to make the NHS the safest healthcare system in the world by creating a culture devoted to continuous learning and improvement (NHS England 2014). Musgrove Park Hospital, part of Taunton and Somerset NHS Foundation Trust, was one of 12 NHS organisations that signed up to the SutS programme, making public its commitment to the national pledges to be 'open and transparent' and to develop a safety improvement plan. This paper describes the development of the strategy.

  18. Certification plan for safety and PRA codes

    International Nuclear Information System (INIS)

    Toffer, H.; Crowe, R.D.; Ades, M.J.

    1990-05-01

    A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA ampersand PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan's objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations

  19. Maintenance implementation plan for the Plutonium Finishing Plant. Revision 3

    International Nuclear Information System (INIS)

    Meldrom, C.A.

    1996-03-01

    This document outlines the Maintenance Implementation Plan (MIP) for the Plutonium Finishing Plant (PFP) located at the Hanford site at Richland, Washington. This MIP describes the PFP maintenance program relative to DOE order 4330.4B. The MIP defines the key actions needed to meet the guidelines of the Order to produce a cost-effective and efficient maintenance program. A previous report identified the presence of significant quantities of Pu-bearing materials within PFP that pose risks to workers. PFP's current mission is to develop, install and operate processes which will mitigate these risks. The PFP Maintenance strategy is to equip the facility with systems and equipment able to sustain scheduled PFP operations. The current operating run is scheduled to last seven years. Activities following the stabilization operation will involve an Environmental Impact Statement (EIS) to determine future plant activities. This strategy includes long-term maintenance of the facility for safe occupancy and material storage. The PFP maintenance staff used the graded approach to dictate the priorities of the improvement and upgrade actions identified in Chapter 2 of this document. The MIP documents PFP compliance to the DOE 4330.4B Order. Chapter 2 of the MIP follows the format of the Order in addressing the eighteen elements. As this revision is a total rewrite, no sidebars are included to highlight changes

  20. 242-A Evaporator waste analysis plan. Revision 4

    International Nuclear Information System (INIS)

    Basra, T.S.; Mulkey, C.H.

    1994-01-01

    This waste analysis plan (WAP) provides the plan for obtaining information needed for proper waste handling and processing in the 242-A Evaporator located on the Hanford Site. Regulatory and safety issues are addressed by establishing boundary conditions for waste received and treated at the 242-A Evaporator. The boundary conditions are set by establishing limits for items such as potential exothermic reactions, waste compatibility, and control of vessel vent organic emissions. Boundary conditions are also set for operational considerations and to ensure waste acceptance at receiving facilities. The issues that are addressed in this plan include prevention of exotherms in the waste, waste compatibility, vessel vent emissions, and compatibility with the liner in the Liquid Effluent Retention Facility (LERF). The 242-A Evaporator feed stream is separated into two liquid streams: a concentrated slurry stream and a process condensate. A gaseous exhaust stream is also produced. The slurry contains the majority of the radionuclides and inorganic constituents. This stream is pumped back to the double shell tanks (DSTs) and stored for further treatment after being concentrated to target levels. The process condensate (PC) is primarily water that contains trace amounts of organic material and a greatly reduced concentration of radionuclides. The process condensate is presently stored in the (LERF) until it can be further processed in the Effluent Treatment Facility once it is operational

  1. UMTRA Project: Environment, Safety, and Health Plan

    International Nuclear Information System (INIS)

    1995-02-01

    The US Department of Energy has prepared this UMTRA Project Environment, Safety, and Health (ES and H) Plan to establish the policy, implementing requirements, and guidance for the UMTRA Project. The requirements and guidance identified in this plan are designed to provide technical direction to UMTRA Project contractors to assist in the development and implementation of their ES and H plans and programs for UMTRA Project work activities. Specific requirements set forth in this UMTRA Project ES and H Plan are intended to provide uniformity to the UMTRA Project's ES and H programs for processing sites, disposal sites, and vicinity properties. In all cases, this UMTRA Project ES and H Plan is intended to be consistent with applicable standards and regulations and to provide guidance that is generic in nature and will allow for contractors' evaluation of site or contract-specific ES and H conditions. This plan specifies the basic ES and H requirements applicable to UMTRA Project ES and H programs and delineates responsibilities for carrying out this plan. DOE and contractor ES and H personnel are expected to exercise professional judgment and apply a graded approach when interpreting these guidelines, based on the risk of operations

  2. Environment, Safety, Health and Waste Management Plan

    International Nuclear Information System (INIS)

    1988-01-01

    The mission of the Feed Materials Production Center (FMPC) is the production of high qaulity uranium metal for use by the US Department of Energy (DOE) in Defense Programs. In order to accomplish this mission and to maintain the FMPC as a viable facility in the DOE production complex, the facility must be brought into full compliance with all federal and state regulations and industry standards for environmental protection and worker safety. Where past practices have resulted in environmental insult, a comprehensive program of remediation must be implemented. The purpose of this combined Environment, Safety, Health and Waste Management Plan is to provide a road map for achieving needed improvements. The plan is structured to provide a comprehensive projection from the current fiscal year (FY) through FY 1994 of the programs, projects and funding required to achieve compliance. To do this, the plan is subdivided into chapters which discuss the applicable regulations;project schedules and funding requirements;details of the various programs for environment, safety, health and waste management;details of the ongoing National Environmental Policy Act (NEPA);the quality assurance program and the environmental monitoring program. 14 refs., 30 figs., 29 tabs

  3. Revision of the basic plans of the first nuclear-powered ship development

    International Nuclear Information System (INIS)

    1978-01-01

    Along with the law for Japan Nuclear Ship Development Agency, the basic plans of development of the first nuclear-powered ship have been revised. After explaining the basic policy concerning the matter, the development program is described as follows: ship type/kind, nuclear power plant, construction, training of ship crew, experimental voyage, compilation of the development results, and works after the experimental voyage. The first nuclear-powered ship of about 8,000 tons gross tonnage, 10,000 horsepower main engine output, and about 16 knots, sea speed will be the ship for special cargo transport and crew training. A pressurized water reactor is used for the power plant. Following the repair of shielding and the overall inspection of safety, the ship is to be completed as early as possible. After completion of the ship, its experimental voyage will be carried out, aiming at the aspects of operational familiarization, ship performance, reliability, port call experience, etc. (Mori, K

  4. The development and revision of the Federal Radiological Emergency Response Plan

    International Nuclear Information System (INIS)

    Gant, K.S.; Adler, M.V.; Wolff, W.F.

    1989-01-01

    Since 1985, federal agencies have been using the Federal Radiological Emergency Response Plan (FRERP) in exercises and real events. This experience and the development of other emergency response guidance (e.g., National System for Emergency Coordination) are fueling current efforts to review and revise the FRERP to reflect what the agencies have learned since the FRERP was published. Revision efforts are concentrating on clarifying the plan and addressing deficiencies. No major changes are expected in the general structure of the federal response nor should states need to revise their plans because of these modifications. 5 refs

  5. 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

  6. 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.

  7. 75 FR 27647 - Approval and Promulgation of Air Quality Implementation Plans; Texas; Revisions to the Emission...

    Science.gov (United States)

    2010-05-18

    ... severable portions of two revisions to the Texas State Implementation Plan (SIP) submitted by the State of... further clarify procedures for using emission protocols and to update the approved list of emission credit... to recently recodified 30 TAC Chapter 117 provisions. EPA has determined that these SIP revisions...

  8. 75 FR 15391 - Approval and Promulgation of Air Quality Implementation Plans; Texas; Revision to Control...

    Science.gov (United States)

    2010-03-29

    ... to control volatile organic compound (VOC) emissions from storage tanks, transport vessels and marine... Promulgation of Air Quality Implementation Plans; Texas; Revision to Control Volatile Organic Compound.... Specifically, this revision subjects owners or operators of VOC storage tanks, transport vessels, and marine...

  9. 77 FR 2496 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2012-01-18

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2011-0987; FRL-9617-5] Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management District and Imperial... rule. SUMMARY: EPA is proposing to approve revisions to the Antelope Valley Air Quality Management...

  10. 78 FR 49992 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2013-08-16

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2013-0394; FRL-9845-4] Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management District and Ventura... rule. SUMMARY: EPA is proposing to approve revisions to the Antelope Valley Air Quality Management...

  11. 78 FR 37176 - Revisions to the California State Implementation Plan, San Diego Air Pollution Control District

    Science.gov (United States)

    2013-06-20

    ...EPA is proposing to approve a revision to the San Diego Air Pollution Control District (SDAPCD) portion of the California State Implementation Plan (SIP). This revision concerns volatile organic compound (VOC) emissions from architectural coatings. We are proposing to approve a local rule to regulate these emission sources under the Clean Air Act (CAA or the Act).

  12. 78 FR 37130 - Revisions to the California State Implementation Plan, San Diego Air Pollution Control District

    Science.gov (United States)

    2013-06-20

    ...EPA is taking direct final action to approve a revision to the San Diego Air Pollution Control District (SDAPCD) portion of the California State Implementation Plan (SIP). This revision concerns volatile organic compound (VOC) emissions from architectural coatings. We are approving a local rule that regulates this emission source under the Clean Air Act (CAA or the Act).

  13. 75 FR 56889 - Revisions to the California State Implementation Plan, San Diego County Air Pollution Control...

    Science.gov (United States)

    2010-09-17

    ...EPA is taking direct final action to approve revisions to the San Diego County Air Pollution Control District (SDCAPCD) portion of the California State Implementation Plan (SIP). This revision concerns the definition of volatile organic compound (VOC). We are approving a local rule that regulates these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  14. 75 FR 56942 - Revisions to the California State Implementation Plan, San Diego County Air Pollution Control...

    Science.gov (United States)

    2010-09-17

    ...EPA is proposing to approve revisions to the San Diego Air Pollution Control District (SDCAPCD) portion of the California State Implementation Plan (SIP). This revision concerns the definition of volatile organic compounds (VOC). We are proposing to approve a local rule to regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  15. 78 FR 6784 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control District

    Science.gov (United States)

    2013-01-31

    ...EPA is proposing to approve revisions to the Placer County Air Pollution Control District (PCAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC), oxides of nitrogen (NOX), and particulate matter (PM) emissions from open burning. We are proposing to approve local rules to regulate this emission source under the Clean Air Act (CAA or the Act).

  16. 78 FR 6736 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control District

    Science.gov (United States)

    2013-01-31

    ...EPA is taking direct final action to approve revisions to the Placer County Air Pollution Control District (PCAPCD) portion of the California State Implementation Plan (SIP). These revisions concern Volatile Organic Compound (VOC), oxides of nitrogen (NOX), and particulate matter (PM) emissions from open burning. We are approving local rules that regulate this emission source under the Clean Air Act (CAA or the Act).

  17. 78 FR 63929 - Approval and Promulgation of Air Quality Implementation Plans; Texas; Revisions to Rules and...

    Science.gov (United States)

    2013-10-25

    ... requirements for grandfathered facilities. The revisions will contribute to improvement in overall air quality... to contribute to improvement of air quality and attainment or maintenance of the federal air quality...] Approval and Promulgation of Air Quality Implementation Plans; Texas; Revisions to Rules and Regulations...

  18. 78 FR 37132 - Approval and Promulgation of Implementation Plans; Revised Format for Materials Being...

    Science.gov (United States)

    2013-06-20

    ... Promulgation of Implementation Plans; Revised Format for Materials Being Incorporated by Reference for Florida... the ``good cause'' exemption in section 553(b)(3)(B) of the Administrative Procedure Act (APA) which... recodification and miscellaneous revisions to the Florida SIP. EPA also finds that there is good cause under APA...

  19. 76 FR 41705 - Approval and Promulgation of Implementation Plans; New York; Revised Format of Materials Being...

    Science.gov (United States)

    2011-07-15

    ...-year period, EPA will review its experience with the new table format and will decide whether or not to... the APA, since the reorganization and codification of the revised format for denoting IBR of the state... Promulgation of Implementation Plans; New York; Revised Format of Materials Being Incorporated by Reference...

  20. Single-shell tank closure work plan. Revision A

    International Nuclear Information System (INIS)

    1995-06-01

    In January 1994, the Hanford Federal Facility Agreement and Conset Order (Tri-Party Agreement) was amended to reflect a revised strategy for remediation of radioactive waste in underground storage tanks. These amendments include milestones for closure of the single-shell tank (SST) operable units, to be initiated by March 2012 and completed by September 2024. This SST-CWP has been prepared to address the principal topical areas identified in Tri-Party Agreement Milestone M-45-06 (i.e., regulatory pathway, operable unit characterization, waste retrieval, technology development, and a strategy for achieving closure). Chapter 2.0 of this SST-CWP provides a brief description of the environmental setting, SST System, the origin and characteristics of SST waste, and ancillary equipment that will be remediated as part of SST operable unit closure. Appendix 2A provides a description of the hydrogeology of the Hanford Site, including information on the unsaturated sediments (vadose zone) beneath the 200 Areas Plateau. Chapter 3.0 provides a discussion of the laws and regulations applicable to closure of the SST farm operable units. Chapter 4.0 provides a summary description of the ongoing characterization activities that best align with the proposed regulatory pathway for closure. Chapter 5.0 describes aspects of the SST waste retrieval program, including retrieval strategy, technology, and sequence, potential tank leakage during retrieval, and considerations of deployment of subsurface barriers. Chapter 6.0 outlines a proposed strategy for closure. Chapter 7.0 provides a summary of the programs underway or planned to develop technologies to support closure. Ca. 325 refs

  1. Single-shell tank closure work plan. Revision A

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    In January 1994, the Hanford Federal Facility Agreement and Conset Order (Tri-Party Agreement) was amended to reflect a revised strategy for remediation of radioactive waste in underground storage tanks. These amendments include milestones for closure of the single-shell tank (SST) operable units, to be initiated by March 2012 and completed by September 2024. This SST-CWP has been prepared to address the principal topical areas identified in Tri-Party Agreement Milestone M-45-06 (i.e., regulatory pathway, operable unit characterization, waste retrieval, technology development, and a strategy for achieving closure). Chapter 2.0 of this SST-CWP provides a brief description of the environmental setting, SST System, the origin and characteristics of SST waste, and ancillary equipment that will be remediated as part of SST operable unit closure. Appendix 2A provides a description of the hydrogeology of the Hanford Site, including information on the unsaturated sediments (vadose zone) beneath the 200 Areas Plateau. Chapter 3.0 provides a discussion of the laws and regulations applicable to closure of the SST farm operable units. Chapter 4.0 provides a summary description of the ongoing characterization activities that best align with the proposed regulatory pathway for closure. Chapter 5.0 describes aspects of the SST waste retrieval program, including retrieval strategy, technology, and sequence, potential tank leakage during retrieval, and considerations of deployment of subsurface barriers. Chapter 6.0 outlines a proposed strategy for closure. Chapter 7.0 provides a summary of the programs underway or planned to develop technologies to support closure. Ca. 325 refs.

  2. 78 FR 73692 - Revisions to Safety Standards for Infant Bath Seats, Toddler Beds, and Full-Size Baby Cribs

    Science.gov (United States)

    2013-12-09

    ... standard issued under the Danny Keysar Child Product Safety Notification Act was based, the revision... standard. Section 26(c) of the CPSA also provides that states or political subdivisions of states may apply... CONSUMER PRODUCT SAFETY COMMISSION 16 CFR Parts 1215, 1217 and 1219 Revisions to Safety Standards...

  3. 76 FR 44493 - Revisions to the California State Implementation Plan, Northern Sierra Air Quality Management...

    Science.gov (United States)

    2011-07-26

    ... California State Implementation Plan, Northern Sierra Air Quality Management District, Sacramento Metropolitan Air Quality Management District, and South Coast Air Quality Management District AGENCY... approve revisions to the Northern Sierra Air Quality Management District (NSAQMD), Sacramento Metropolitan...

  4. 77 FR 65133 - Revisions to the California State Implementation Plan, Mojave Desert Air Quality Management District

    Science.gov (United States)

    2012-10-25

    ... the California State Implementation Plan, Mojave Desert Air Quality Management District AGENCY... limited disapproval of revisions to the Mojave Desert Air Quality Management District (MDAQMD) portion of.... * * * * * (c) * * * (379) * * * (i) * * * (E) Mojave Desert Air Quality Management District. (1) Rule 1159...

  5. 78 FR 21582 - Revisions to the California State Implementation Plan, Butte County Air Quality Management...

    Science.gov (United States)

    2013-04-11

    ... the California State Implementation Plan, Butte County Air Quality Management District and Sacramento Metropolitan Air Quality Management District AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: EPA is proposing to approve revisions to the Butte County Air Quality Management...

  6. 77 FR 12526 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2012-03-01

    ... the California State Implementation Plan, Antelope Valley Air Quality Management District and Mojave Desert Quality Management District AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: EPA is proposing to approve revisions to the Antelope Valley Air Quality Management District...

  7. 76 FR 5276 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-01-31

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the... protection, Air pollution control, Incorporation by reference, Intergovernmental relations, Nitrogen dioxide...

  8. 75 FR 40762 - Revisions to the California State Implementation Plan, Sacramento Metropolitan Air Quality...

    Science.gov (United States)

    2010-07-14

    ... the California State Implementation Plan, Sacramento Metropolitan Air Quality Management District and South Coast Air Quality Management District AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: EPA is proposing to approve revisions to the Sacramento Metropolitan Air Quality...

  9. 76 FR 52623 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-08-23

    ... respiratory and cardiovascular disease, decreased lung function, visibility impairment, and damage to... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of...

  10. 75 FR 28509 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2010-05-21

    ..., aggravation of respiratory and cardiovascular disease, decreased lung function, visibility impairment, and... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of...

  11. 76 FR 37044 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-06-24

    ... premature mortality, aggravation of respiratory and cardiovascular disease, decreased lung function... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of...

  12. 77 FR 35327 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-06-13

    ...EPA is proposing to approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from the manufacture of polystyrene, polyethylene, and polypropylene products. We are approving a local rule that regulates these emission sources under the Clean Air Act (CAA or the Act). We are taking comments on this proposal and plan to follow with a final action.

  13. 77 FR 24883 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-04-26

    ...EPA is proposing to approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the California State Implementation Plan (SIP). These revisions concern oxides of nitrogen (NOX) from solid fuel fired boilers, steam generators and process heaters. We are approving a local rule that regulates these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act). We are taking comments on this proposal and plan to follow with a final action.

  14. 77 FR 35329 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-06-13

    ...EPA is proposing to approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from crude oil production sumps and refinery wastewater separators. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act). We are taking comments on this proposal and plan to follow with a final action.

  15. Safety analysis report for the Waste Storage Facility. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Bengston, S.J.

    1994-05-01

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

  16. Revision of AESJ standard 'the code of implemnetation of periodic safety review of nuclear power plants'

    International Nuclear Information System (INIS)

    Hirano, Masashi; Narumiya, Yoshiyuki

    2010-01-01

    The Periodic Safety Review (PSR) was launched in June 1992, when the Agency for Natural Resources and Energy issued a notification that required licensees to conduct comprehensive review on the safety of each existing nuclear power plant (NPP) once approximately every ten years based on the latest technical findings for the purpose of improving the safety of the NPP. In 2006, the Standard Committee of the Atomic Energy Society of Japan established the first version of 'The Standard of Implementation for Periodic Safety Review of Nuclear Power Plants: 2006'. Taking into account developments in safety regulation of PSR after the issuance of the first version, the Standard Committee has revised the Standard. This paper summarizes background on PSR, such developments are major contents of the Standard as well as the focal points of the revision. (author)

  17. 75 FR 38432 - Railroad Safety Appliance Standards, Miscellaneous Revisions

    Science.gov (United States)

    2010-07-02

    ...: Stephen J. Carullo, Railroad Safety Specialist, Office of Safety, FRA, 1200 New Jersey Avenue, SE..., Office of Chief Counsel, FRA, 1200 New Jersey Avenue, SE., Mail Stop 10, Washington, DC 20590 (telephone... government (FRA and Transport Canada participate as non-voting members), as well as ergonomics experts. The...

  18. Revised

    DEFF Research Database (Denmark)

    Johannsen, Vivian Kvist; Nord-Larsen, Thomas; Riis-Nielsen, Torben

    This report is a revised analysis of the Danish data on CO2 emissions from forest, afforestation and deforestation for the period 1990 - 2008 and a prognosis for the period until 2020. Revision have included measurements from 2009 in the estimations. The report is funded by the Ministry of Climate...

  19. Menu Planning Guide for School Food Service. Revised.

    Science.gov (United States)

    VanEgmont-Pannell, Dorothy; And Others

    This menu planning guide for school lunches and breakfasts contains: (1) lunch requirements, recommendations, and policies; (2) the basics of menu planning; (3) how to vary portions for various age/grade groups; (4) planning breakfasts; (5) merchandising school lunches and breakfasts; and (6) nutrition education and menu planning; Appendixes…

  20. A revised 3-column classification approach for the surgical planning of extended lateral tibial plateau fractures.

    Science.gov (United States)

    Hoekstra, H; Kempenaers, K; Nijs, S

    2017-10-01

    Variable angle locking compression plates allow for lateral buttress and support of the posterolateral joint surface of tibial plateau fractures. This gives room for improvement of the surgical 3-column classification approach. Our aim was to revise and validate the 3-column classification approach to better guide the surgical planning of tibial plateau fractures extending into the posterolateral corner. In contrast to the 3-column classification approach, in the revised approach the posterior border of the lateral column in the revised approach lies posterior instead of anterior of the fibula. According to the revised 3-column classification approach, extended lateral column fractures are defined as single lateral column fractures extending posteriorly into the posterolateral corner. CT-images of 36 patients were reviewed and classified twice online according to Schatzker and revised 3-column classification approach by five observers. The intraobserver reliability was calculated using the Cohen's kappa and the interobserver reliability was calculated using the Fleiss' kappa. The intraobserver reliability showed substantial agreement according to Landis and Koch for both Schatzker and the revised 3-column classification approach (0.746 vs. 0.782 p = 0.37, Schatzker vs. revised 3-column, respectively). However, the interobserver reliability of the revised 3-column classification approach was significantly higher as compared to the Schatzker classification (0.531 vs. 0.669 p column, respectively). With the introduction of variable angle locking compression plates, the revised 3-column classification approach is a very helpful tool in the preoperative surgical planning of tibial plateau fractures, in particular, lateral column fractures that extend into the posterolateral corner. The revised 3-column classification approach is rather a practical supplement to the Schatzker classification. It has a significantly higher interobserver reliability as compared to the

  1. 76 FR 32113 - Revisions to the California State Implementation Plan

    Science.gov (United States)

    2011-06-03

    .... SUMMARY: EPA is proposing to approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) and Imperial County Air Pollution Control District (ICAPCD) portions of the California... Motor Vehicle Assembly Coatings, Surface Coatings of Metal Parts and Products, Plastic Parts and...

  2. Waste convention regulatory impact on planning safety assessment for LILW disposal in Croatia

    International Nuclear Information System (INIS)

    Valcic, I.; Subasic, D.; Lokner, V.

    2000-01-01

    Preparations for establishment of a LILW repository in Croatia have reached a point where a preliminary safety assessment for the prospective facility is being planned. The planning is not based upon the national regulatory framework, which does not require such an assessment at this early stage, but upon the interagency BSS and the IAEA RADWASS programme recommendations because the national regulations are being revised with express purpose to conform to the most recent international standards and good practices. The Waste Convention, which Croatia has ratified in the meantime, supports this approach in principle, but does not appear to have more tangible regulatory relevance for the safety assessment planning. Its actual requirements regarding safety analyses for a repository fall short of the specific assessment concepts practiced in this decade, and could have well been met by the old Croatian regulations from the mid-eighties. (author)

  3. 75 FR 2846 - Plan Revision for Prescott National Forest, Yavapai and Coconino Counties, AZ

    Science.gov (United States)

    2010-01-19

    .... Finally, this notice briefly describes the applicable planning rule and how work done on the plan revision... addressed project specific needs and the balance addressed programmatic needs. Programmatic needs for... guidelines; Suitability of lands for timber production, grazing, and recreation opportunities; Monitoring and...

  4. 78 FR 16612 - National Oil and Hazardous Substances Pollution Contingency Plan; Revision To Increase Public...

    Science.gov (United States)

    2013-03-18

    ... Hazardous Substances Pollution Contingency Plan (NCP) to broaden the technology, to include computer... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 300 [EPA-HQ-SFUND-2012-0738; FRL-9791-4] National Oil and Hazardous Substances Pollution Contingency Plan; Revision To Increase Public Availability of the...

  5. 76 FR 59155 - Notice of Availability of South Coast Draft Resource Management Plan Revision and Draft...

    Science.gov (United States)

    2011-09-23

    ... policies and emphasis on the management of public lands and local land use planning; and new data that have... DEPARTMENT OF THE INTERIOR Bureau of Land Management [LLCAD06000, L16100000.DP0000] Notice of Availability of South Coast Draft Resource Management Plan Revision and Draft Environmental Impact Statement...

  6. Use of risk assessment panels during revision of the Tongass Land and Resource Management Plan.

    Science.gov (United States)

    Charles G. Shaw

    1999-01-01

    This paper describes the process used to conduct the 16 risk assessment panels and a subsistence working group held during revision of the Tongass land management plan. It provides an overview of how results from the panels were used by forest managers in plan-related decisionmaking, discusses some reactions to the effort, and identifies some opportunities to improve...

  7. 75 FR 56131 - Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for the Northern...

    Science.gov (United States)

    2010-09-15

    ... on the MOCA network recommended in the 2008 Recovery Plan and will instead use the model results to... DEPARTMENT OF THE INTERIOR Fish and Wildlife Service [FWS-R1-ES-2010-N184; 10120-1113-0000-C2] Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for the Northern Spotted Owl...

  8. 78 FR 7703 - Revisions to the California State Implementation Plan, South Coast Air Quality Management...

    Science.gov (United States)

    2013-02-04

    ... the California State Implementation Plan, South Coast Air Quality Management District, Proposed Rule... approve a revision to the South Coast Air Quality Management District (SCAQMD) portion of the California... digesters. Rule 1127 was designed to implement the 2003 Air Quality Management Plan (AQMP) control measure...

  9. 75 FR 32353 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2010-06-08

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2010-0276; FRL-9139-8] Revisions to the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District portion of the California State Implementation Plan...

  10. 77 FR 32483 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2012-06-01

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0236; FRL-9670-9] Revisions to the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District portion of the California State Implementation Plan...

  11. 75 FR 25775 - Disapproval of State Implementation Plan Revisions, South Coast Air Quality Management District

    Science.gov (United States)

    2010-05-10

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2009-0573; FRL-9146-5] Disapproval of State Implementation Plan Revisions, South Coast Air Quality Management District AGENCY: Environmental... South Coast Air Quality Management District (SCAQMD) portion of the California State Implementation Plan...

  12. 76 FR 76115 - Revisions to the California State Implementation Plan, Feather River Air Quality Management District

    Science.gov (United States)

    2011-12-06

    ... the California State Implementation Plan, Feather River Air Quality Management District AGENCY... limited disapproval of revisions to the Feather River Air Quality Management District (FRAQMD) portion of..., Regulatory Planning and Review The Office of Management and Budget (OMB) has exempted this regulatory action...

  13. 20 CFR 435.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NON-PROFIT ORGANIZATIONS, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 435.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  14. 38 CFR 49.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) UNIFORM ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 49.25 Revision of budget and program plans. (a) The budget plan is the financial expression of...

  15. 22 CFR 145.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... Section 145.25 Foreign Relations DEPARTMENT OF STATE CIVIL RIGHTS GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 145.25 Revision of budget and program plans. (a) The budget plan is the...

  16. 28 CFR 70.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... REQUIREMENTS FOR GRANTS AND AGREEMENTS (INCLUDING SUBAWARDS) WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 70.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  17. 22 CFR 518.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 518.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or program as approved during the...

  18. 45 CFR 2543.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ... AND COMMUNITY SERVICE GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 2543.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  19. 40 CFR 30.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... FEDERAL ASSISTANCE UNIFORM ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 30.25 Revision of budget and program plans. (a) The budget plan is the financial...

  20. 34 CFR 74.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 74.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or program as approved during the award process. It may...

  1. 45 CFR 74.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ... ADMINISTRATIVE REQUIREMENTS FOR AWARDS AND SUBAWARDS TO INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NONPROFIT ORGANIZATIONS, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 74.25 Revision of budget and program plans. (a) The budget plan is the financial expression of...

  2. 15 CFR 14.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NON-PROFIT, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 14.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  3. 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

  4. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

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

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  5. Nuclear Criticality Safety Organization training implementation. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-05-19

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document provides a listing of the roles and responsibilities of NCSO personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This Training Implementation document is applicable to all technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who are in a qualification program.

  6. Nuclear Criticality Safety Organization training implementation. Revision 4

    International Nuclear Information System (INIS)

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

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document provides a listing of the roles and responsibilities of NCSO personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This Training Implementation document is applicable to all technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who are in a qualification program

  7. 78 FR 21581 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2013-04-11

    ...EPA is proposing to approve revisions to the Antelope Valley Air Quality Management District (AVAQMD), Monterey Bay Unified Air Pollution Control District (MBUAPCD) and Santa Barbara County Air Pollution Control District (SCAPCD) portions of the California State Implementation Plan (SIP). We are proposing to approve revisions local rules that address emission statements for AVAQMD, rule rescissions that address public records for MBUAPCD, and define terms for SBCAPCD, under the Clean Air Act as amended in 1990 (CAA or the Act).

  8. 77 FR 12491 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2012-03-01

    ...EPA is taking direct final action to approve revisions to the Antelope Valley Air Quality Management District (AVAQMD) and San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portions of the California State Implementation Plan (SIP). These revisions concern negative declarations for volatile organic compound (VOC) and oxides of sulfur source categories for the AVAQMD and SJVUAPCD. We are approving these negative declarations under the Clean Air Act as amended in 1990 (CAA or the Act).

  9. 77 FR 12527 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2012-03-01

    ...EPA is proposing to approve revisions to the Antelope Valley Air Quality Management District (AVAQMD) and San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portions of the California State Implementation Plan (SIP). These revisions concern negative declarations for volatile organic compound (VOC) and oxides of sulfur source categories. We are proposing to approve these negative declarations under the Clean Air Act as amended in 1990 (CAA or the Act).

  10. 76 FR 67366 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2011-11-01

    ...EPA is taking direct final action to approve revisions to the Placer County Air Pollution Control District (PCAPCD) and Sacramento Metro Air Quality Management District (SMAQMD) portions of the California State Implementation Plan (SIP). These revisions concern oxides of nitrogen (NOX) emissions from industrial, institutional and commercial boilers, stationary internal combustion engines and water heaters. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  11. 76 FR 39357 - Revisions to the California State Implementation Plan, Imperial County Air Pollution Control...

    Science.gov (United States)

    2011-07-06

    ...EPA is proposing to approve revisions to the Imperial County Air Pollution Control District (ICAPCD), Kern County Air Pollution Control District (KCAPCD), and Ventura County Air Pollution Control District (VCAPCD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from architectural coating operations. We are proposing to approve local rules to regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  12. 76 FR 17347 - Revision to the California State Implementation Plan, Great Basin Unified Air Pollution Control...

    Science.gov (United States)

    2011-03-29

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 Revision to the California State Implementation Plan, Great Basin Unified Air Pollution Control District CFR Correction In Title 40 of the Code of Federal Regulations, Part 52 (Sec. Sec. 52.01 to 52.1018), revised as of July 1, 2010, on page 252, in Sec. 52.220, paragraph (c)(345)(i)(D) is added to...

  13. 76 FR 30080 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2011-05-24

    ...EPA is proposing to approve revisions to the Placer County Air Pollution Control District (PCAPCD) and Ventura County Air Pollution Control District (VCAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from surface coatings of metal parts and products. We are proposing to approve local rules to regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  14. 75 FR 24408 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2010-05-05

    ...EPA is finalizing approval of revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVAPCD) portion of the California State Implementation Plan (SIP). These revisions were proposed in the Federal Register on January 22, 2010 and concern oxides of nitrogen (NOx) emissions from residential water heaters. We are approving a local rule that regulates this emission source under the Clean Air Act as amended in 1990 (CAA or the Act).

  15. 76 FR 71886 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2011-11-21

    ...EPA is taking direct final action to approve revisions to the Placer County Air Pollution Control District (PCAPCD) and Sacramento Metropolitan Air Quality Management District (SMAQMD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from coatings and strippers used on wood products, wood paneling, and miscellaneous metal parts and products. We are approving these local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  16. 76 FR 71922 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2011-11-21

    ...EPA is proposing to approve revisions to the Placer County Air Pollution Control District (PCAPCD) and Sacramento Metropolitan Air Quality Management District (SMAQMD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from coatings and strippers used on wood products, wood paneling, and miscellaneous metal parts and products. We are proposing to approve three local rules to regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  17. 77 FR 73322 - Revisions to the California State Implementation Plan, Monterey Bay Unified Air Pollution Control...

    Science.gov (United States)

    2012-12-10

    ...EPA is taking direct final action to approve revisions to the Monterey Bay Unified Air Pollution Control District (MBUAPCD) portion of the California State Implementation Plan (SIP). These revisions concern opacity standards related to multiple pollutants, including particulate matter (PM) emissions from several different types of sources, ranging from fugitive dust to gas turbines. We are approving a local rule that regulates these emission sources under the Clean Air Act (CAA or the Act).

  18. 75 FR 10690 - Revisions to the California State Implementation Plan, San Joaquin Valley Air Pollution Control...

    Science.gov (United States)

    2010-03-09

    ...EPA is finalizing approval of revisions to the San Joaquin Valley Air Pollution Control District (SJVAPCD) portion of the California State Implementation Plan (SIP). These revisions were proposed in the Federal Register on December 18, 2009 and concern reduction of animal matter and volatile organic compound (VOC) emissions from crude oil production, cutback asphalt, and petroleum solvent dry cleaning. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  19. 76 FR 26224 - Revisions to the California State Implementation Plan, Northern Sonoma County Air Pollution...

    Science.gov (United States)

    2011-05-06

    ...EPA is proposing to approve revisions to the Northern Sonoma County Air Pollution Control District (NSCAPCD) and Mendocino County Air Quality Management District (MCAQMD) portions of the California State Implementation Plan (SIP). Both districts are required under Part C of title I of the Clean Air Act (CAA) to adopt and implement SIP- approved Prevention of Significant Deterioration (PSD) permit programs. These proposed revisions update the definitions used in the districts' PSD permit programs.

  20. 76 FR 26192 - Revisions to the California State Implementation Plan, Northern Sonoma County Air Pollution...

    Science.gov (United States)

    2011-05-06

    ...EPA is taking direct final action to approve revisions to the Northern Sonoma County Air Pollution Control District (NSCAPCD) and Mendocino County Air Quality Management District (MCAQMD) portions of the California State Implementation Plan (SIP). Both districts are required under Part C of title I of the Clean Air Act (CAA) to adopt and implement SIP-approved Prevention of Significant Deterioration (PSD) permit programs. These revisions update the definitions used in the districts' PSD permit programs.

  1. 77 FR 73392 - Revisions to the California State Implementation Plan, Monterey Bay Unified Air Pollution Control...

    Science.gov (United States)

    2012-12-10

    ...EPA is proposing to approve revisions to the Monterey Bay Unified Air Pollution Control District (MBUAPCD) portion of the California State Implementation Plan (SIP). This revision concerns opacity standards related to multiple pollutants, including particulate matter (PM) emissions from several different types of sources, ranging from fugitive dust to gas turbines. We are proposing to approve a local rule to regulate these emission sources under the Clean Air Act (CAA or the Act).

  2. 76 FR 30025 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2011-05-24

    ...EPA is taking direct final action to approve revisions to the Placer County Air Pollution Control District (PCAPCD) and Ventura County Air Pollution Control District (VCAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from surface coating of metal parts and products. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  3. 76 FR 39303 - Revisions to the California State Implementation Plan, Imperial County Air Pollution Control...

    Science.gov (United States)

    2011-07-06

    ...EPA is taking direct final action to approve revisions to the Imperial County Air Pollution Control District (ICAPCD), Kern County Air Pollution Control District (KCAPCD), and Ventura County Air Pollution Control District (VCAPCD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from architectural coating operations. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  4. Environment, safety, and health regulatory implementation plan

    International Nuclear Information System (INIS)

    1993-01-01

    To identify, document, and maintain the Uranium Mill Tailings Remedial Action (UMTRA) Project's environment, safety, and health (ES ampersand H) regulatory requirements, the US Department of Energy (DOE) UMTRA Project Office tasked the Technical Assistance Contractor (TAC) to develop a regulatory operating envelope for the UMTRA Project. The system selected for managing the UMTRA regulatory operating envelope data bass is based on the Integrated Project Control/Regulatory Compliance System (IPC/RCS) developed by WASTREN, Inc. (WASTREN, 1993). The IPC/RCS is a tool used for identifying regulatory and institutional requirements and indexing them to hardware, personnel, and program systems on a project. The IPC/RCS will be customized for the UMTRA Project surface remedial action and groundwater restoration programs. The purpose of this plan is to establish the process for implementing and maintaining the UMTRA Project's regulatory operating envelope, which involves identifying all applicable regulatory and institutional requirements and determining compliance status. The plan describes how the Project will identify ES ampersand H regulatory requirements, analyze applicability to the UMTRA Project, and evaluate UMTRA Project compliance status

  5. 75 FR 37727 - Disapproval of California State Implementation Plan Revisions, Monterey Bay Unified Air Pollution...

    Science.gov (United States)

    2010-06-30

    ...EPA is finalizing disapproval of a revision to the Monterey Bay Unified Air Pollution Control District (MBUAPCD) portion of the California State Implementation Plan (SIP). This action was proposed in the Federal Register on March 22, 2010. This revision concerns opacity standards related to multiple pollutants, including particulate matter (PM) emissions, from a wide variety of sources. Under authority of the Clean Air Act as amended in 1990 (CAA or the Act), this action identifies a deficiency that precludes approval of this SIP revision.

  6. Containment Emergency Sump Performance. Technical findings related to Unresolved Safety Issue A-43. Revision 1

    International Nuclear Information System (INIS)

    1985-10-01

    This report summarizes key technical findings related to Unresolved Safety Issue (USI) A-43, Containment Emergency Sump Performance. Both BWRs and PWRs are considered in this report. Emergency core cooling systems require a clean, reliable water source to maintain long-term recirculation following a loss-of-coolant accident (LOCA). PWRs rely on the containment emergency sump to provide such a water supply to residual heat removal pumps and containment spray pumps. BWRs rely on pump suction intakes in the suppression pool or wet well to provide water to residual heat removal and core spray systems. Thus, the technical findings in this report provide information on post-LOCA recirculation. These findings have been derived from extensive experimental studies, generic plant studies, and assessments of sumps used for long-term cooling. Results of hydraulic tests have shown that the potential for air ingestion is less severe than previously hypothesized. The effects of debris blockage on NPSH margin must be dealt with on a plant-specific basis. These findings have been used to develop revisions to Regulatory Guide 1.82 and Standard Review Plan Section 6.2.2 (NUREG-0800)

  7. 78 FR 17632 - Caribou-Targhee National Forest; Idaho and Wyoming; Amendment to the Targhee Revised Forest Plan...

    Science.gov (United States)

    2013-03-22

    ...; Amendment to the Targhee Revised Forest Plan--Canada Lynx Habitat AGENCY: Forest Service, USDA. ACTION... Forest proposes to amend the Targhee Revised Forest Plan (1997) to include a map identifying specific... Administrative Review Process: The decision on this proposed plan amendment will be subject to the objection...

  8. Waste minimization and pollution prevention awareness plan. Revision 1

    International Nuclear Information System (INIS)

    1994-07-01

    The purpose of this plan is to document Lawrence Livermore National Laboratory (LLNL) projections for present and future waste minimization and pollution prevention. The plan specifies those activities and methods that are or will be used to reduce the quantity and toxicity of wastes generated at the site. It is intended to satisfy Department of Energy (DOE) requirements. This Waste Minimization and Pollution Prevention Awareness Plan provides an overview of projected activities from FY 1994 through FY 1999. The plans are broken into site-wide and problem-specific activities. All directorates at LLNL have had an opportunity to contribute input, estimate budgets, and review the plan. In addition to the above, this plan records LLNL's goals for pollution prevention, regulatory drivers for those activities, assumptions on which the cost estimates are based, analyses of the strengths of the projects, and the barriers to increasing pollution prevention activities

  9. Revised action plan of the Maintenance division for 1965, Annex 4

    International Nuclear Information System (INIS)

    Nikolic, M.

    1965-01-01

    The action plan presented in this annex is a revised version of the plan adopted in January 1965. It includes tasks of the mechanics, electrical and electronic equipment services. It includes a detailed list of planned and preventive maintenance actions related to the heavy water system, technical water system, helium system, reactor core, transportation equipment, hot cells, heating and ventilation systems in the reactor building, power supply system, auxiliary systems in the RA reactor building [sr

  10. Environmental monitoring plan - environmental monitoring section. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Wilt, G.C. [ed.; Tate, P.J.; Brigdon, S.L. [and others

    1994-11-01

    This report presents the environmental monitoring plan for the Lawrence Livermore National Laboratory. A site characterization is provided along with monitoring and measurement techniques and quality assurance measures.

  11. Quality Assurance Program Plan for FFTF effluent controls. Revision 1

    International Nuclear Information System (INIS)

    Seamans, J.A.

    1995-01-01

    This Quality Assurance Program Plan is specific to environmental related activities within the FFTF Property Protected Area. The activities include effluent monitoring and Low Level Waste Certification

  12. Los Alamos National Laboratory emergency management plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Ramsey, G.F.

    1998-07-15

    The Laboratory has developed this Emergency Management Plan (EMP) to assist in emergency planning, preparedness, and response to anticipated and actual emergencies. The Plan establishes guidance for ensuring safe Laboratory operation, protection of the environment, and safeguarding Department of Energy (DOE) property. Detailed information and specific instructions required by emergency response personnel to implement the EMP are contained in the Emergency Management Plan Implementing Procedure (EMPIP) document, which consists of individual EMPIPs. The EMP and EMPIPs may be used to assist in resolving emergencies including but not limited to fires, high-energy accidents, hazardous material releases (radioactive and nonradioactive), security incidents, transportation accidents, electrical accidents, and natural disasters.

  13. Environmental monitoring plan - environmental monitoring section. Revision 1

    International Nuclear Information System (INIS)

    Wilt, G.C.; Tate, P.J.; Brigdon, S.L.

    1994-11-01

    This report presents the environmental monitoring plan for the Lawrence Livermore National Laboratory. A site characterization is provided along with monitoring and measurement techniques and quality assurance measures

  14. Task Group on Safety Margins Action Plan (SMAP). Safety Margins Action Plan - Final Report

    International Nuclear Information System (INIS)

    Hrehor, Miroslav; Gavrilas, Mirela; Belac, Josef; Sairanen, Risto; Bruna, Giovanni; Reocreux, Michel; Touboul, Francoise; Krzykacz-Hausmann, B.; Park, Jong Seuk; Prosek, Andrej; Hortal, Javier; Sandervaag, Odbjoern; Zimmerman, Martin

    2007-01-01

    The international nuclear community has expressed concern that some changes in existing plants could challenge safety margins while fulfilling all the regulatory requirements. In 1998, NEA published a report by the Committee on Nuclear Regulatory Activities on Future Nuclear Regulatory Challenges. The report recognized 'Safety margins during more exacting operating modes' as a technical issue with potential regulatory impact. Examples of plant changes that can cause such exacting operating modes include power up-rates, life extension or increased fuel burnup. In addition, the community recognized that the cumulative effects of simultaneous changes in a plant could be larger than the accumulation of the individual effects of each change. In response to these concerns, CSNI constituted the safety margins action plan (SMAP) task group with the following objectives: 'To agree on a framework for integrated assessments of the changes to the overall safety of the plant as a result of simultaneous changes in plant operation / condition; To develop a CSNI document which can be used by member countries to assess the effect of plant change on the overall safety of the plant; To share information and experience.' The two approaches to safety analysis, deterministic and probabilistic, use different methods and have been developed mostly independently of each other. This makes it difficult to assure consistency between them. As the trend to use information on risk (where the term risk means results of the PSA/PRA analysis) to support regulatory decisions is growing in many countries, it is necessary to develop a method of evaluating safety margin sufficiency that is applicable to both approaches and, whenever possible, integrated in a consistent way. Chapter 2 elaborates on the traditional view of safety margins and the means by which they are currently treated in deterministic analyses. This chapter also discusses the technical basis for safety limits as they are used today

  15. NIF special equipment construction health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    Sawicki, R.H.

    1997-07-28

    The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES&H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan.

  16. NIF special equipment construction health and safety plan

    International Nuclear Information System (INIS)

    Sawicki, R.H.

    1997-01-01

    The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES ampersand H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan

  17. Nevada National Security Site Integrated Groundwater Sampling Plan, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Marutzky, Sam; Farnham, Irene

    2014-10-01

    The purpose of the Nevada National Security Site (NNSS) Integrated Sampling Plan (referred to herein as the Plan) is to provide a comprehensive, integrated approach for collecting and analyzing groundwater samples to meet the needs and objectives of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) Underground Test Area (UGTA) Activity. Implementation of this Plan will provide high-quality data required by the UGTA Activity for ensuring public protection in an efficient and cost-effective manner. The Plan is designed to ensure compliance with the UGTA Quality Assurance Plan (QAP). The Plan’s scope comprises sample collection and analysis requirements relevant to assessing the extent of groundwater contamination from underground nuclear testing. This Plan identifies locations to be sampled by corrective action unit (CAU) and location type, sampling frequencies, sample collection methodologies, and the constituents to be analyzed. In addition, the Plan defines data collection criteria such as well-purging requirements, detection levels, and accuracy requirements; identifies reporting and data management requirements; and provides a process to ensure coordination between NNSS groundwater sampling programs for sampling of interest to UGTA. This Plan does not address compliance with requirements for wells that supply the NNSS public water system or wells involved in a permitted activity.

  18. Tank 241-BY-103 Tank Characterization Plan. Revision 1

    International Nuclear Information System (INIS)

    Schreiber, R.D.

    1995-01-01

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-103

  19. Tank 241-C-103 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Schreiber, R.D.

    1995-01-01

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from tank 241-C-103

  20. Safety assessment of discharge chute isolation barrier preparation and installation activities. Revision 3

    International Nuclear Information System (INIS)

    Meichle, R.H.

    1994-01-01

    This revision adds a section addressing impacts of dropping surfacing tool and rack cutter on the basin floor, and corrects typographical errors. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparisons of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions was made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classifications

  1. 77 FR 37359 - Revisions to the California State Implementation Plan, South Coast Air Quality Management...

    Science.gov (United States)

    2012-06-21

    ...EPA is proposing to approve revisions to the South Coast Air Quality Management District (SCAQMD) and the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from chipping and grinding activities, and composting operations. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act). We are taking comments on this proposal and plan to follow with a final action.

  2. 77 FR 66429 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-11-05

    ...EPA is proposing to approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compounds (VOC), carbon monoxide (CO), oxides of nitrogen (NOX), oxides of sulfur (SOX), and particulate matter (PM) emissions from glass melting furnaces. We are approving a local rule that regulates these emission sources under the Clean Air Act (CAA or the Act). We are taking comments on this proposal and plan to follow with a final action.

  3. 78 FR 922 - Revisions to the California State Implementation Plan, Imperial County Air Pollution Control...

    Science.gov (United States)

    2013-01-07

    ...EPA is proposing to approve revisions to the Imperial County Air Pollution Control District (ICAPCD) portion of the California Implementation Plan (SIP). These revisions concern local rules that regulate inhalable particulate matter (PM10) emissions from sources of fugitive dust such as unpaved roads and disturbed soils in open and agricultural areas in Imperial County. We are proposing to approve local rules that regulate these emission sources under the Clean Air Act (CAA or the Act). We are taking comments on this proposal and plan to follow with a final action.

  4. 75 FR 13468 - Disapproval of California State Implementation Plan Revisions, Monterey Bay Unified Air Pollution...

    Science.gov (United States)

    2010-03-22

    ...EPA is proposing to disapprove a revision to the Monterey Bay Unified Air Pollution Control District (MBAPCD) portion of the California State Implementation Plan (SIP). This revision concerns opacity standards related to multiple pollutants, including particulate matter (PM) emissions from several different types of sources, ranging from fugitive dust to gas turbine generators. We are proposing action on a local rule that regulates these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act). We are taking comments on this proposal and plan to follow with a final action.

  5. DIII-D tokamak long range plan. Revision 3

    International Nuclear Information System (INIS)

    1992-08-01

    The DIII-D Tokamak Long Range Plan for controlled thermonuclear magnetic fusion research will be carried out with broad national and international participation. The plan covers: (1) operation of the DIII-D tokamak to conduct research experiments to address needs of the US Magnetic Fusion Program; (2) facility modifications to allow these new experiments to be conducted; and (3) collaborations with other laboratories to integrate DIII-D research into the national and international fusion programs. The period covered by this plan is 1 November 19983 through 31 October 1998

  6. 300 Area waste acid treatment system closure plan. Revision 1

    International Nuclear Information System (INIS)

    1996-03-01

    This section provides a description of the Hanford Site, identifies the proposed method of 300 Area Waste Acid Treatment System (WATS) closure, and briefly summarizes the contents of each chapter of this plan

  7. Tank 241-BY-110 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Homi, C.S.

    1995-01-01

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-BY-110

  8. Tank 241-S-107 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Homi, C.S.

    1995-01-01

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-S-107

  9. 242-A Evaporator quality assurance plan. Revision 2

    International Nuclear Information System (INIS)

    Basra, T.S.

    1995-01-01

    The purpose of this quality assurance project plan (Plan) is to provide requirements for activities pertaining to sampling, shipping, and analyses associated with candidate feed tank samples for the 242-A Evaporator project. The purpose of the 242-A Evaporator project is to reduce the volume of aqueous waste in the Double Shell Tank (DST) System and will result in considerable savings to the disposal of mixed waste. The 242-A Evaporator feed stream originates from DSTs identified as candidate feed tanks. The 242-A Evaporator reduces the volume of aqueous waste contained in DSTs by boiling off water and sending the condensate (called process condensate) to the Liquid Effluent Retention Facility (LEPF) storage basin where it is stored prior to treatment in the Effluent Treatment Facility (ETF). The objective of this quality assurance project plan is to provide the planning, implementation, and assessment of sample collection and analysis, data issuance, and validation activities for the candidate feed tanks

  10. Tank 241-AN-102 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Homi, C.S.

    1995-01-01

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-AN-102

  11. Tank 241-U-111 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Homi, C.S.

    1995-01-01

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-U-111

  12. 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

  13. 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.

  14. 300 Area waste acid treatment system closure plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    This section provides a description of the Hanford Site, identifies the proposed method of 300 Area Waste Acid Treatment System (WATS) closure, and briefly summarizes the contents of each chapter of this plan.

  15. Tank 241-B-106 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Homi, C.S.

    1995-01-01

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-B-106

  16. Tank 241-SY-103 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Homi, C.S.

    1995-01-01

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-SY-103

  17. B Plant Complex pollution prevention plan. Revision 1

    International Nuclear Information System (INIS)

    Beam, T.G.

    1994-01-01

    The US Department of Energy (DOE) has directed Westinghouse Hanford Company (WHC) to develop an effective strategy to minimize the generation of hazardous, radioactive, and mixed wastes at Hanford in compliance with state and federal regulations. WHC has formalized a pollution prevention program composed of management policies, management requirements and procedures. This plan addresses pollution prevention for B Plant Complex. A pollution prevention team is in place and has been assigned responsibility for implementing the plan. This plan includes actions and goals for reducing volume and toxicity of waste generated, as well as a basis for evaluation of progress. Descriptions of waste streams, current specific goals, general pollution prevention methods, and specific accomplishments are in the appendices of this plan

  18. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-20

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

  19. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    International Nuclear Information System (INIS)

    1994-01-01

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

  20. Sanitation health risk and safety planning in urban residential ...

    African Journals Online (AJOL)

    The aim of this review paper was to determine the best sanitation health risk and safety planning approach for sustainable management of urban environment. This was achieved by reviewing the concept of sanitation safety planning as a tool. The review adopted exploratory research approach and used secondary data ...

  1. 49 CFR 1106.4 - The Safety Integration Plan process.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 8 2010-10-01 2010-10-01 false The Safety Integration Plan process. 1106.4 Section 1106.4 Transportation Other Regulations Relating to Transportation (Continued) SURFACE... CONSIDERATION OF SAFETY INTEGRATION PLANS IN CASES INVOLVING RAILROAD CONSOLIDATIONS, MERGERS, AND ACQUISITIONS...

  2. Validation and verification plan for safety and PRA codes

    International Nuclear Information System (INIS)

    Ades, M.J.; Crowe, R.D.; Toffer, H.

    1991-04-01

    This report discusses a verification and validation (V ampersand V) plan for computer codes used for safety analysis and probabilistic risk assessment calculations. The present plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River Office (DOE-SRO) to bring the essential safety analysis and probabilistic risk assessment codes in compliance with verification and validation requirements

  3. Plutonium Focus Area research and development plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    The Department of Energy (DOE) committed to a research and development program to support the technology needs for converting and stabilizing its nuclear materials for safe storage. The R and D Plan addresses five of the six material categories from the 94-1 Implementation Plan: plutonium (Pu) solutions, plutonium metals and oxides, plutonium residues, highly enriched uranium, and special isotopes. R and D efforts related to spent nuclear fuel (SNF) stabilization were specifically excluded from this plan. This updated plan has narrowed the focus to more effectively target specific problem areas by incorporating results form trade studies. Specifically, the trade studies involved salt; ash; sand, slag, and crucible (SS and C); combustibles; and scrub alloy. The plan anticipates possible disposition paths for nuclear materials and identifies resulting research requirements. These requirements may change as disposition paths become more certain. Thus, this plan represents a snapshot of the current progress and will continue to be updated on a regular basis. The paper discusses progress in safeguards and security, plutonium stabilization, special isotopes stabilization, highly-enriched uranium stabilization--MSRE remediation project, storage technologies, engineered systems, core technology, and proposed DOE/Russian technology exchange projects.

  4. Plutonium Focus Area research and development plan. Revision 1

    International Nuclear Information System (INIS)

    1996-11-01

    The Department of Energy (DOE) committed to a research and development program to support the technology needs for converting and stabilizing its nuclear materials for safe storage. The R and D Plan addresses five of the six material categories from the 94-1 Implementation Plan: plutonium (Pu) solutions, plutonium metals and oxides, plutonium residues, highly enriched uranium, and special isotopes. R and D efforts related to spent nuclear fuel (SNF) stabilization were specifically excluded from this plan. This updated plan has narrowed the focus to more effectively target specific problem areas by incorporating results form trade studies. Specifically, the trade studies involved salt; ash; sand, slag, and crucible (SS and C); combustibles; and scrub alloy. The plan anticipates possible disposition paths for nuclear materials and identifies resulting research requirements. These requirements may change as disposition paths become more certain. Thus, this plan represents a snapshot of the current progress and will continue to be updated on a regular basis. The paper discusses progress in safeguards and security, plutonium stabilization, special isotopes stabilization, highly-enriched uranium stabilization--MSRE remediation project, storage technologies, engineered systems, core technology, and proposed DOE/Russian technology exchange projects

  5. Monitoring well plugging and abandonment plan, Y-12 Plant, Oak Ridge, Tennessee (revised)

    International Nuclear Information System (INIS)

    1997-05-01

    Plugging and abandonment (P ampersand A) of defunct groundwater monitoring wells is a primary element of the Oak Ridge Y-12 Plant Groundwater Protection Program (GWPP) (AJA Technical Services, Inc. 1996). This document is the revised groundwater monitoring well P ampersand A plan for the U.S. Department of Energy (DOE) Y-12 Plant located in Oak Ridge, Tennessee. This plan describes the systematic approach employed by Y-12 Plant GWPP to identify wells that require P ampersand A, the technical methods employed to perform P ampersand A activities, and administrative requirements. Original documentation for Y-12 Plant GWPP groundwater monitoring well P ampersand A was provided in HSW, Inc. (1991). The original revision of the plan specified that a comprehensive monitoring well P ampersand A was provided in HSW, Inc. (1991). The original revision of the plan specified that a comprehensive monitoring well P ampersand A schedule be maintained. Wells are added to this list by issuance of both a P ampersand A request and a P ampersand A addendum to the schedule. The current Updated Subsurface Data Base includes a single mechanism to track the status of monitoring wells. In addition, rapid growth of the groundwater monitoring network and new regulatory requirements have resulted in constant changes to the status of wells. As a result, a streamlined mechanism to identify and track monitoring wells scheduled for P ampersand A has been developed and the plan revised to formalize the new business practices

  6. Russian Minatom nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    Royen, J.

    1999-01-01

    An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

  7. Safety Standards Plan for Middlesex County Vocational & Technical High Schools.

    Science.gov (United States)

    Sommer, Cy

    This vocational education safety standards plan outlines rules and regulations adopted by the Board of Education of Middlesex County Vocational and Technical High Schools. The first of eleven chapters presents demographics and a safety organization table for Middlesex County Vocational and Technical Schools. In chapter 2, six safety program…

  8. A prioritization of generic safety issues. Supplement 19, Revision insertion instructions

    International Nuclear Information System (INIS)

    1995-11-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. This document provides revisions and amendments to the report

  9. A prioritization of generic safety issues. Supplement 19, Revision insertion instructions

    Energy Technology Data Exchange (ETDEWEB)

    None

    1995-11-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. This document provides revisions and amendments to the report.

  10. Hanford Site Pollution Prevention Plan progress report, 1994. Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    This report tracks progress made during 1994 against the goals stated in DOE/RL-92-62, Executive Summary, Hanford Site Pollution Prevention Plan. The Executive Summary of the plan was submitted to the Washington State Department of Ecology (Ecology) in September 1992. The plan, Executive Summary, and the progress reports are elements of a pollution prevention planning program that is required by WAC 173-307, ''Plans,'' for all hazardous substance users and/or all hazardous waste generators regulated by Ecology. These regulations implement RCW 70.95C, ''Waste Reduction,'' an act relating to hazardous waste reduction. The act encourages voluntary efforts to redesign industrial processes to help reduce or eliminate hazardous substances and hazardous waste byproducts, and to maximize the in-process reuse or reclamation of valuable spent material. The Hanford Site is voluntarily complying with this state regulatory-mandated program. All treatment, storage, or disposal (TSD) facilities are exempt from participating; the Hanford Site is classified as a TSD

  11. ORCWM test and evaluaton master plan. Revision 00

    International Nuclear Information System (INIS)

    1995-08-01

    The Office of Civilian Radioactive Waste Management (OCRWM) Test and Evaluation Master Plan (TEMP) describes the program Test and Evaluation (T ampersand E) policy, objectives, requirements, general methodology (test flow and description of each T ampersand E phase), responsibilities, and scheduling of test phases for the Civilian Radioactive Waste Management System (CRWMS). This TEMP is a program-level management planning document for al CRWMS T ampersand E activities and will be used in conjunction with Section 11 of the Quality Assurance Requirements and Description (QARD), as appropriate, as a guide for the projects in developing their T ampersand E plans. In the OCRWM document hierarchy, that is described in the OCRWM Systems Engineering Management Plan (SEMP), the TEMP is subordinate to the program SEMP. To ensure CRWMS operates as an integrated system, the plans for verifying the performance and evaluating the operational suitability and effectiveness of the overall system are also described. Test and evaluation is an integral part of the systems engineering process. Key aspects of the systems engineering process, more fully described in the OCRWM SEMP, are discussed in this TEMP to illustrate how T ampersand E supports the overall systems engineering process

  12. Hanford Site Pollution Prevention Plan progress report, 1994. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This report tracks progress made during 1994 against the goals stated in DOE/RL-92-62, Executive Summary, Hanford Site Pollution Prevention Plan. The Executive Summary of the plan was submitted to the Washington State Department of Ecology (Ecology) in September 1992. The plan, Executive Summary, and the progress reports are elements of a pollution prevention planning program that is required by WAC 173-307, ``Plans,`` for all hazardous substance users and/or all hazardous waste generators regulated by Ecology. These regulations implement RCW 70.95C, ``Waste Reduction,`` an act relating to hazardous waste reduction. The act encourages voluntary efforts to redesign industrial processes to help reduce or eliminate hazardous substances and hazardous waste byproducts, and to maximize the in-process reuse or reclamation of valuable spent material. The Hanford Site is voluntarily complying with this state regulatory-mandated program. All treatment, storage, or disposal (TSD) facilities are exempt from participating; the Hanford Site is classified as a TSD.

  13. The Norwegian Plan of Action for nuclear safety issues

    International Nuclear Information System (INIS)

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects

  14. The Norwegian Plan of Action for nuclear safety issues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects.

  15. Hawaii State Plan for Occupational Safety and Health. Final rule.

    Science.gov (United States)

    2012-09-21

    This document announces the Occupational Safety and Health Administration's (OSHA) decision to modify the Hawaii State Plan's ``final approval'' determination under Section 18(e) of the Occupational Safety and Health Act (the Act) and to transition to ``initial approval'' status. OSHA is reinstating concurrent federal enforcement authority over occupational safety and health issues in the private sector, which have been solely covered by the Hawaii State Plan since 1984.

  16. Maintenance implementation plan for T Plant. Revision 2

    International Nuclear Information System (INIS)

    Ayers, W.S.

    1995-05-01

    This document is a Maintenance Implementation Plan (MIP) for the T Plant Facility complex located in the 200 West Area of the Hanford Reservation in Washington state. This plan has been developed to provide a disciplined approach to maintenance functions and to describe how the T Plant facility will implement and comply with the regulations according to US DOE order 4330.4B, entitled Maintenance Management Program, Chapter 2.0 open-quotes Nuclear Facilitiesclose quotes. Physical structures, systems, processes, as well as all associated equipment specifically assigned to these groups are included in the MIP

  17. Nevada National Security Site Integrated Groundwater Sampling Plan, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Farnham, Irene

    2018-03-01

    The purpose is to provide a comprehensive, integrated approach for collecting and analyzing groundwater samples to meet the needs and objectives of the DOE/EM Nevada Program’s UGTA Activity. Implementation of this Plan will provide high-quality data required by the UGTA Activity for ensuring public protection in an efficient and cost-effective manner. The Plan is designed to ensure compliance with the UGTA Quality Assurance Plan (QAP) (NNSA/NFO, 2015); Federal Facility Agreement and Consent Order (FFACO) (1996, as amended); and DOE Order 458.1, Radiation Protection of the Public and the Environment (DOE, 2013). The Plan’s scope comprises sample collection and analysis requirements relevant to assessing both the extent of groundwater contamination from underground nuclear testing and impact of testing on water quality in downgradient communities. This Plan identifies locations to be sampled by CAU and location type, sampling frequencies, sample collection methodologies, and the constituents to be analyzed. In addition, the Plan defines data collection criteria such as well purging, detection levels, and accuracy requirements/recommendations; identifies reporting and data management requirements; and provides a process to ensure coordination between NNSS groundwater sampling programs for sampling analytes of interest to UGTA. Information used in the Plan development—including the rationale for selection of wells, sampling frequency, and the analytical suite—is discussed under separate cover (N-I, 2014) and is not reproduced herein. This Plan does not address compliance for those wells involved in a permitted activity. Sampling and analysis requirements associated with these wells are described in their respective permits and are discussed in NNSS environmental reports (see Section 5.2). In addition, sampling for UGTA CAUs that are in the Closure Report (CR) stage are not included in this Plan. Sampling requirements for these CAUs are described in the CR

  18. OCRWM [Office of Civilian Radioactive Waste Management] Safety Plan

    International Nuclear Information System (INIS)

    1986-12-01

    The OCRWM Safety Plan sets forth management policies and general requirements for the safety of the public and of personnel associated with the Civilian Radioactive Waste Management Program (hereinafter called the ''Program''). It is applicable to all individuals and organizational elements of the Program, including all facilities and activities controlled by the Program pursuant to the Act, and to all phases of the Program. The plan defines the responsibilities assigned by the Director of the OCRWM to the various OCRWM line organizations, and to the contractors and the projects. It discusses the means by which safety policies and requirements will be communicated, and summarizes the applicable DOE Orders, and the procedures for reviewing, reporting, and evaluating safety problems. In addition, the OCRWM Safety Plan addresses DOE Orders applicable to occupational health and safety, worker protection, and public health and safety. OCRWM believes that it has an equally high level of commitment to both public safety and worker safety. The Plan also summarizes applicable NRC criteria and regulations that will be imposed through the formal licensing proceedings. While the Safety Plan sets forth OCRWM policy, it is not intended to be prescriptive in the details of implementation. Each OCRWM program element must develop and control its own set of detailed requirements for the protection of its workers and the public based on the principles set forth herein

  19. Affirmative Action Plans, January 1, 1994--December 31, 1994. Revision

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-16

    This document is the Affirmative Action Plan for January 1, 1994 through December 31, 1994 for the Lawrence Berkeley Laboratory, University of California (``LBL`` or ``the Laboratory.``) This is an official document that will be presented upon request to the Office of Federal Contract Compliance Programs, US Department of Labor. The plan is prepared in accordance with the Executive Order 11246 and 41 CFR Section 60-1 et seq. covering equal employment opportunity and will be updated during the year, if appropriate. Analyses included in this volume as required by government regulations are based on statistical comparisons. All statistical comparisons involve the use of geographic areas and various sources of statistics. The geographic areas and sources of statistics used here are in compliance with the government regulations, as interpreted. The use of any geographic area or statistic does not indicate agreement that the geographic area is the most appropriate or that the statistic is the most relevant. The use of such geographic areas and statistics is intended to have no significance outside the context of this Affirmative Action Plan, although, of course, such statistics and geographic areas will be used in good faith with respect to this Affirmative Action Plan.

  20. 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…

  1. 222-S Laboratory Quality Assurance Plan. Revision 1

    International Nuclear Information System (INIS)

    Meznarich, H.K.

    1995-01-01

    This Quality Assurance Plan provides,quality assurance (QA) guidance, regulatory QA requirements (e.g., 10 CFR 830.120), and quality control (QC) specifications for analytical service. This document follows the U.S Department of Energy (DOE) issued Hanford Analytical Services Quality Assurance Plan (HASQAP). In addition, this document meets the objectives of the Quality Assurance Program provided in the WHC-CM-4-2, Section 2.1. Quality assurance elements required in the Guidelines and Specifications for Preparing Quality Assurance Program Plans (QAMS-004) and Interim Guidelines and Specifications for Preparing Quality Assurance Project Plans (QAMS-005) from the US Environmental Protection Agency (EPA) are covered throughout this document. A quality assurance index is provided in the Appendix A. This document also provides and/or identifies the procedural information that governs laboratory operations. The personnel of the 222-S Laboratory and the Standards Laboratory including managers, analysts, QA/QC staff, auditors, and support staff shall use this document as guidance and instructions for their operational and quality assurance activities. Other organizations that conduct activities described in this document for the 222-S Laboratory shall follow this QA/QC document

  2. Automated Procurement System (APS) revised project management plan (DS-03)

    Science.gov (United States)

    Murphy, Diane R.

    1995-01-01

    The Project Plan is the governing document for the implementation of the Automated Procurement System (APS). It includes a description of the proposed system, describes the work to be done, establishes a schedule of deliverables, and discusses the major standards and procedures to be followed.

  3. 242-A evaporator quality assurance project plan: Revision 1

    International Nuclear Information System (INIS)

    Tucker, B.J.

    1994-01-01

    The scope of this quality assurance project plan (Plan) is sampling and analytical services including, but not limited to, sample receipt, handling and storage, analytical measurements, submittal of data deliverables, archiving selected portions of samples, returning unneeded sample material to Westinghouse Hanford Company (WHC), and/or sample disposal associated with candidate feed samples and process condensate compliance samples. Sampling and shipping activities are also included within the scope. The purpose of this project is to provide planning, implementation, and assessment guidance for achieving established data quality objectives measurement parameters. This Plan requires onsite and offsite laboratories to conform to that guidance. Laboratory conformance will help ensure that quality data are being generated and therefore, that the 242-A evaporator is operating in a safe and compliant manner. The 242-A evaporator feed stream originates from double-shell tanks (DSTs) identified as candidate feed tanks. The 242-A evaporator reduces the volume of aqueous waste contained in DSTs by boiling off water and sending it to the Liquid Effluent Retention Facility (LERF) storage basin before further treatment. The slurry product is returned to DSTs. Evaporation results in considerable savings by reducing the volume of mixed waste for disposal

  4. Human Research Program Integrated Research Plan. Revision A January 2009

    Science.gov (United States)

    2009-01-01

    The Integrated Research Plan (IRP) describes the portfolio of Human Research Program (HRP) research and technology tasks. The IRP is the HRP strategic and tactical plan for research necessary to meet HRP requirements. The need to produce an IRP is established in HRP-47052, Human Research Program - Program Plan, and is under configuration management control of the Human Research Program Control Board (HRPCB). Crew health and performance is critical to successful human exploration beyond low Earth orbit. The Human Research Program (HRP) is essential to enabling extended periods of space exploration because it provides knowledge and tools to mitigate risks to human health and performance. Risks include physiological and behavioral effects from radiation and hypogravity environments, as well as unique challenges in medical support, human factors, and behavioral or psychological factors. The Human Research Program (HRP) delivers human health and performance countermeasures, knowledge, technologies and tools to enable safe, reliable, and productive human space exploration. Without HRP results, NASA will face unknown and unacceptable risks for mission success and post-mission crew health. This Integrated Research Plan (IRP) describes HRP s approach and research activities that are intended to address the needs of human space exploration and serve HRP customers and how they are integrated to provide a risk mitigation tool. The scope of the IRP is limited to the activities that can be conducted with the resources available to the HRP; it does not contain activities that would be performed if additional resources were available. The timescale of human space exploration is envisioned to take many decades. The IRP illustrates the program s research plan through the timescale of early lunar missions of extended duration.

  5. 75 FR 1715 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2010-01-13

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVAPCD) portion of the...)(2)). List of Subjects in 40 CFR Part 52 Environmental protection, Air pollution control...

  6. 77 FR 22676 - Revisions to the Arizona State Implementation Plan, Pinal County Air Quality Control District

    Science.gov (United States)

    2012-04-17

    ... the Arizona State Implementation Plan, Pinal County Air Quality Control District AGENCY: Environmental... disapproval of a revision to the Pinal County Air Quality Control District portion of the Arizona State... the Control Officer to determine whether the manner of control of fugitive emissions is satisfactory...

  7. 75 FR 8008 - Revisions to the California State Implementation Plan, Imperial County Air Pollution Control...

    Science.gov (United States)

    2010-02-23

    ... the California State Implementation Plan, Imperial County Air Pollution Control District AGENCY... limited disapproval of revisions to the Imperial County Air Pollution Control District (ICAPCD) portion of... soils in open and agricultural areas. We are proposing action on local rules that regulate these...

  8. 75 FR 21221 - Plan Revision for Kaibab National Forest; Coconino, Yavapai, and Mojave Counties; AZ

    Science.gov (United States)

    2010-04-23

    ..., including the identification of management indicator species (MIS). It may also make new special area... identification of the types of decisions that will not be made within the revised forest plan. The authorization... characteristics such as spacing tree groups and tree density; and disturbance patterns such as frequency, severity...

  9. 75 FR 15648 - Approval and Promulgation of Air Quality Implementation Plans; Texas; Revisions to the Discrete...

    Science.gov (United States)

    2010-03-30

    ... Promulgation of Air Quality Implementation Plans; Texas; Revisions to the Discrete Emission Credit Banking and... Air Quality Rules, Subchapter H--Emissions Banking and Trading, Division 4--Discrete Emission Credit Banking and Trading, referred to elsewhere in this notice as the Discrete Emission Reduction Credit (DERC...

  10. 75 FR 27644 - Approval and Promulgation of Air Quality Implementation Plans; Texas; Revisions to the Discrete...

    Science.gov (United States)

    2010-05-18

    ... Promulgation of Air Quality Implementation Plans; Texas; Revisions to the Discrete Emission Credit Banking and... Rules, Subchapter H--Emissions Banking and Trading, Division 4--Discrete Emission Credit Banking and Trading, referred to elsewhere in this notice as the Discrete Emission Reduction Credit (DERC) Program...

  11. 75 FR 15645 - Approval and Promulgation of Air Quality Implementation Plans; Texas; Revisions to the Emission...

    Science.gov (United States)

    2010-03-30

    ... clarify EPA's role in the approval of emission quantification protocols. While the previous SIP- approved... approve severable portions of two revisions to the Texas State Implementation Plan (SIP) submitted by the... to further clarify procedures for using emission protocols and to update the approved list of...

  12. 75 FR 69910 - Revisions to the California State Implementation Plan, California Air Resources Board-Consumer...

    Science.gov (United States)

    2010-11-16

    ...'s national Consumer Products rule. The TSD has more information on our evaluation. C. Public Comment... the California State Implementation Plan, California Air Resources Board--Consumer Products AGENCY... revisions concern volatile organic compound (VOC) emissions from consumer products. We are approving a local...

  13. 76 FR 62004 - Revisions to the California State Implementation Plan, California Air Resources Board-Consumer...

    Science.gov (United States)

    2011-10-06

    ... Organic Compound Emission Standards for Consumer Products. B. Does the rule meet the evaluation criteria... the California State Implementation Plan, California Air Resources Board--Consumer Products AGENCY... revisions concern volatile organic compound (VOC) emissions from consumer products. We are approving a local...

  14. 76 FR 56132 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-09-12

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of... did the State submit? B. Are there other versions of this rule? C. What is the purpose of the...

  15. 12 CFR 702.306 - Revised business plans for new credit unions.

    Science.gov (United States)

    2010-01-01

    ... exposure to risk (including credit risk, interest-rate risk, and other types of risk). (d) Consideration of... 12 Banks and Banking 6 2010-01-01 2010-01-01 false Revised business plans for new credit unions. 702.306 Section 702.306 Banks and Banking NATIONAL CREDIT UNION ADMINISTRATION REGULATIONS AFFECTING...

  16. 75 FR 15348 - Approval and Promulgation of Air Quality Implementation Plans; Texas; Revision To Control...

    Science.gov (United States)

    2010-03-29

    ... to control volatile organic compound (VOC) emissions from storage tanks, transport vessels and marine... Promulgation of Air Quality Implementation Plans; Texas; Revision To Control Volatile Organic Compound..., Division 1 (Storage of Volatile Organic Compounds) and Subchapter F, Division 3 (Degassing or Cleaning of...

  17. 76 FR 29153 - Revisions to the California State Implementation Plan, Mojave Desert Air Quality Management District

    Science.gov (United States)

    2011-05-20

    ... the California State Implementation Plan, Mojave Desert Air Quality Management District AGENCY... approve revisions to the Mojave Desert Air Quality Management District (MDAQMD) portion of the California... approving with the dates that they were adopted by the Mojave Desert Air Quality Management District (MDAQMD...

  18. 78 FR 58459 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2013-09-24

    ... the California State Implementation Plan, Antelope Valley Air Quality Management District, Santa Barbara County Air Pollution Control District, South Coast Air Quality Management District and Ventura.... SUMMARY: EPA is finalizing approval of revisions to the Antelope Valley Air Quality Management District...

  19. 76 FR 41744 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2011-07-15

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2011-0537; FRL-9432-1] Revisions to the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District (SCAQMD) portion of the California State...

  20. 76 FR 29182 - Revisions to the California State Implementation Plan, Mojave Desert Air Quality Management District

    Science.gov (United States)

    2011-05-20

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2011-0030; FRL-9308-4] Revisions to the California State Implementation Plan, Mojave Desert Air Quality Management District AGENCY... the Mojave Desert Air Quality Management District (MDAQMD) portion of the California State...

  1. 76 FR 40303 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2011-07-08

    ... the California State Implementation Plan, South Coast Air Quality Management District AGENCY... limited disapproval of revisions to the South Coast Air Quality Management District (SCAQMD) portion of... designated nonattainment for the fine particulate matter (PM2.5) National Ambient Air Quality Standards...

  2. 75 FR 32293 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2010-06-08

    ... the California State Implementation Plan, South Coast Air Quality Management District AGENCY... approve revisions to the South Coast Air Quality Management District (SCAQMD) portion of the California... submit regulations that control the primary and secondary National Ambient Air Quality Standards (NAAQS...

  3. 75 FR 46880 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2010-08-04

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2010-0503; FRL-9183-5] Revisions to the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District (SCAQMD) portion of the California State...

  4. 76 FR 78871 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2011-12-20

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2011-0897; FRL-9499-8] Revisions to the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District (SCAQMD) portion of the California State...

  5. 76 FR 78829 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2011-12-20

    ... the California State Implementation Plan, South Coast Air Quality Management District AGENCY... approve a revision to the South Coast Air Quality Management District (SCAQMD) portion of the California... Reference (A) South Coast Air Quality Management District (1) Rule 2005, ``New Source Review for RECLAIM...

  6. 78 FR 56639 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2013-09-13

    ...] Revisions to the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District (SCAQMD) portion of the California State... the Office of Management and Budget under Executive Order 12866 (58 FR 51735, October 4, 1993); does...

  7. 76 FR 38589 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2011-07-01

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2011-0383; FRL-9428-1] Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management District AGENCY... the Antelope Valley Air Quality Management District (AVAQMD) portion of the California State...

  8. 76 FR 47074 - Revision to the California State Implementation Plan; South Coast Air Quality Management District

    Science.gov (United States)

    2011-08-04

    ... California State Implementation Plan; South Coast Air Quality Management District AGENCY: Environmental... revision to the South Coast Air Quality Management District portion of the California State Implementation... Submittal A. What rule did the State submit? We are approving South Coast Air Quality Management District...

  9. 78 FR 18853 - Revision to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2013-03-28

    ... California State Implementation Plan, South Coast Air Quality Management District AGENCY: Environmental... revision to the South Coast Air Quality Management District (SCAQMD) portion of the California State...) * * * (411) * * * (i) * * * (F) South Coast Air Quality Management District. (1) Rule 463, ``Organic Liquid...

  10. 77 FR 11990 - Revisions to the California State Implementation Plan, Mojave Desert Air Quality Management...

    Science.gov (United States)

    2012-02-28

    ... the California State Implementation Plan, Mojave Desert Air Quality Management District and Yolo-Solano Air Quality Management District AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: EPA is proposing to approve revisions to the Mojave Desert Air Quality Management...

  11. 76 FR 38572 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2011-07-01

    ... the California State Implementation Plan, Antelope Valley Air Quality Management District AGENCY... approve revisions to the Antelope Valley Air Quality Management District (AVAQMD) portion of the... approving with the dates that they were adopted by the Antelope Valley Air Quality Management District...

  12. 78 FR 49925 - Revisions to California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2013-08-16

    ... California State Implementation Plan, Antelope Valley Air Quality Management District and Ventura County Air...: EPA is taking direct final action to approve revisions to the Antelope Valley Air Quality Air Management District (AVAQMD) and Ventura County Air Pollution Control District (VCAPCD) portions of the...

  13. 75 FR 25798 - Revisions to the California State Implementation Plan, Yolo Solano Air Quality Management District

    Science.gov (United States)

    2010-05-10

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2010-0286; FRL-9138-7] Revisions to the California State Implementation Plan, Yolo Solano Air Quality Management District AGENCY... the Yolo-Solano Air Quality Management District (YSAQMD) portion of the California State...

  14. 77 FR 12493 - Revisions to the California State Implementation Plan, Feather River Air Quality Management District

    Science.gov (United States)

    2012-03-01

    ... the California State Implementation Plan, Feather River Air Quality Management District AGENCY... limited disapproval of revisions to the Feather River Air Quality Management District (FRAQMD) portion of.... * * * * * (c) * * * (378) * * * (i) * * * (E) Feather River Air Quality Management District. (1) Rule 3.22...

  15. 76 FR 41717 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2011-07-15

    ... the California State Implementation Plan, South Coast Air Quality Management District AGENCY... approve revisions to the South Coast Air Quality Management District (SCAQMD) portion of the California... Governor's Designee. (i) Incorporation by reference. (A) South Coast Air Quality Management District. (1...

  16. 77 FR 32398 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2012-06-01

    ... the California State Implementation Plan, South Coast Air Quality Management District AGENCY... approve a revision to the South Coast Air Quality Management District (SCAQMD) portion of the California... action: Is not a ``significant regulatory action'' subject to review by the Office of Management and...

  17. 78 FR 59249 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2013-09-26

    ...] Revisions to the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District (SCAQMD) portion of the California State...'s Designee. (i) Incorporation by Reference. (A) South Coast Air Quality Management District. (1...

  18. 75 FR 46845 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2010-08-04

    ... the California State Implementation Plan, South Coast Air Quality Management District AGENCY... approve revisions to the South Coast Air Quality Management District (SCAQMD) portion of the California..., this action: Is not a ``significant regulatory action'' subject to review by the Office of Management...

  19. 77 FR 53773 - Revisions to the California State Implementation Plan, South Coast Air Quality Management...

    Science.gov (United States)

    2012-09-04

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0236; FRL-9711-2] Revisions to the California State Implementation Plan, South Coast Air Quality Management District (SCAQMD) AGENCY... ``significant regulatory action'' subject to review by the Office of Management and Budget under Executive Order...

  20. 78 FR 25011 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2013-04-29

    ... the California State Implementation Plan, Antelope Valley Air Quality Management District, Santa Barbara County Air Pollution Control District, South Coast Air Quality Management District and Ventura... rule. SUMMARY: EPA is proposing to approve revisions to the Antelope Valley Air Quality Management...

  1. 77 FR 11992 - Revisions to the California State Implementation Plan, Mojave Desert Air Quality Management District

    Science.gov (United States)

    2012-02-28

    ... the California State Implementation Plan, Mojave Desert Air Quality Management District AGENCY... limited disapproval of revisions to the Mojave Desert Air Quality Management District (MDAQMD) portion of...,'' Northeast States for Coordinated Air Use Management, December 2000. B. Does the rule meet the evaluation...

  2. 77 FR 58076 - Revisions to the California State Implementation Plan, South Coast Air Quality Management District

    Science.gov (United States)

    2012-09-19

    ... the California State Implementation Plan, South Coast Air Quality Management District AGENCY... the South Coast Air Quality Management District (SCAQMD) portion of the California State... Quality Standards (NAAQS). The revisions to the primary and secondary Lead NAAQS were to provide increased...

  3. 76 FR 68638 - Approval and Promulgation of Air Quality Implementation Plans; Virginia; Revision to Nitrogen...

    Science.gov (United States)

    2011-11-07

    ... Promulgation of Air Quality Implementation Plans; Virginia; Revision to Nitrogen Oxides Budget Trading Program... pertains to regulatory language in its nitrogen oxides (NO X ) Budget Trading Program that inadvertently..., Nitrogen dioxide, Ozone, Sulfur oxides. Dated: October 25, 2011. W.C. Early, Acting Regional Administrator...

  4. 77 FR 214 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-01-04

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approval of revisions to the San Joaquin Valley Air Pollution Control District (SJVUAPCD) portion of the... used by the California Air Resources Board and air districts for evaluating air pollution control...

  5. 77 FR 745 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-01-06

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2011-0547; FRL-9480-1] Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) Correction In rule document 2011-33660 appearing on pages 214-217 in the issue of Wednesday, January 4, 2012, make the following corrections...

  6. 76 FR 31242 - Revisions to the California State Implementation Plan, Santa Barbara County Air Pollution Control...

    Science.gov (United States)

    2011-05-31

    ... the California State Implementation Plan, Santa Barbara County Air Pollution Control District AGENCY... limited disapproval of revisions to the Santa Barbara County Air Pollution Control District (SBCAPCD... BTU/hr and internal combustion engines with a rated brake horse power of 50 or greater. Under...

  7. 76 FR 40237 - Approval and Disapproval and Promulgation of Air Quality Implementation Plans; Montana; Revisions...

    Science.gov (United States)

    2011-07-08

    ... words EPA, we, us or our mean or refer to the United States Environmental Protection Agency. (iii) The... no federal requirement for minor source BACT. To the extent the commenter makes this argument, EPA... Disapproval and Promulgation of Air Quality Implementation Plans; Montana; Revisions to the Administrative...

  8. 76 FR 59338 - Approval and Promulgation of Air Quality Implementation Plans; Montana; Revisions to the...

    Science.gov (United States)

    2011-09-26

    ... to other minor administrative changes to the Administrative Rules of Montana. The intended effect of... words EPA, we, us or our mean or refer to the United States Environmental Protection Agency. (iii) The... Promulgation of Air Quality Implementation Plans; Montana; Revisions to the Administrative Rules of Montana...

  9. 75 FR 3993 - Approval and Promulgation of Air Quality Implementation Plans; Montana; Revisions to the...

    Science.gov (United States)

    2010-01-26

    ... include minor editorial and grammatical changes, updates to the citations and references to federal and... otherwise. (ii) The words EPA, we, us or our mean or refer to the United States Environmental Protection... Promulgation of Air Quality Implementation Plans; Montana; Revisions to the Administrative Rules of Montana...

  10. 78 FR 29032 - Approval and Promulgation of Implementation Plans Tennessee: Revisions to Volatile Organic...

    Science.gov (United States)

    2013-05-17

    ... of the term ``particulate matter emissions'' at 1200-03-09-.01(4)(b)47 (vi) as part of the definition... Promulgation of Implementation Plans Tennessee: Revisions to Volatile Organic Compound Definition AGENCY..., 1999, SIP adds 17 compounds to the list of compounds excluded from the definition of ``Volatile Organic...

  11. 76 FR 56134 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-09-12

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of... preempt Tribal law. List of Subjects in 40 CFR Part 52 Environmental protection, Air pollution control...

  12. 75 FR 60623 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2010-10-01

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approval and limited disapproval of revisions to the San Joaquin Valley Unified Air Pollution Control... 30, 2008) \\2\\; and Ventura County Air Pollution Control District (VCAPCD) Rule 74.15 (as amended...

  13. 75 FR 57862 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2010-09-23

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the... section 307(b)(2)). List of Subjects in 40 CFR Part 52 Environmental protection, Air pollution control...

  14. 76 FR 69135 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-11-08

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the... of Subjects in 40 CFR Part 52 Environmental protection, Air pollution control, Incorporation by...

  15. 76 FR 56706 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-09-14

    ... the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... approve revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of... of Subjects in 40 CFR Part 52 Environmental protection, Air pollution control, Intergovernmental...

  16. 76 FR 35167 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-06-16

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2011-0312; FRL-9319-8] Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution Control District... Subjects in 40 CFR Part 52 Environmental protection, Air pollution control, Intergovernmental relations...

  17. Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1

    International Nuclear Information System (INIS)

    Schlosser, R.L.

    1996-01-01

    This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade

  18. 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

  19. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Downey, N.J.

    1994-12-14

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User`s Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered.

  20. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    International Nuclear Information System (INIS)

    Downey, N.J.

    1994-01-01

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User's Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered

  1. PUREX Storage Tunnels waste analysis plan. Revision 1

    International Nuclear Information System (INIS)

    Stephenson, M.J.

    1995-11-01

    Washington Administrative Code 173-303-300 requires that a facility develop and follow a written waste analysis plan which describes the procedures that will be followed to ensure that its dangerous waste is managed properly. This document covers the activities at the PUREX Storage Tunnels used to characterize and designate waste that is generated within the PUREX Plant, as well as waste received from other on-site sources

  2. Automated Transportation Management System (ATMS) Configuration Management Plan. Revision 1

    International Nuclear Information System (INIS)

    Weidert, R.S.

    1994-01-01

    This document describes the Software Configuration Management (SCM) approach and procedures to be utilized in developing and maintaining the Automated Transportation Management System (ATMS). The configuration management procedures are necessary to ensure that any changes made to software and related documentation are consistent with ATMS goals and contained securely in a central library. This plan applies to all software and associated documentation used in producing ATMS V1.0 and ATMS V2.0 system

  3. Research on the Evaluation System for Rural Public Safety Planning

    Institute of Scientific and Technical Information of China (English)

    Ming; SUN; Jianxin; YAN

    2014-01-01

    The indicator evaluation system is introduced to the study of rural public safety planning in this article.By researching the current rural public safety planning and environmental carrying capacity,we select some carrying capacity indicators influencing the rural public safety,such as land,population,ecological environment,water resources,infrastructure,economy and society,to establish the environmental carrying capacity indicator system.We standardize the indicators,use gray correlation analysis method to determine the weight of indicators,and make DEA evaluation of the indicator system,to obtain the evaluation results as the basis for decision making in rural safety planning,and provide scientific and quantified technical support for rural public safety planning.

  4. Remedial action work plan for the Colonie site. Revision 1

    International Nuclear Information System (INIS)

    1985-08-01

    The Colonie site is a DOE Formerly Utilized Sites Remedial Action Program (FUSRAP) site located in the Town of Colonie, New York, and consisting of an interim storage site and several vicinity properties. The Colonie Interim Storage Site (CISS) is the former National Lead (NL) Industries plant located at 1130 Central Avenue. There are 11 vicinity properties that received remedial action in 1984: 7 located south of the site on Yardboro and Palmer Avenues just across the Colonie-Albany town limits in Albany, and 4 located northwest of the site along Central Avenue in Colonie. Of these properties, nine are residences and two are commercial properties. This document describes the engineering design, construction, and associated plans for remedial action on the vicinity properties and the interim storage site. These plans include both radiological and chemical work. Radiological work includes: excavating the above-guideline radioactive wastes on the vicinity properties; designing required facilities for the interim storage site; preparing the interim storage site to receive these contaminated materials; transporting the contaminated materials to the interim waste storage stockpile; and preparing necessary schedules for accomplishing the remedial actions. Chemical work involves: developing the Resource Conservation and Recovery Act (RCRA) closure plans; neutralizing chemical hazards associated with plating solutions; inventorying on-site chemicals; and disposal of chemicals and/or residues. 17 refs., 5 figs., 1 tab

  5. Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1

    International Nuclear Information System (INIS)

    Dukelow, G.T.; Hanson, G.A.

    1995-05-01

    The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies

  6. Nuclear power plant severe accident research plan. Revision 1

    International Nuclear Information System (INIS)

    Marino, G.P.

    1986-04-01

    Subsequent to the Three Mile Island Unit 2 accident, recommendations were made by a number of review committees to consider regulatory changes which would provide better protection of the public from severe accidents. Over the past six years a major research effort has been underway by the NRC to develop an improved understanding of severe accidents and to provide a technical basis to support regulatory decisions. The purpose of this report is to describe current plans for the completion and extension of this research in support of ongoing regulatory actions in this area

  7. LANDSAT-D ground segment operations plan, revision A

    Science.gov (United States)

    Evans, B.

    1982-01-01

    The basic concept for the utilization of LANDSAT ground processing resources is described. Only the steady state activities that support normal ground processing are addressed. This ground segment operations plan covers all processing of the multispectral scanner and the processing of thematic mapper through data acquisition and payload correction data generation for the LANDSAT 4 mission. The capabilities embedded in the hardware and software elements are presented from an operations viewpoint. The personnel assignments associated with each functional process and the mechanisms available for controlling the overall data flow are identified.

  8. Public involvement plan for the Oak Ridge Reservation. Revision 1

    International Nuclear Information System (INIS)

    1995-03-01

    For the past few years, the Department of Energy (DOE) has increased its efforts to involve the public in environmental management decisions. On the national level, Energy Secretary Hazel O'Leary has declared public involvement one of DOE's most important objectives. On the local level, citizens are taking the microphone at DOE public hearings to voice their opinions and ask tough, detailed questions about proposed cleanup plans. To ensure that it hears, understands and responds to public input from all of its neighbors, DOE-Oak Ridge Operations has developed an Environmental Management Public Involvement Program to keep stakeholders--those affected or potentially affected by cleanup programs--informed about environmental management work on the Oak Ridge Reservation and opportunities for public comment. This Public Involvement Plan contains information about the Oak Ridge Public Involvement Program its history, goals and proposed interactions with stakeholders. It also contains information to help area citizens become involved or increase their involvement in helping DOE make responsible environmental management decisions

  9. Tank waste remediation system integrated technology plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P. [eds.] [Pacific Northwest Lab., Richland, WA (United States)

    1995-02-28

    The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m{sup 3} (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program.

  10. Tank waste remediation system integrated technology plan. Revision 2

    International Nuclear Information System (INIS)

    Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P.

    1995-01-01

    The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m 3 (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program

  11. Socioeconomic monitoring and mitigation plan for site characterization: Revision 1

    International Nuclear Information System (INIS)

    1988-01-01

    The objective of the SMMP is to document compliance with the NWPA. In order to do so, a summary description of site characterization activities based on the consultation draft of the Site Characterization Plan and the final EA is provided. Subsequent chapters identify issues related to the potential for significant adverse impacts and the monitoring plans proposed to determine whether those impacts occur. Should monitoring confirm the potential for significant adverse impact, mitigative maesures will be developed. In the context of site characterization, mitigation is defined as those changes in site characterization activities that serve to avoid or minimize, to the maximum extent practicable, any significant adverse environmental impacts. Proposed site characterization activites involve a variety of surface and subsurface activities including site preparation, access road construction and improvment, exploratory drilling and testing, geophysical surveys, geological mapping, and construction of the exploratory shaft facility. It is not anticipated that any significant adverse socioeconomic impacts will result form any of the proposed site characterization activities. However, the assessment of impacts in the EA, especially impacts related to employment and population growth, was based on assumptions concerning activities and conditions during the site characterization phase

  12. Nevada Test Site Site Treatment Plan. Revision 2

    International Nuclear Information System (INIS)

    1996-03-01

    Treatment Plans (STPS) are required for facilities at which the US Department of Energy (DOE) or stores mixed waste, defined by the Federal Facility Compliance Act (FFCAct) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act and a radioactive material subject to the Atomic Energy Act. On April 6, 1993, DOE published a Federal Register notice (58 FR 17875) describing its proposed process for developing the STPs in three phases including a Conceptual, a Draft, and a Proposed Site Treatment Plan (PSTP). All of the DOE Nevada Operations Office STP iterations have been developed with the state of Nevada's input. The options and schedules reflect a ''bottoms-up'' approach and have been evaluated for impacts on other DOE sites, as well as impacts to the overall DOE program. Changes may have occurred in the preferred option and associated schedules between the PSTP, which was submitted to the state of Nevada and US Environmental Protection Agency April 1995, and the Final STP (hereafter referred to as the STP) as treatment evaluations progressed. The STP includes changes that have occurred since the submittal of the PSTP as a result of state-to-state and DOE-to-state discussions

  13. U.S. Btu tax plan revised; industry wary of results

    International Nuclear Information System (INIS)

    Crow, P.

    1993-01-01

    The Clinton administration has changed its U.S. energy tax proposal to remove some objection voiced by industry and consumers. The Treasury Department's revised plan will still tax oil products at double the rate of other types of energy except for home heating oil, which now is to be taxed at the lower rate for natural gas. Of major importance to California producers, the revision will not tax natural gas used in enhanced recovery for heavy oil. This paper describes exemptions; effects on natural gas; the credibility gap; inhibition of gas market recovery; tax on NGL; and forecasting the future

  14. 77 FR 26475 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2012-05-04

    ...EPA is proposing to approve revisions to the Antelope Valley Air Quality Management District (AVAQMD), Eastern Kern Air Pollution Control District (EKAPCD), and Santa Barbara County Air Pollution Control District (SBCAPCD) portions of the California State Implementation Plan (SIP). We are proposing to approve revisions to local rules that define terms used in other air pollution regulations in these areas and a rule rescission that address Petroleum Coke Calcining Operations--Oxides of Sulfur, under the Clean Air Act as amended in 1990 (CAA or the Act).

  15. 75 FR 24406 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2010-05-05

    ...EPA is taking direct final action to approve revisions to the Placer County Air Pollution Control District (PCAPCD), Sacramento Metropolitan Air Quality Management District (SMAQMD), San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD), and South Coast Air Quality Management District (SCAQMD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from petroleum facilities, chemical plants, and facilities which use organic solvents. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  16. 75 FR 2796 - Revisions to the California State Implementation Plan, San Joaquin Valley Air Pollution Control...

    Science.gov (United States)

    2010-01-19

    ...EPA is finalizing approval of revisions to the San Joaquin Valley Air Pollution Control District portion of the California State Implementation Plan (SIP). These revisions were proposed in the Federal Register on June 16, 2009 and concern volatile organic compound (VOC) emissions from coating of metal parts, large appliances, metal furniture, motor vehicles, mobile equipment, cans, coils, organic solvent cleaning, and storage and disposal related to such operations. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  17. 76 FR 60376 - Revisions to the California State Implementation Plan, Santa Barbara Air Pollution Control...

    Science.gov (United States)

    2011-09-29

    ...EPA is taking direct final action to approve revisions to the Santa Barbara Air Pollution Control District (SBAPCD), Sacramento Municipal Air Quality Management District (SMAQMD) and South Coast Air Quality Management District (SCAQMD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from solvent cleaning machines and solvent cleaning operations and oil and gas production wells. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  18. 78 FR 21581 - Revisions to the California State Implementation Plan, Santa Barbara County Air Pollution Control...

    Science.gov (United States)

    2013-04-11

    ...EPA is proposing to approve revisions to the Santa Barbara County Air Pollution Control District (SBCAPCD) and South Coast Air Quality Management District (SCAQMD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) and oxides of nitrogen (NOX) emissions from gas-fired fan-type central furnaces, small water heaters, and the transfer and dispensing of gasoline. We are proposing to approve local rules to regulate these emission sources under the Clean Air Act (CAA or the Act).

  19. 76 FR 60405 - Revisions to the California State Implementation Plan, Santa Barbara Air Pollution Control...

    Science.gov (United States)

    2011-09-29

    ...EPA is proposing to approve revisions to the Santa Barbara Air Pollution Control District (SBAPCD), Sacramento Municipal Air Quality Management District (SMAQMD) and South Coast Air Quality Management District (SCAQMD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from solvent cleaning machines and solvent cleaning operations and oil and gas production wells. We are proposing to approve local rules to regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  20. 78 FR 21542 - Revisions to the California State Implementation Plan, Santa Barbara County Air Pollution Control...

    Science.gov (United States)

    2013-04-11

    ...EPA is taking direct final action to approve revisions to the Santa Barbara County Air Pollution Control District (SBCAPCD) and South Coast Air Quality Management District (SCAQMD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) and oxides of nitrogen (NOX) emissions from gas-fired fan-type central furnaces, small water heaters, and the transfer and dispensing of gasoline. We are approving local rules that regulate these emission sources under the Clean Air Act (CAA or the Act).

  1. 76 FR 5277 - Revisions to the California State Implementation Plan, Santa Barbara Air Pollution Control...

    Science.gov (United States)

    2011-01-31

    ...EPA is taking direct final action to approve revisions to the Santa Barbara Air Pollution Control District (SBAPCD), Antelope Valley Air Quality Management District (AVAQMD), Ventura County Air Pollution Control District (VCAPCD) and Placer County Air Pollution Control District (PCAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from gasoline bulk plants, terminals and vehicle dispensing facilities. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  2. 76 FR 16696 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2011-03-25

    ...EPA is finalizing approval of revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVAPCD) portion of the California State Implementation Plan (SIP). These revisions were proposed in the Federal Register on November 5, 2010 and concern oxides of nitrogen (NOX), carbon monoxide (CO), oxides of sulfur (SO2) and particulate matter emissions from boilers, steam generators and process heaters greater than 5.0 MMbtu/hour. We are approving a local rule that regulates these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  3. 75 FR 24544 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2010-05-05

    ...EPA is proposing to approve revisions to the Placer County Air Pollution Control District (PCAPCD), Sacramento Metropolitan Air Quality Management District (SMAQMD), San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD), and South Coast Air Quality Management District (SCAQMD) portions of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from petroleum facilities, chemical plants, and facilities which use organic solvents. We are proposing to approve local rules to regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  4. 76 FR 5319 - Revisions to the California State Implementation Plan, Santa Barbara Air Pollution Control...

    Science.gov (United States)

    2011-01-31

    ...EPA is proposing to approve revisions to the Santa Barbara Air Pollution Control District (SBAPCD), Placer County Air Pollution Control District (PCAPCD), Antelope Valley Air Quality Management District (AVAQMD), and Ventura County Air Pollution Control District (VCAPCD) portion of the California State Implementation Plan (SIP). These revisions concern volatile organic compound (VOC) emissions from gasoline bulk plants, terminals and vehicle dispensing facilities. We are proposing to approve local rules to regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  5. 49 CFR 659.25 - Annual review of system safety program plan and system security plan.

    Science.gov (United States)

    2010-10-01

    ... system security plan. 659.25 Section 659.25 Transportation Other Regulations Relating to Transportation... and system security plan. (a) The oversight agency shall require the rail transit agency to conduct an annual review of its system safety program plan and system security plan. (b) In the event the rail...

  6. Revised IAEA Code of Conduct on the Safety and Security of Radioactive Sources

    International Nuclear Information System (INIS)

    Wheatley, J. S.

    2004-01-01

    The revised Code of Conduct on the Safety and Security of Radioactive Sources is aimed primarily at Governments, with the objective of achieving and maintaining a high level of safety and security of radioactive sources through the development, harmonization and enforcement of national policies, laws and regulations; and through the fostering of international co-operation. It focuses on sealed radioactive sources and provides guidance on legislation, regulations and the regulatory body, and import/export controls. Nuclear materials (except for sources containing 239Pu), as defined in the Convention on the Physical Protection of Nuclear Materials, are not covered by the revised Code, nor are radioactive sources within military or defence programmes. An earlier version of the Code was published by IAEA in 2001. At that time, agreement was not reached on a number of issues, notably those relating to the creation of comprehensive national registries for radioactive sources, obligations of States exporting radioactive sources, and the possibility of unilateral declarations of support. The need to further consider these and other issues was highlighted by the events of 11th September 2001. Since then, the IAEA's Secretariat has been working closely with Member States and relevant International Organizations to achieve consensus. The text of the revised Code was finalized at a meeting of technical and legal experts in August 2003, and it was submitted to IAEA's Board of Governors for approval in September 2003, with a recommendation that the IAEA General Conference adopt it and encourage its wide implementation. The IAEA General Conference, in September 2003, endorsed the revised Code and urged States to work towards following the guidance contained within it. This paper summarizes the history behind the revised Code, its content and the outcome of the discussions within the IAEA Board of Governors and General Conference. (Author) 8 refs

  7. Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Irene Farnham

    2011-05-01

    This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

  8. High-heat tank safety issue resolution program plan

    International Nuclear Information System (INIS)

    Wang, O.S.

    1993-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank (SST) 241-C-106. This program plan also outlines the logic for selecting approaches and tasks to mitigate and resolve the high-heat safety issue. The identified safety issue for high-heat tank 241-C-106 involves the potential release of nuclear waste to the environment as the result of heat-induced structural damage to the tank's concrete, if forced cooling is interrupted for extended periods. Currently, forced ventilation with added water to promote thermal conductivity and evaporation cooling is used to cool the waste. At this time, the only viable solution identified to resolve this safety issue is the removal of heat generating waste in the tank. This solution is being aggressively pursued as the permanent solution to this safety issue and also to support the present waste retrieval plan. Tank 241-C-106 has been selected as the first SST for retrieval. The program plan has three parts. The first part establishes program objectives and defines safety issues, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. Selected tasks and best-estimate schedules are also summarized in the program plan

  9. Hanford analytical services quality assurance plan. Revision 1

    International Nuclear Information System (INIS)

    1995-02-01

    This document, the Hanford Analytical Services Quality Assurance Plan (HASQAP), is issued by the U.S. Department of Energy, Richland Operations Office (RL). The HASQAP establishes quality requirements in response to U.S. Department of Energy (DOE) Order 5700.6C, Quality Assurance (10 CFR 830.120, open-quotes Quality Assurance Requirementsclose quotes). The HASQAP is designed to meet the needs of the RL for controlling the of analytical chemistry services provided by laboratory operations. The HASQAP is issued through the Analytical Services Branch of the Waste Management Division. The Analytical Services Branch is designated by the RL as having the responsibility for oversight management of laboratory operations under the Waste Management Division. The laboratories conduct sample analyses under several regulatory statutes, such as the Clean Air Act and the Clean Water Act. Sample analysis in support of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) is a major role of the laboratory operations

  10. B Plant Complex waste management training plan. Revision 1

    International Nuclear Information System (INIS)

    Beam, T.G.

    1994-01-01

    This training program is designed to comply with all applicable federal, state and US Department of Energy-Richland Operations Office training requirements. The training program complies with requirements contained within WAC 173-303-330 for the development of a written dangerous waste training program. The training program is designed to prepare personnel to manage and maintain waste treatment, storage and disposal (TSD) units, as well as generator units, in a safe, effective, efficient and environmentally sound manner. In addition to preparing employees to manage and maintain TSD and generator units under normal conditions, the training program ensures that employees are prepared to respond in a prompt and effective manner should an emergency occur. The training plan also identifies specific individuals holding key waste management positions at B Plant Complex

  11. Environmental monitoring and mitigation plan for site characterization: Revision 1

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of the EMMP is: to identify, in consultation with the affected states and Indian tribes, potentially significant adverse environmental impacts that could result from site characterization activities, to describe data collection methods that will be used to monitor any such identified impacts, and procedures for mitigating them. Chapter 2 of the EMMP provides an overview of the background and scope of the document. Chapter 3 of the EMMP provides a description of site characterization phase activities planned to assess the geologic condition of the site and construct the exploratory shafts and surface support facilities. The rationale for developing environmental monitoring studies is presented in Chapeter 4. Chapter 5 contains descriptions of the environmental monitoring and mitigation procedures whenever they are applicable. Additionally, in Chapter 6, the EMMP includes a procedure for modifying the monitoring and mitigation program and an approach for reporting monitoring results to interested parties. 21 figs., 10 tabs

  12. C-018H LERF filtration test plan. Revision 1

    International Nuclear Information System (INIS)

    Moberg, T.P.; King, C.V.

    1994-01-01

    The following outlines the plan to test the polymeric backwash filtration system at the LERF. These tests will determine if the ETF filter design is adequate. If the tests show that the design is adequate, the task will be complete. If the tests show that the technology is inadequate, it may be necessary to perform further tests to qualify other candidate filtration technologies (e.g., polymeric tubular ultrafiltration, centrifugal ultrafiltration). The criteria to determine the success or failure of the backwash filter will be based on the system's ability to remove the bacteria and inorganic contaminants from the evaporator process condensate. The tests are designed to qualify the design basis of the filtration technology that will be used in the ETF

  13. C-018H LERF filtration test plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Moberg, T.P.; King, C.V.

    1994-08-26

    The following outlines the plan to test the polymeric backwash filtration system at the LERF. These tests will determine if the ETF filter design is adequate. If the tests show that the design is adequate, the task will be complete. If the tests show that the technology is inadequate, it may be necessary to perform further tests to qualify other candidate filtration technologies (e.g., polymeric tubular ultrafiltration, centrifugal ultrafiltration). The criteria to determine the success or failure of the backwash filter will be based on the system`s ability to remove the bacteria and inorganic contaminants from the evaporator process condensate. The tests are designed to qualify the design basis of the filtration technology that will be used in the ETF.

  14. 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

  15. Safety evaluation report on Tennessee Valley Authority: Browns Ferry nuclear performance plan

    International Nuclear Information System (INIS)

    1989-10-01

    This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory commission staff. The Browns Ferry Nuclear Plant consists of three boiling-water reactors at a site in Limestone County, Alabama. The plan addresses the plant-specific concerns requiring resolution before the startup of Unit 2. The staff will inspect implementation of those TVA programs that address these concerns. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 85 refs

  16. Minnesota urban partnership agreement national evaluation : safety data test plan.

    Science.gov (United States)

    2009-11-17

    This report provides the safety data test plan for the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reducing congestion by employing strat...

  17. Assessment of CFD Codes for Nuclear Reactor Safety Problems - Revision 2

    International Nuclear Information System (INIS)

    Smith, B.L.; Andreani, M.; Bieder, U.; Ducros, F.; Bestion, D.; Graffard, E.; Heitsch, M.; Scheuerer, M.; Henriksson, M.; Hoehne, T.; Houkema, M.; Komen, E.; Mahaffy, J.; Menter, F.; Moretti, F.; Morii, T.; Muehlbauer, P.; Rohde, U.; Krepper, E.; Song, C.H.; Watanabe, T.; Zigh, G.; Boyd, C.F.; Archambeau, F.; Bellet, S.; Munoz-Cobo, J.M.; Simoneau, J.P.

    2015-01-01

    Following recommendations made at an 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety (NRS) Problems', held in Aix-en-Provence, France, 15-16 May, 2002, and a follow-up meeting 'Use of Computational Fluid Dynamics (CFD) Codes for Safety Analysis of Reactor Systems including Containment', which took place in Pisa on 11-14 Nov., 2002, a CSNI action plan was drawn up which resulted in the creation of three Writing Groups, with mandates to perform the following tasks: (1) Provide a set of guidelines for the application of CFD to NRS problems; (2) Evaluate the existing CFD assessment bases, and identify gaps that need to be filled; (3) Summarise the extensions needed to CFD codes for application to two-phase NRS problems. Work began early in 2003. In the case of Writing Group 2 (WG2), a preliminary report was submitted to Working Group on the Analysis and Management of Accidents (WGAMA) in September 2004 that scoped the work needed to be carried out to fulfil its mandate, and made recommendations on how to achieve the objective. A similar procedure was followed by the other two groups, and in January 2005 all three groups were reformed to carry out their respective tasks. In the case of WG2, this resulted in the issue of a CSNI report (NEA/CSNI/R(2007)13), issued in January 2008, describing the work undertaken. The writing group met on average twice per year during the period March 2005 to May 2007, and coordinated activities strongly with the sister groups WG1 (Best Practice Guidelines) and WG3 (Multiphase Extensions). The resulting document prepared at the end of this time still represents the core of the present revised version, though updates have been made as new material has become available. After some introductory remarks, Chapter 3 lists twenty-three (23) NRS issues for which it is considered that the application of CFD would bring real benefits

  18. 75 FR 29588 - Office of New Reactors: Proposed NUREG-0800; Standard Review Plan Section 13.6.6, Draft Revision...

    Science.gov (United States)

    2010-05-26

    ...; Standard Review Plan Section 13.6.6, Draft Revision 0 on Cyber Security Plan AGENCY: Nuclear Regulatory... Plants,'' on a proposed Standard Review Plan (SRP) Section 13.6.6 on ``Cyber Security Plan'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093560837). The Office of Nuclear Security...

  19. Double-shell tank ultrasonic inspection plan. Revision 1

    International Nuclear Information System (INIS)

    Pfluger, D.C.

    1994-01-01

    The waste tank systems managed by the Tank Waste Remediation System Division of Westinghouse Hanford Company includes 28 large underground double-shell tanks (DST) used for storing hazardous radioactive waste. The ultrasonic (UT) inspection of these tanks is part of their required integrity assessment (WAC 1993) as described in the tank systems integrity assessment program plan (IAPP) (Pfluger 1994a) submitted to the Ecology Department of the State of Washington. Because these tanks hold radioactive waste and are located underground examinations and inspections must be done remotely from the tank annuli with specially designed equipment. This document describes the UT inspection system (DSTI system), the qualification of the equipment and procedures, field inspection readiness, DST inspections, and post-inspection activities. Although some of the equipment required development, the UT inspection technology itself is the commercially proven and available projection image scanning technique (P-scan). The final design verification of the DSTI system will be a performance test in the Hanford DST annulus mockup that includes the demonstration of detecting and sizing corrosion-induced flaws

  20. Nuclear safety authority. Strategical planning 2005- 2007

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    The Nuclear safety Authority (A.S.N.) provides, in the name of the state, the monitoring of nuclear safety and radiation protection to protect workers, patients, public and environment from the risks in relation with nuclear activities and more broadly with ionizing radiations, it contributes to citizens information in these areas. The ambition of A.S.N. is to carry out a successful, legitimate, credible nuclear monitoring, recognized by citizens and that constitutes an international reference. (N.C.)

  1. Safety Evaluation Report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan: Browns Ferry Unit 2 restart

    International Nuclear Information System (INIS)

    1989-04-01

    This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Power Station and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of Unit 2. The staff will inspect implementation of those programs. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 3 refs

  2. Monitoring well inspection and maintenance plan Y-12 Plant, Oak Ridge, Tennessee (revised)

    International Nuclear Information System (INIS)

    1996-09-01

    Inspection and maintenance of groundwater monitoring wells is a primary element of the Oak Ridge Y-12 Plant Groundwater Protection Program (GWPP). This document is the revised groundwater monitoring well inspection and maintenance plan for the U.S. Department of Energy (DOE) Y-12 Plant in Oak Ridge, Tennessee. The plan provides a systematic program for: (1) inspecting the physical condition of monitoring wells at the Y-12 Plant and (2) identifying maintenance needs that will extend the life of each well and ensure that representative groundwater quality samples and hydrologic data are collected from the wells. Original documentation for the Y-12 Plant GWPP monitoring well inspection and maintenance program was provided in HSW, Inc. 1991a. The original revision of the plan specified that only a Monitoring Well Inspection/Maintenance Summary need be updated and reissued each year. Rapid growth of the monitoring well network and changing regulatory requirements have resulted in constant changes to the status of wells (active or inactive) listed on the Monitoring Well Inspection/Maintenance Summary. As a result, a new mechanism to track the status of monitoring wells has been developed and the plan revised to formalize the new business practices. These changes are detailed in Sections 2.4 and 2.5

  3. 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.

  4. Work Plans 2011 – Norwegian Scientific Committee for Food Safety

    OpenAIRE

    Norwegian Scientific Committee for Food Safety

    2011-01-01

    The annual work plan for 2011 summaries activities for the Scientific Steering Committee and the 9 panels of the Norwegian Scientific Committee for Food Safety (VKM). VKM carries out independent risk assessments for the Norwegian Food Safety Authority across the Authority’s field of responsibility as well as environmental risk assessments of genetically modified organisms for the Directorate for Nature Management.

  5. Supporting Fernald Site Closure with Integrated Health and Safety Plans as Documented Safety Analyses

    International Nuclear Information System (INIS)

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

    2004-01-01

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 200 structures, including eight major nuclear production plants. There is one of twelve nuclear facilities still remaining (Silos containing uranium ore residues) with its own safety basis documentation. This paper presents the status of the FCP's safety basis documentation program, illustrating that all of the former nuclear facilities and activities have now replaced. Basis of Interim Operations (BIOs) with I-HASPs as their safety basis during the closure process

  6. Overview of IAEA Action Plan on Nuclear Safety

    International Nuclear Information System (INIS)

    Monti, Stefano

    2012-01-01

    The IAEA Action Plan represents a work programme to strengthen and improve nuclear safety world wide. The plan identifies actions for Member States and the IAEA. Success depends upon: • Cooperation between IAEA, Member States, and other stakeholders; • Availability of appropriate financial resources (MS voluntary contributions)

  7. Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1, Revision 1 (Chinese Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication establishes requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

  8. 77 FR 66548 - Revisions to the California State Implementation Plan, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-11-06

    ...EPA is approving revisions to the San Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the California State Implementation Plan (SIP). This action was proposed in the Federal Register on April 26, 2012 and concerns oxides of nitrogen (NOX) from solid fuel fired boilers. We are approving a local rule that regulates these emission sources under the Clean Air Act (CAA or the Act).

  9. 77 FR 71129 - Revisions to the California State Implementation Plan, San Joaquin Valley United Air Pollution...

    Science.gov (United States)

    2012-11-29

    ...EPA is finalizing approval of revisions to the SJVUAPCD and SCAQMD portion of the California State Implementation Plan (SIP). This action was proposed in the Federal Register on June 21, 2012 and concerns volatile organic compound (VOC) emissions from chipping and grinding activities, and composting operations. We are approving local rules that regulate these emission sources under the Clean Air Act (CAA or the Act).

  10. Stress Tests Worldwide - IAEA Nuclear Safety Action Plan

    International Nuclear Information System (INIS)

    Lyons, J.E.

    2012-01-01

    The IAEA nuclear safety action plan relies on 11 important issues. 1) Safety assessments in light of the Fukushima accident: the IAEA secretariat will develop a methodology for stress tests against specific extreme natural hazards and will provide assistance for their implementation; 2) Strengthen existing IAEA peer reviews; 3) Emergency preparedness and response; 4) National Regulatory bodies in terms of independence and adequacy of human and financial resources; 5) The development of safety culture and scientific and technical capacity in Operating Organizations; 6) The upgrading of IAEA safety standards in a more efficient way; 7) A better implementation of relevant conventions concerning nuclear safety and nuclear accidents; 8) To provide a broad assistance on safety standard for countries embarking on a nuclear power program; 9) To facilitate the use of available information, expertise and techniques concerning radiation protection; 10) To enhance the transparency of nuclear industry; and 11) To promote the cooperation between member states in nuclear safety. (A.C.)

  11. K basins interim remedial action health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    DAY, P.T.

    1999-09-14

    The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

  12. Annual plan of research on safety techniques against low level radioactive wastes, 1984-1988

    International Nuclear Information System (INIS)

    1984-01-01

    The establishment of the countermeasures for treating and disposing radioactive wastes has become an important subject for promoting the utilization of atomic energy. Especially as to low level radioactive wastes, the cumulative quantity has reached about 460,000 in terms of 200 l drums as of the end of March, 1983, and accompanying the development of the utilization of atomic energy, its rapid increase is expected. So far, as for the disposal of low level radioactive wastes, the research and development and the preparation of safety criteria and safety evaluation techniques have been carried out, following the basic policy of the Atomic Energy Commission to execute land disposal and ocean disposal in combination, first to make the test disposal after preliminary safety evaluation, and to shift to the full scale disposal based on the results. The annual plan was decided on July 22, 1983, and the first revision was carried out this time, therefore, it is reported here. The basic policy of establishing this annual plan, and the annual plan for safety technique research are described. (Kako, I.)

  13. Role of nuclear safety research and future plan

    International Nuclear Information System (INIS)

    Kim, W. S.; Lee, J. I.; Kang, S. C.; Park, Y. W.; Lee, J. H.; Kim, M. W.; Lee, C. J.; Park, Y. I.

    2000-01-01

    For promoting and improving nuclear safety research activities, this report gives an insight on the scope of safety research and its role in the safety management of nuclear installations, and suggests measures to adequately utilize the research results through taking an optimized role share among research organizations. Several measures such as cooperative planning of common research areas and proper role assignment, improvement of the interfaces among researchers, and reflection of end-users' opinion in the course of planning and conducting research to promote application of research results are identified. It is expected that the identified measures will contribute to enhancing the efficiency and effectiveness of nuclear safety research, if they are implemented after deliberating with the government and safety research organizations

  14. Safety and Inspection Planning of Older Installations

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Ersdal, G.

    2007-01-01

    A basic assumption often made in risk/reliability based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and a no-...

  15. Safety and Inspection Planning of Older Installations

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Ersdal, G.

    2008-01-01

    A basic assumption often made in risk- and reliability-based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and ...

  16. Savannah River interim waste management program plan: FY 1984. Revision 1

    International Nuclear Information System (INIS)

    1983-10-01

    This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the interim waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1984. In addition, the document projects activities for several years beyond 1984 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of June 1983

  17. Software quality assurance plans for safety-critical software

    International Nuclear Information System (INIS)

    Liddle, P.

    2006-01-01

    Application software is defined as safety-critical if a fault in the software could prevent the system components from performing their nuclear-safety functions. Therefore, for nuclear-safety systems, the AREVA TELEPERM R XS (TXS) system is classified 1E, as defined in the Inst. of Electrical and Electronics Engineers (IEEE) Std 603-1998. The application software is classified as Software Integrity Level (SIL)-4, as defined in IEEE Std 7-4.3.2-2003. The AREVA NP Inc. Software Program Manual (SPM) describes the measures taken to ensure that the TELEPERM XS application software attains a level of quality commensurate with its importance to safety. The manual also describes how TELEPERM XS correctly performs the required safety functions and conforms to established technical and documentation requirements, conventions, rules, and standards. The program manual covers the requirements definition, detailed design, integration, and test phases for the TELEPERM XS application software, and supporting software created by AREVA NP Inc. The SPM is required for all safety-related TELEPERM XS system applications. The program comprises several basic plans and practices: 1. A Software Quality-Assurance Plan (SQAP) that describes the processes necessary to ensure that the software attains a level of quality commensurate with its importance to safety function. 2. A Software Safety Plan (SSP) that identifies the process to reasonably ensure that safety-critical software performs as intended during all abnormal conditions and events, and does not introduce any new hazards that could jeopardize the health and safety of the public. 3. A Software Verification and Validation (V and V) Plan that describes the method of ensuring the software is in accordance with the requirements. 4. A Software Configuration Management Plan (SCMP) that describes the method of maintaining the software in an identifiable state at all times. 5. A Software Operations and Maintenance Plan (SO and MP) that

  18. 75 FR 57055 - Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Utah Prairie Dog

    Science.gov (United States)

    2010-09-17

    ...] Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Utah Prairie Dog AGENCY: Fish... recovery plan for the Utah prairie dog (Cynomys parvidens). This species is federally listed as threatened... and peer reviewers in an appendix to the approved recovery plan. The Utah prairie dog (Cynomys...

  19. 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

  20. 78 FR 47014 - Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear...

    Science.gov (United States)

    2013-08-02

    .... ML12354A524. 3. Revision 1 of RG 1.170, ``Test Documentation for Digital Computer Software used in Safety... is in ADAMS at Accession No. ML12354A531. 4. Revision 1 of RG 1.171, ``Software Unit Testing for... Software Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION...

  1. IAEA Sets Up Team to Drive Nuclear Safety Action Plan

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: The International Atomic Energy Agency is setting up a Nuclear Safety Action Team to oversee prompt implementation of the IAEA Action Plan on Nuclear Safety and ensure proper coordination among all stakeholders. The 12-point Action Plan, drawn up in the wake of the Fukushima Daiichi accident, was approved by the Agency's Board of Governors on 13 September and endorsed by all 151 Member States at its General Conference last week. The team will work within the Agency's Department of Nuclear Safety and Security, headed by Deputy Director General Denis Flory, and will coordinate closely with the Director General's Office for Policy. ''The Action Plan requires immediate follow-up,'' Director General Yukiya Amano said. ''This compact, dedicated team will assist Deputy Director General Flory in implementing the measures agreed in the Action Plan.'' Gustavo Caruso, Head of the Regulatory Activities Section in the IAEA's Division of Installation Safety, has been designated as the team's Special Coordinator for the implementation of the Action Plan. The IAEA has already started implementing its responsibilities under the Action Plan, including development of an IAEA methodology for stress tests for nuclear power plants. The methodology will be ready in October. (IAEA)

  2. Simplifying documentation while approaching site closure: integrated health and safety plans as documented safety analysis

    International Nuclear Information System (INIS)

    Brown, Tulanda

    2003-01-01

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

  3. The revision of the safety standards for protection against ionizing radiation

    International Nuclear Information System (INIS)

    Wei Li Chen; Hsiao Ping Wang; Chia Chun Liao; Chin Shiun Yeh

    1994-01-01

    The Chinese Safety Standards for Protection Against Ionizing Radiation was issued on July 29, 1970, and has been used for more than thirteen years. In 1983, the Atomic Energy Council (AEC) decided to revise it accordingly to the recommendations of the International Commission on Radiological Protection and the experiences of regulation enforcement in Taiwan and other countries. The AEC assembled a task group of eight members from academic institutions, licensees, government agency, and senior health physics to be in charge of the revision. In this presentation the major changes of the Safety Standards are summarized. They refer to the adoption of the system of dose limitation recommended by ICRP publication 26 and 30, the use of the units of the International System as the primary units with the old units being noted in parentheses, the adoption of the minimums levels recommended by the International Atomic Energy Agency and the setting up of an executive regulatory system for the implementation of the ALARA concept. 6 refs

  4. Digital Problems and Strategies of Partial Revision in Overall Plan of Land Use

    Institute of Scientific and Technical Information of China (English)

    2010-01-01

    The technical route of partial revision in overall plan of land use is briefly described.It is pointed out that problems of area measuring in the technical route are mainly due to the digital process.The digital problems of partial revision in overall plan of land use are presented as follows:the maps are not proofread before digitalization;the coordinate matching and projection transformation are not conducted on the maps;the information is asymmetrical pre and post the digitalization;the location lacks precision;the result maps are substandard.The causes of these problems are analyzed,which cover the following aspects.The lack of united management regulations;uneven working abilities of the staff in the compilation units;unawareness of the importance of map digilalization;poor basic conclitions of the original plan maps.At last,the relevant suggestions are put forward,for instance,releasing the national united management methods and technical criteria,establishing industrial admittance system and qualification system of complication units,setting up the mechanism of supervising digitalized results and controlling the quality,conducting coordinate matching and projection transformation and unifying the specification and mode of the results of maps so as to provide technical support for the overall plan of land use,play the micro-regulating role of land use and take a leading role in the sustainable development of social economy.

  5. Prospects offered by the departmental plans inspection; Les perspectives offertes par la revision des plans departementaux

    Energy Technology Data Exchange (ETDEWEB)

    Thauvin, Ph.

    2000-07-01

    In the framework of the departmental plans inspection, a detailed document is presented on the domestic and industrial wastes management. These plans forecast an increase of the recycling facing the incineration, a mastership of the costs, a better application of the regulations and a campaign of public information. The indicators of control and the main points of these plans are discussed, supported by tables and definitions. (A.L.B.)

  6. Safety planning for nuclear power stations

    International Nuclear Information System (INIS)

    Tadmor, J.

    1979-01-01

    The article shows that compared to the many industries and other human activities, nuclear power stations are among the safest. A short description of the measures taken to prevent accidents and of the additional safety means entering into action if an accident does occur is presented. It is shown that in nuclear plants the death frequency following malfunctioning is 1 death in 100.000 years whereas deaths following other human activities is 1 in 2 to 100 years and following natural calamities like earthquakes and floods is 1 in 10 years. As an example it is shown that for a population of 15.000.000 living in a radius of 40 km around 100 power stations the average number of deaths will be of 2 per year as compared to 4200 from road accidents with the corresponding number of injuries of 20 and 375.000 respectively. (B.G.)

  7. 75 FR 36126 - Office of New Reactors; Proposed Revision to Standard Review Plan Section 13.6.1, Revision 1 on...

    Science.gov (United States)

    2010-06-24

    ... Standard Review Plan Section 13.6.1, Revision 1 on Physical Security--Combined License and Operating...), Section 13.6.1 on ``Physical Security--Combined License and Operating Reactors,'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100350158). The Office of Nuclear Security and...

  8. 78 FR 12267 - Revision of Air Quality Implementation Plan; California; Placer County Air Pollution Control...

    Science.gov (United States)

    2013-02-22

    ...EPA is proposing a limited approval and limited disapproval of permitting rules submitted by California as a revision to the Placer County Air Pollution Control District (PCAPCD) and Feather River Air Quality Management District (FRAQMD) portion of the California State Implementation Plan (SIP). These rules were adopted by the PCAPCD and FRAQMD to regulate the construction and modification of stationary sources of air pollution within each District. EPA is proposing to approve these SIP revisions based on the Agency's conclusion that the rules are consistent with applicable Clean Air Act (CAA) requirements, policies and guidance. Final approval of these rules would make the rules federally enforceable and correct program deficiencies identified in a previous EPA rulemaking (76 FR 44809, July 27, 2011).

  9. 78 FR 58460 - Revision of Air Quality Implementation Plan; California; Placer County Air Pollution Control...

    Science.gov (United States)

    2013-09-24

    ...EPA is finalizing a limited approval and limited disapproval of two permitting rules submitted by California as a revision to the Placer County Air Pollution Control District (PCAPCD) and Feather River Air Quality Management District (FRAQMD) portion of the California State Implementation Plan (SIP). These revisions were proposed in the Federal Register on February 22, 2013 and concern construction and modification of stationary sources of air pollution within each District. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA). Final approval of these rules makes the rules federally enforceable and corrects program deficiencies identified in a previous EPA rulemaking (76 FR 44809, July 27, 2011). EPA is also making a technical amendment to the Code of Federal Regulations (CFR) to reflect this previous rulemaking, which removed an obsolete provision from the California SIP.

  10. 78 FR 51754 - Request To Modify License by Replacing Security Plan With New Radiation Safety Plan; U.S...

    Science.gov (United States)

    2013-08-21

    ... Replacing Security Plan With New Radiation Safety Plan; U.S. Department of the Army, Jefferson Proving... security plan with a new radiation safety plan. DATES: Submit comments by September 20, 2013. Requests for.... The proposed change is to modify License Condition No. 12 D which refers to the security plan of...

  11. Oak Ridge National Laboratory Environmenal, Safety, and Health Management Plan

    International Nuclear Information System (INIS)

    1991-12-01

    The 1990 Tiger Team Appraisal of Oak Ridge National Laboratory (ORNL) revealed that neither Martin Marietta Energy Systems, Inc. (Energy Systems) nor ORNL had a strategic plan for Environmental, Safety, and Health (ES ampersand H) activities. There were no detailed plans describing ORNL's mission, objectives, and strategies for ES ampersand H activities. A number of plans do exist that cover various aspects of ES ampersand H. Their scope ranges from multiyear program plans to annual audit schedules to compliance plans to action plans from specific audits. However, there is not a single document that identifies the plans and the objectives they are to address. This document describes the strategic plan for ORNL and provides the linkage among existing plans. It gives a brief description of the organization and management of ES ampersand H activities at ORNL. The plan identifies the general strategies to be taken by ORNL, using the overall guidance from Energy Systems in its corporate ES ampersand H Strategic Plan. It also identifies more detailed plans for implementation of these strategies, where appropriate

  12. Planning and evaluation of plant under safety aspects

    International Nuclear Information System (INIS)

    Strnad, H.

    1985-01-01

    Plant denotes a technical product characterized as being structured, complex, comprising the use of energy, and that of measuring, automatic control and monitoring systems to keep track of present, control and monitor processes. Particular attention is paid to methods of developing plant concepts, measures to exclude or detect risks, integration of safety engineering into the course of planning, safety concept and ergonomics in plant design. (DG) [de

  13. Safety evaluation report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan

    International Nuclear Information System (INIS)

    1991-01-01

    This safety evaluation report (SER) was prepared by the US Nuclear Regulatory Commission (NRC) staff and represents the second and last supplement (SSER 2) to the staff's original SER published as Volume 3 of NUREG-1232 in April 1989. Supplement 1 of Volume 3 of NUREG-1232 (SSER 1) was published in October 1989. Like its predecessors, SSER 2 is composed of numerous safety evaluations by the staff regarding specific elements contained in the Browns Ferry Nuclear Performance Plan (BFNPP), Volume 3 (up to and including Revision 2), submitted by the Tennessee Valley Authority (TVA) for the Browns Ferry Nuclear Plant (BFN). The Browns Ferry Nuclear Plant consists of three boiling-water reactors (BWRs) at a site in Limestone County, Alabama. The BFNPP describes the corrective action plans and commitments made by TVA to resolve deficiencies with its nuclear programs before the startup of Unit 2. The staff has inspected and will continue to inspect TVA's implementation of these BFNPP corrective action plans that address staff concerns about TVA's nuclear program. SSER 2 documents the NRC staff's safety evaluations and conclusions for those elements of the BFNPP that were not previously addressed by the staff or that remained open as a result of unresolved issues identified by the staff in previous SERs and inspections

  14. Expedited technology demonstration project (Revised mixed waste management facility project) Project baseline revision 4.0 and FY98 plan

    International Nuclear Information System (INIS)

    Adamson, M. G.

    1997-01-01

    The re-baseline of the Expedited Technology Demonstration Project (Revised Mixed Waste Facility Project) is designated as Project Baseline Revision 4.0. The last approved baseline was identified as Project Baseline Revision 3.0 and was issued in October 1996. Project Baseline Revision 4.0 does not depart from the formal DOE guidance followed by, and contained in, Revision 3.0. This revised baseline document describes the MSO and Final Forms testing activities that will occur during FY98, the final year of the ETD Project. The cost estimate for work during FY98 continues to be $2.OM as published in Revision 3.0. However, the funds will be all CENRTC rather than the OPEX/CENTRC split previously anticipated. LLNL has waived overhead charges on ETD Project CENRTC funds since the beginning of project activities. By requesting the $2.OM as all CENTRC a more aggressive approach to staffing and testing can be taken. Due to a cost under- run condition during FY97 procurements were made and work was accomplished, with the knowledge of DOE, in the Feed Preparation and Final Forms areas that were not in the scope of Revision 3.0. Feed preparation activities for FY98 have been expanded to include the drum opening station/enclosure previously deleted

  15. A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

    International Nuclear Information System (INIS)

    Yang, Seung Hyo; Choi, Sun Do

    2012-01-01

    Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control

  16. A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Seung Hyo; Choi, Sun Do [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2012-10-15

    Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control.

  17. Russian MINATOM nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    1999-03-01

    The 'Safety Research Strategic Plan for Russian Nuclear Power Plants' was published in draft form at the Russian International Nuclear Safety Centre (RINSC) by a working group of fifteen senior Russian experts. The Plan consists of 12 chapters, each addressing a specific technical area and containing a number of proposed research programmes and projects to advance the state-of-knowledge in that area. In part because a strong Recommendation to undertake such a Plan was made by the 1998 OECD/NEA study, the OECD Nuclear Energy Agency was asked by the Director of RINSC and the Director of USINSC to organize an international review of the Plan when the English-language version became available in October, 1998. This report represents the results of that review. (R.P.)

  18. 200 West Area Ash Pit Demolition Site closure plan. Revision 1

    International Nuclear Information System (INIS)

    Ruck, F.R.

    1994-01-01

    The Ash Pit Demolition Site had two known demolition events, the first occurred in November of 1984, and the second occurred in June of 1986. These demolition events were a form of thermal treatment for discarded explosive chemical products. Because the Ash Pit Demolition Site will no longer be used for this thermal activity, the site will be closed. Closure will be conducted pursuant to the requirements of the Washington State Department of Ecology (Ecology) ''Dangerous Waste Regulations'', Washington Administrative Code (WAC) 173-303-610 and 40 Code of Federal Regulations (CFR) 270.1. The 200 West Area Ash Pit Demolition Site Closure Plan consists of a Part A, Form 3, Dangerous Waste Permit Application (Revision 4) and a closure plan. An explanation of the Part A, Form 3, submitted with this closure plan is provided at the beginning of the Part A Section. The closure plan consists of nine chapters and five appendices. This closure plan presents a description of the Ash,Pit Demolition Site, the history of the waste treated, and the approach that will be followed to close the Ash Pit Demolition Site. Because there were no radioactively contaminated chemicals involved in the demolitions, the information on radionuclides is provided for ''information only''. Remediation of any radioactive contamination is not within the scope of this closure plan. Only dangerous constituents derived from Ash Pit Demolition Site operations will be addressed in this closure plan in accordance with WAC 173-303-610(2)(b)(i)

  19. Safety Evaluation report on Tennessee Valley Authority: Sequoyah nuclear performance plan

    International Nuclear Information System (INIS)

    1988-05-01

    This Safety Evaluation Report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Sequoyah Nuclear Performance Plan, through Revision 2, and supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of either of the Sequoyah units. In particular, the SER addresses required actions for Unit 2 restart. In many cases, the programmatic aspects for Unit 1 are identical to those for Unit 2; the staff will conduct inspections of implementation of those programs. Where the Unit 1 program is different, the staff evaluation will be provided in a supplement to this SER. On the basis of its review, the staff concludes that Sequoyah-specific issues have been resolved to the extent that would support restart of Sequoyah Unit 2

  20. Upgraded safety analysis document including operations policies, operational safety limits and policy changes. Revision 2

    International Nuclear Information System (INIS)

    Batchelor, K.

    1996-03-01

    The National Synchrotron Light Source Safety Analysis Reports (1), (2), (3), BNL reports number-sign 51584, number-sign 52205 and number-sign 52205 (addendum) describe the basic Environmental Safety and Health issues associated with the department's operations. They include the operating envelope for the Storage Rings and also the rest of the facility. These documents contain the operational limits as perceived prior or during construction of the facility, much of which still are appropriate for current operations. However, as the machine has matured, the experimental program has grown in size, requiring more supervision in that area. Also, machine studies have either verified or modified knowledge of beam loss modes and/or radiation loss patterns around the facility. This document is written to allow for these changes in procedure or standards resulting from their current mode of operation and shall be used in conjunction with the above reports. These changes have been reviewed by NSLS and BNL ES and H committee and approved by BNL management

  1. Selenide isotope generator for the Galileo Mission: safety test plan

    International Nuclear Information System (INIS)

    1979-01-01

    The intent of this safety test plan is to outline particular kinds of safety tests designed to produce information which would be useful in the safety analysis process. The program deals primarily with the response of the RTG to accident environments; accordingly two criteria were established: (1) safety tests should be performed for environments which are the most critical in terms of risk contribution; and (2) tests should be formulated to determine failure conditions for critical heat source components rather than observe heat source response in reference accident environments. To satisfy criterion 1. results of a recent safety study were used to rank various accidents in terms of expected source terms. Six kinds of tests were then proposed which would provide information meeting the second criterion

  2. Program plan for shipment, receipt, and storage of the TMI-2 core. Revision 1

    International Nuclear Information System (INIS)

    Quinn, G.J.; Reno, H.W.; Schmitt, R.C.

    1985-01-01

    This plan addresses the preparation and shipment of core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that core debris. The Manager of the Nuclear Materials Evaluation Programs Division of EG and G Idaho, Inc. will manage two separate but integrated programs, one located at TMI (Part 1) and the other at INEL (Part 2). The Technical Integration Office (at TMI) is responsible for developing and implementing Part 1, TMI-2 Core Shipment Program. The Technical Support Branch (at INEL) is responsible for developing and implementing Part 2, TMI-2 Core Receipt and Storage. The plan described herein is a revision of a previous document entitled Plan for Shipment, Storage, and Examination of TMI-2 Fuel. This revision was required to delineate changes, primarily in Part 2, Core Activities Program, of the previous document. That part of the earlier document related to core examination was reidentified in mid-FY-1984 as a separate trackable entity entitled Core Sample Acquisition and Examination Project, which is not included here

  3. Engineering work plan for container venting system drill press assembly troubleshooting. Revision 1

    International Nuclear Information System (INIS)

    Prather, M.C.

    1994-11-01

    This work plan is for troubleshooting the current CVS drill press to ensure that the drill bit assembly doesn't bind in the press plate. A drill press assembly has been fabricated for the Container Venting System (CVS). The drill bit assembly has bound in the press plate in previous revisions of this design. Initial troubleshooting of the drill press per Rev. 0 of this work plan was performed at the 200W Kaiser Machine Shop under Work Package 2H9401670F, Internal Work Order E20027. The drill press operated without jamming. Then, during the pre-operational test on 11/14/17 and the operational test on 11/17/94, two drum lids were drilled. Immediately after the test on 11/17/94, the drill was again operated, and it jammed. An inspection found shavings at the bottom of the drill bit assembly, between the drill bit sleeve and the press plate bore. This revised work plan provides direction for the machine shop to diagnose and correct this recent problem

  4. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 3

    International Nuclear Information System (INIS)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2006-01-01

    This is the 2006 update (Revision 3) of the NGNP Materials Research and Development Program Plan. This law established that the U.S Department of Energy (DOE) Secretary of Energy shall establish a ''Next Generation Nuclear Plant'' (NGNP) project. The NGNP project named in the Act was given the following attributes and guiding principles to manage its development: (1) The NGNP consists of research, development, design (R and DD), construction, and operation of a prototype reactor to generate electricity and hydrogen; (2) The project shall be managed by the DOE Office of Nuclear Energy; (3) The Idaho National Laboratory (INL) shall be the lead DOE laboratory for the NGNP; (4) The INL shall establish collaborations with selected institutions of higher education, other research institutes and international researchers; (5) The INL shall organize an industrial consortium of partners for cost-shared R and DD, construction; (6) The project shall be sited at the INL; (7) The project shall be licensed by the Nuclear Regulatory Commission (NRC) and by July, 2008 the NRC and DOE shall jointly submit a licensing strategy to Congress; (8) The project shall be organized to maximize technical interchange with the nuclear power industry, nuclear power plant construction firms, the chemical process industry and to seek international cooperation, participation and contributions; (9) The Nuclear Energy Research Advisory Committee (NERAC) shall review all program plans for the NGNP; (10) Phase 1 of the project (selection of hydrogen production technology, conduct R and DD and initial design activities) shall be completed no later than September 30, 2011; (11) Phase 2 of the project (continue R and DD, develop final design, apply for a license, construct and start operations) shall be completed by September 30, 2021; and (12) Provision for authorization of appropriations was made. As a result of the direction provided, the INL and the DOE issued an NGNP Preliminary Project Management

  5. 77 FR 26448 - Revisions to the California State Implementation Plan, Antelope Valley Air Quality Management...

    Science.gov (United States)

    2012-05-04

    ...EPA is taking direct final action to approve revisions to the Antelope Valley Air Quality Management District (AVAQMD), Eastern Kern Air Pollution Control District (EKAPCD), and Santa Barbara County Air Pollution Control District (SBCAPCD) portions of the California State Implementation Plan (SIP). Under authority of the Clean Air Act as amended in 1990 (CAA or the Act), we are approving local rules that define terms used in other air pollution regulation in these areas and approving a rule rescission that addresses Petroleum Coke Calcining Operations--Oxides of Sulfur.

  6. 76 FR 44809 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2011-07-27

    ...EPA is finalizing a limited approval and limited disapproval of permitting rules submitted for the Placer County Air Pollution Control District (PCAPCD) and Feather River Air Quality Management District (FRAQMD) portions of the California State Implementation Plan (SIP). These revisions were proposed in the Federal Register on May 19, 2011 and concern New Source Review (NSR) permit programs for new and modified major stationary sources of air pollution. We are approving local rules that regulate these emission sources under the Clean Air Act as amended in 1990 (CAA or the Act).

  7. 78 FR 23677 - Revisions to the California State Implementation Plan, Imperial County Air Pollution Control...

    Science.gov (United States)

    2013-04-22

    ...EPA is finalizing approval of revisions to the Imperial County Air Pollution Control District (ICAPCD) portion of the California State Implementation Plan (SIP). This action was proposed in the Federal Register on January 7, 2013 and concerns local rules that regulate inhalable particulate matter (PM) emissions from sources of fugitive dust such as unpaved roads and disturbed soils in open and agricultural areas in Imperial County. We are approving local rules that regulate these emission sources under the Clean Air Act (CAA or the Act).

  8. 77 FR 2643 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control District

    Science.gov (United States)

    2012-01-19

    ...EPA is finalizing a limited approval and limited disapproval of revisions to the Placer County Air Pollution Control District (PCAPCD) portion of the California State Implementation Plan (SIP). This action was proposed in the Federal Register on September 6, 2011 and concerns oxides of nitrogen (NOX) emissions from biomass fuel-fired boilers. Under authority of the Clean Air Act as amended in 1990 (CAA or the Act), this action simultaneously approves a local rule that regulates these emission sources and directs California to correct rule deficiencies.

  9. Management implementation plan for a safety analysis and review system

    International Nuclear Information System (INIS)

    Hulburt, D.A.; Berkey, B.D.

    1981-04-01

    The US Department of Energy has issued an Order, DOE 5481.1, which establishes uniform requirements for the preparation and review of Safety Analysis for DOE Operations. The Management Implementation Plan specified herein establishes the administrative procedures and technical requirements for implementing DOE 5481.1 to Operations under the cognizance of the Pittsburgh Energy Technology Center. This Implementation Plan is applicable to all present and future Operations under the cognizance of PETC. The Plan identifies those Operations for which DOE 5481.1 is applicable and those Operations for which no further analysis is required because the initial determination and review has concluded that DOE 5481.1 does not apply

  10. Children's high-level writing skills: development of planning and revising and their contribution to writing quality.

    Science.gov (United States)

    Limpo, Teresa; Alves, Rui A; Fidalgo, Raquel

    2014-06-01

    It is well established that the activity of producing a text is a complex one involving three main cognitive processes: Planning, translating, and revising. Although these processes are crucial in skilled writing, beginning and developing writers seem to struggle with them, mainly with planning and revising. To trace the development of the high-level writing processes of planning and revising, from Grades 4 to 9, and to examine whether these skills predict writing quality in younger and older students (Grades 4-6 vs. 7-9), after controlling for gender, school achievement, age, handwriting fluency, spelling, and text structure. Participants were 381 students from Grades 4 to 9 (age 9-15). Students were asked to plan and write a story and to revise another story by detecting and correcting mechanical and substantive errors. From Grades 4 to 9, we found a growing trend in students' ability to plan and revise despite the observed decreases and stationary periods from Grades 4 to 5 and 6 to 7. Moreover, whereas younger students' planning and revising skills made no contribution to the quality of their writing, in older students, these high-level skills contributed to writing quality above and beyond control predictors. The findings of this study seem to indicate that besides the increase in planning and revising, these skills are not fully operational in school-age children. Indeed, given the contribution of these high-level skills to older students' writing, supplementary instruction and practice should be provided from early on. © 2013 The British Psychological Society.

  11. The advanced neutron source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1989-01-01

    The Advanced Neutron Source (ANS) is a user facility for all areas of neutron research proposed for construction at the Oak Ridge National Laboratory. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements [which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies] into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences. 8 refs., 2 tabs

  12. The Advanced Neutron Source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1990-01-01

    The Advanced Neutron Source (ANS) is a user facility proposed for construction at the Oak Ridge National Laboratory for all areas of neutron research. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements (which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies) into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences

  13. Safety analysis on Non-LOCA events for the revision of Wolsong NPP unit 2,3,4 sar

    International Nuclear Information System (INIS)

    Kim, Jong Hyun; Jin, Dong Sik; Ryu, Eui Seung; Kho, Dong Wook; Kim, Sung Min

    2015-01-01

    Korean Wolsong Nuclear Power Plant Units 2,3,4 (CANDU-6 Type) has prepared the revision of safety analysis report (Final Safety Analysis Report (FSAR) chapter 15) from the original performed in the year of 1990s, using the updated and state-of-the-art methodology and tools including IST safety analysis codes and more detail modelling. Compared with the original FSAR15, the revised FSAR15 has significant improvement in both the scope and the depth of safety analysis, which has demonstrated the safety analysis results have complied with the safety requirements(acceptance criteria). This paper will present the analysis scope for Non-LOCA events re-analyzed or added for the FSAR15 revision, methodologies applied such as codes and modelling and some important analysis results will be demonstrated with comparison to acceptance criteria. Application of more detail and near-realistic assumptions and method including Dev-PDO options and uncertainty related to the CHF correlations has altogether brought about more safety margin compared with the original FSAR15 with respect to SDS trip effectiveness etc. (author)

  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. Plan for safety case of spent fuel repository at Olkiluoto

    International Nuclear Information System (INIS)

    Vieno, T.; Ikonen, A.T.K.

    2005-02-01

    Posiva aims to present the Safety Case supporting the construction license application of the spent fuel repository at Olkiluoto by 2012. An outline and preliminary assessments will be presented in 2009. Interim reporting and an update of the Safety Case plan will be presented in 2006, as required by the authorities. The KBS-3 disposal concept aims at long-term isolation and containment of spent fuel assemblies in durable copper-iron canisters emplaced in a repository to be constructed at a depth between 400 and 600 metres in crystalline bedrock. By 2012, studies on the KBS-3 disposal concept and site investigations at Olkiluoto will have been continued over about thirty years. The construction of an underground rock characterisation facility (called ONKALO) was started in June 2004. The investigations are carried out in close cooperation with the Swedish SKB developing and assessing the same disposal concept at candidate sites, resembling Olkiluoto, at the other side of the Baltic Sea. A safety case is the synthesis of evidence, analyses and arguments that quantify and substantiate the safety, and the level of expert confidence in the safety, of a planned repository. Posiva's Safety Case will be organised in a portfolio including ten main reports, which will be periodically updated according the overall schedule presented in the plan. The Site report describing the present state and past evolution of the Olkiluoto site, as well as the disturbances caused by the construction of ONKALO and the first stage of the repository, forms the geoscientific basis of the Safety Case. The engineering basis is provided by the reports on the Characteristics of spent fuel, Canister design, and Repository design. The Process report containing descriptions and analyses of features, events and processes potentially affecting the disposal system, and the report on the Evolution of site and repository form the scientific basis of the Safety Case. The latter report will describe and

  16. A plan for safety and integrity of research reactor components

    International Nuclear Information System (INIS)

    Moatty, Mona S. Abdel; Khattab, M.S.

    2013-01-01

    Highlights: ► A plan for in-service inspection of research reactor components is put. ► Section XI of the ASME Code requirements is applied. ► Components subjected to inspection and their classes are defined. ► Flaw evaluation and its acceptance–rejection criteria are reviewed. ► A plan of repair or replacement is prepared. -- Abstract: Safety and integrity of a research reactor that has been operated over 40 years requires frequent and thorough inspection of all the safety-related components of the facility. The need of increasing the safety is the need of improving the reliability of its systems. Diligent and extensive planning of in-service inspection (ISI) of all reactor components has been imposed for satisfying the most stringent safety requirements. The Safeguards Officer's responsibilities of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code ASME Code have been applied. These represent the most extensive and time-consuming part of ISI program, and identify the components subjected to inspection and testing, methods of component classification, inspection and testing techniques, acceptance/rejection criteria, and the responsibilities. The paper focuses on ISI planning requirements for welded systems such as vessels, piping, valve bodies, pump casings, and control rod-housing parts. The weld in integral attachments for piping, pumps, and valves are considered too. These are taken in consideration of safety class (1, 2, 3, etc.), reactor age, and weld type. The parts involve in the frequency of inspection, the examination requirements for each inspection, the examination method are included. Moreover the flaw evaluation, the plan of repair or replacement, and the qualification of nondestructive examination personnel are considered

  17. 76 FR 23630 - Office of New Reactors; Proposed Revision 2 to Standard Review Plan, Section 1.0 on Introduction...

    Science.gov (United States)

    2011-04-27

    ... Standard Review Plan, Section 1.0 on Introduction and Interfaces AGENCY: Nuclear Regulatory Commission (NRC... Revision 2 to Standard Review Plan (SRP), Section 1.0, ``Introduction and Interfaces'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110110573). The Office of New Reactors (NRO...

  18. 76 FR 31381 - Office Of New Reactors; Proposed Revision 4 to Standard Review Plan; Section 8.1 on Electric...

    Science.gov (United States)

    2011-05-31

    ... Standard Review Plan; Section 8.1 on Electric Power--Introduction AGENCY: U.S. Nuclear Regulatory...,'' on a proposed Revision 4 to Standard Review Plan (SRP), Section 8.1 on ``Electric Power--Introduction,'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111180542). The previous version of...

  19. 75 FR 15723 - Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for the Mariana Fruit...

    Science.gov (United States)

    2010-03-30

    ... Wildlife Service, announce the availability of the Draft Revised Recovery Plan for the Mariana Fruit Bat or... and assistance of a Recovery Team appointed by the U.S. Fish and Wildlife Service. Section 4(f) of the... life history and ecology, this recovery plan focuses on the first 10 years of the recovery process. As...

  20. 76 FR 38575 - Endangered and Threatened Wildlife and Plants; Revised Recovery Plan for the Northern Spotted Owl...

    Science.gov (United States)

    2011-07-01

    ... document availability: revised recovery plan. SUMMARY: We, the U.S. Fish and Wildlife Service, announce the... concluded that the integrity of the agency decisionmaking process for the spotted owl recovery plan was... DEPARTMENT OF THE INTERIOR Fish and Wildlife Service 50 CFR Part 17 [FWS-R1-ES-2011-N020; 10120...

  1. 75 FR 25778 - Revisions to the California State Implementation Plan, Yolo-Solano Air Quality Management District

    Science.gov (United States)

    2010-05-10

    ... the California State Implementation Plan, Yolo- Solano Air Quality Management District AGENCY... approve revisions to the Yolo-Solano Air Quality Management District (YSAQMD) portion of the California... Identification of plan. * * * * * (c) * * * (377) * * * (i) * * * (B) Yolo Solano Air Quality Management District...

  2. 77 FR 23193 - Revisions to the California State Implementation Plan, Yolo-Solano Air Quality Management District

    Science.gov (United States)

    2012-04-18

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0180; FRL-9652-3] Revisions to the California State Implementation Plan, Yolo- Solano Air Quality Management District AGENCY... the Yolo-Solano Air Quality Management District portion of the California State Implementation Plan...

  3. 77 FR 24975 - Endangered and Threatened Wildlife and Plants; Revised Recovery Plan for the Utah Prairie Dog

    Science.gov (United States)

    2012-04-26

    ...-FF06E00000] Endangered and Threatened Wildlife and Plants; Revised Recovery Plan for the Utah Prairie Dog... Utah prairie dog (Cynomys parvidens). This species is federally listed as threatened under the... recovery plan for the Utah prairie dog. The Service and other Federal agencies also will take these...

  4. Nuclear waste: Department of Energy's Transuranic Waste Disposal Plan needs revision

    International Nuclear Information System (INIS)

    1986-01-01

    Transuranic waste consists of discarded tools, rags, machinery, paper, sheet metal, and glass containing man-made radioactive elements that can be dangerous if inhaled, ingested, or absorbed into the body through an open wound. GAO found that the Defense Waste Management Plan does not provide the Congress with complete inventory and cost data or details on environmental and safety issues related to the permanent disposal of TRU waste; the Plan's $2.8 billion costs are understated by at least $300 million. Further, it does not include costs for disposing of buried waste, contaminated soil, and TRU waste that may not be accepted at the Waste Isolation Pilot Plant. Lastly, the Plan provides no details on the environmental and safety issues related to the permanent disposal of TRU waste, nor does it discuss the types of or timing for environmental analyses needed before WIPP starts operating

  5. Expedited technology demonstration project. Project baseline revision 2.2 and FY96 plan

    International Nuclear Information System (INIS)

    1996-07-01

    The Expedited Technology Demonstration Project Plan, Mixed Waste Management Facility (MWMF) current baseline. The revised plan will focus efforts specifically on the demonstration of an integrated Molten Salt Oxidation (MSO) system. In addition to the MSO primary unit, offgas, and salt recycle subsystems, the demonstrations will include feed preparation and feed delivery systems, and the generation of robust final forms from process mineral residues. A simplified process flow chart for the expedited demonstration is provided. To minimize costs and to accelerate the schedule for deployment, the integrated system will be staged in an existing facility at LLNL equipped to handle hazardous and radioactive materials. The MSO systems will be activated in fiscal year 97, followed by the activation of feed preparation and final forms in fiscal year 98

  6. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-06-13

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations.

  7. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    International Nuclear Information System (INIS)

    Sweeney, M.D.

    1995-01-01

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations

  8. 76 FR 28944 - Revisions to the California State Implementation Plan, Placer County Air Pollution Control...

    Science.gov (United States)

    2011-05-19

    ...EPA is proposing a limited approval and limited disapproval of permitting rules submitted for the Placer County Air Pollution Control District (PCAPCD) and Feather River Air Quality Management District (FRAQMD) portion of the California State Implementation Plan (SIP). The districts are required under Part D of title I of the Clean Air Act (CAA) to adopt and implement a SIP-approved New Source Review (NSR) permit program. These rules update and revise the District's NSR permitting program for new and modified sources of air pollution. If EPA finalizes the limited approval and limited disapproval action, as proposed, then a sanctions clock would be triggered. We are taking comments on this proposal and plan to follow with a final action.

  9. Revising superior planning performance in chess players: the impact of time restriction and motivation aspects.

    Science.gov (United States)

    Unterrainer, Josef Martin; Kaller, Christoph Philipp; Leonhart, Rainer; Rahm, Benjamin

    2011-01-01

    In a previous study (Unterrainer, Kaller, Halsband, & Rahm, 2006), chess players outperformed non-chess players in the Tower of London planning task but exhibited disproportionately longer processing times. This pattern of results raises the question of whether chess players' planning capabilities are superior or whether the results reflect differences in the speed-accuracy trade-off between the groups, possibly attributable to sports motivation. The present study was designed to disambiguate these alternative suggestions by implementing various constraints on planning time and by assessing self-reported motivation. In contrast to the previous study, chess players' performance was not superior, independently of whether problems had to be solved with (Experiment 1) or without (Experiment 2) time limits. As expected, chess players reported higher overall trait and state motivation scores across both experiments. These findings revise the notion of superior planning performance in chess players. In consequence, they do not conform with the assumption of a general transfer of chess-related planning expertise to other cognitive domains, instead suggesting that superior performance may be possible only under specific circumstances such as receiving competitive instructions.

  10. Underground Test Area Activity Quality Assurance Plan Nevada National Security Site, Nevada. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Krenzien, Susan [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States); Farnham, Irene [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States)

    2015-06-01

    This Quality Assurance Plan (QAP) provides the overall quality assurance (QA) requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) Underground Test Area (UGTA) activities. The requirements in this QAP are consistent with DOE Order 414.1D, Change 1, Quality Assurance (DOE, 2013a); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). If a participant’s requirement document differs from this QAP, the stricter requirement will take precedence. NNSA/NFO, or designee, must review this QAP every two years. Changes that do not affect the overall scope or requirements will not require an immediate QAP revision but will be incorporated into the next revision cycle after identification. Section 1.0 describes UGTA objectives, participant responsibilities, and administrative and management quality requirements (i.e., training, records, procurement). Section 1.0 also details data management and computer software requirements. Section 2.0 establishes the requirements to ensure newly collected data are valid, existing data uses are appropriate, and environmental-modeling methods are reliable. Section 3.0 provides feedback loops through assessments and reports to management. Section 4.0 provides the framework for corrective actions. Section 5.0 provides references for this document.

  11. Underground Test Area Activity Quality Assurance Plan Nevada National Security Site, Nevada. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Farnham, Irene [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States); Krenzien, Susan [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States)

    2012-10-01

    This Quality Assurance Plan (QAP) provides the overall quality assurance (QA) requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) activities. The requirements in this QAP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). NNSA/NSO, or designee, must review this QAP every two years. Changes that do not affect the overall scope or requirements will not require an immediate QAP revision but will be incorporated into the next revision cycle after identification. Section 1.0 describes UGTA objectives, participant responsibilities, and administrative and management quality requirements (i.e., training, records, procurement). Section 1.0 also details data management and computer software requirements. Section 2.0 establishes the requirements to ensure newly collected data are valid, existing data uses are appropriate, and environmental-modeling methods are reliable. Section 3.0 provides feedback loops through assessments and reports to management. Section 4.0 provides the framework for corrective actions. Section 5.0 provides references for this document.

  12. A tailored online safety and health intervention for women experiencing intimate partner violence: the iCAN Plan 4 Safety randomized controlled trial protocol

    Directory of Open Access Journals (Sweden)

    Marilyn Ford-Gilboe

    2017-03-01

    Full Text Available Abstract Background Intimate partner violence (IPV threatens the safety and health of women worldwide. Safety planning is a widely recommended, evidence-based intervention for women experiencing IPV, yet fewer than 1 in 5 Canadian women access safety planning through domestic violence services. Rural, Indigenous, racialized, and immigrant women, those who prioritize their privacy, and/or women who have partners other than men, face unique safety risks and access barriers. Online IPV interventions tailored to the unique features of women’s lives, and to maximize choice and control, have potential to reduce access barriers, and improve fit and inclusiveness, maximizing effectiveness of these interventions for diverse groups. Methods/Design In this double blind randomized controlled trial, 450 Canadian women who have experienced IPV in the previous 6 months will be randomized to either a tailored, interactive online safety and health intervention (iCAN Plan 4 Safety or general online safety information (usual care. iCAN engages women in activities designed to increase their awareness of safety risks, reflect on their plans for their relationships and priorities, and create a personalize action plan of strategies and resources for addressing their safety and health concerns. Self-reported outcome measures will be collected at baseline and 3, 6, and 12 months post-baseline. Primary outcomes are depressive symptoms (Center for Epidemiological Studies Depression Scale, Revised and PTSD Symptoms (PTSD Checklist, Civilian Version. Secondary outcomes include helpful safety actions, safety planning self-efficacy, mastery, and decisional conflict. In-depth qualitative interviews with approximately 60 women who have completed the trial and website utilization data will be used to explore women’s engagement with the intervention and processes of change. Discussion This trial will contribute timely evidence about the effectiveness of online safety and

  13. Probabilistic safety analysis procedures guide. Sections 1-7 and appendices. Volume 1, Revision 1

    International Nuclear Information System (INIS)

    Bari, R.A.; Buslik, A.J.; Cho, N.Z.

    1985-08-01

    A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. This first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. The second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

  14. Effects of the Original Versus Revised Bloom's Taxonomy on Lesson Planning Skills: A Turkish Study Among Pre-Service Teachers

    Science.gov (United States)

    Bümen, Nilay T.

    2007-07-01

    The original taxonomy of educational objectives, developed by Benjamin S.␣Bloom and his associates in the 1950s, was revised several decades later by a group of educationists and cognitive psychologists, who developed a revised taxonomy (RT). This article describes a Turkish study carried out among a group of pre-service teachers in order to compare the influence of the two systems on lesson planning skills. The results confirmed other studies that have indicated a number of advantages of the revised system over the earlier one.

  15. Safety assessment plans for authorization and inspection of radiation sources

    International Nuclear Information System (INIS)

    2002-05-01

    The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

  16. Safety assessment plans for authorization and inspection of radiation sources

    International Nuclear Information System (INIS)

    1999-09-01

    The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

  17. 218-E-8 Borrow Pit Demolition Site closure plan. Revision 1

    International Nuclear Information System (INIS)

    Ruck, F.R.

    1994-01-01

    The 218-E-8 Demolition Site was the site of a single demolition event in November of 1984. This demolition event was a form of thermal treatment for discarded explosive chemical products. Because the 218-E-8 Demolition Site will no longer be used for this thermal activity, the site will be closed. Closure will be conducted pursuant to the requirements of the Washington State Department of Ecology (Ecology) ''Dangerous Waste Regulations,'' Washington Administrative Code (WAC) 173-303-610 and 40 Code of Federal Regulations (CFR) 270.1. The 218-E-8 Borrow Pit Demolition Site Closure Plan consists of a Hanford Facility Dangerous Waste Part A Permit Application, Form 3, Revision 4, and a closure plan. An explanation of the Part A Form 3, submitted with this closure plan is provided at the beginning of the Part A Section. The closure plan consists of nine chapters and five appendices. This closure plan presents a description of the 218-E-8 Demolition Site, the history of the waste treated, and the approach that will be followed to close the 218-E-8 Demolition Site. Because there were no radioactively contaminated chemicals involved in t he demolitions at the 218-E-8 Borrow Pit site, the information on radionuclides is provided for ''information only.'' Remediation of any radioactive contamination is not within the scope of this closure plan. Only dangerous constituents derived from 218-E-8 Demolition Site operations will be addressed in this closure plan in accordance with WAC 173-303-610(2)(b)(i)

  18. Sodium Fast Reactor Safety and Licensing Research Plan

    International Nuclear Information System (INIS)

    Denman, Matthew; Lachance, Jeff; Sofu, Tanju; Wigeland, Roald; Flanagan, George; Bari, Robert

    2013-01-01

    Conclusions: The Sodium Fast Reactor Safety and Licensing Research Plan reports conclude a multi-year expert elicitation process. All information included in the studies are publicly available and the reports are UUR. These reports are intended to guide SFR researchers in the safety and licensing arena to important and outstanding issues Two (and a half) projects have been funded based on the recommendations in this report: • Modernization of SAS4A; • Incorporation of Contain/LMR with MELCOR; • (Data recovery at INL and PNNL)

  19. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.; Rockwell, V.S.

    1992-08-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization plans for Word Processors, Personal Computers, Workstations, and Associated Software (ANL/TM, Revision 4) to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference document that (1) documents the plans of each organization for office automation, (2) identifies appropriate planners and other contact people in those organizations and (3) encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations (ANL/TM 458) and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan (ANL/TM 466).

  20. The emergency plan of the ININ

    International Nuclear Information System (INIS)

    Ruiz C, M.A.

    1991-01-01

    The emergency plan of the ININ, it was elaborated in 1988 and revised by the National Commission of Nuclear Safety and Safeguards (CNSNS) in 1989. At the beginning of 1990 and with the support of the IAEA it was practiced the first revision to the text of this plan, for what the proposal revision is what constitutes the development of this report

  1. Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    2013-01-01

    The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

  2. Revised Master Plan for the Hood River Production Program, Technical Report 2008.

    Energy Technology Data Exchange (ETDEWEB)

    Oregon Department of Fish and Wildlife; Confederated Tribes of the Warm Springs Reservation

    2008-04-28

    The Hood River Production Program (HRPP) is a Bonneville Power Administration (BPA) funded program initiated as a mitigation measure for Columbia River hydrosystem effects on anadromous fish. The HRPP began in the early 1990s with the release of spring Chinook and winter steelhead smolts into the basin. Prior to implementation, co-managers, including the Confederated Tribes of the Warm Springs Reservation and the Oregon Department of Fish and Wildlife drafted the Hood River Production Master Plan (O'Toole and ODFW 1991a; O'Toole and ODFW 1991b) and the Pelton Ladder Master Plan (Smith and CTWSR 1991). Both documents were completed in 1991 and subsequently approved by the Council in 1992 and authorized through a BPA-led Environmental Impact Statement in 1996. In 2003, a 10-year programmatic review was conducted for BPA-funded programs in the Hood River (Underwood et al. 2003). The primary objective of the HRPP Review (Review) was to determine if program goals were being met, and if modifications to program activities would be necessary in order to meet or revise program goals. In 2003, an agreement was signed between PacifiCorp and resource managers to remove the Powerdale Dam (RM 10) and associated adult trapping facility by 2010. The HRPP program has been dependant on the adult trap to collect broodstock for the hatchery programs; therefore, upon the dam's removal, some sort of replacement for the trap would be needed to continue the HRPP. At the same time the Hood River Subbasin Plan (Coccoli 2004) was being written and prompted the co-managers to considered future direction of the program. This included revising the numerical adult fish objectives based on the assimilated data and output from several models run on the Hood River system. In response to the Review as well as the Subbasin Plan, and intensive monitoring and evaluation of the current program, the HRPP co-managers determined the spring Chinook program was not achieving the HRPP

  3. Therapeutic risk management of the suicidal patient: safety planning.

    Science.gov (United States)

    Matarazzo, Bridget B; Homaifar, Beeta Y; Wortzel, Hal S

    2014-05-01

    This column is the fourth in a series describing a model for therapeutic risk management of the suicidal patient. Previous columns presented an overview of the therapeutic risk management model, provided recommendations for how to augment risk assessment using structured assessments, and discussed the importance of risk stratification in terms of both severity and temporality. This final column in the series discusses the safety planning intervention as a critical component of therapeutic risk management of suicide risk. We first present concerns related to the relatively common practice of using no-suicide contracts to manage risk. We then present the safety planning intervention as an alternative approach and provide recommendations for how to use this innovative strategy to therapeutically mitigate risk in the suicidal patient.

  4. TWRS safety and technical integration risk management plan

    International Nuclear Information System (INIS)

    Fordham, R.A.

    1996-01-01

    The objectives of the Tank Waste Remediation System (TWRS) Safety and Technical Integration (STI) programmatic risk management program are to assess, analyze, and handle risks associated with TWRS STI responsibilities and to communicate information about the actions being taken and the results to enable decision making. The objective of this TWRS STI Risk Management Plan is to communicate a consistent approach to risk management that will be used by the organization

  5. Planning and architectural safety considerations in designing nuclear power plants

    International Nuclear Information System (INIS)

    Konsowa, Ahmed A.

    2009-01-01

    To achieve optimum safety and to avoid possible hazards in nuclear power plants, considering architectural design fundamentals and all operating precautions is mandatory. There are some planning and architectural precautions should be considered to achieve a high quality design and construction of nuclear power plant with optimum safety. This paper highlights predicted hazards like fire, terrorism, aircraft crash attacks, adversaries, intruders, and earthquakes, proposing protective actions against these hazards that vary from preventing danger to evacuating and sheltering people in-place. For instance; using safeguards program to protect against sabotage, theft, and diversion. Also, site and building well design focusing on escape pathways, emergency exits, and evacuation zones, and the safety procedures such as; evacuation exercises and sheltering processes according to different emergency classifications. In addition, this paper mentions some important codes and regulations that control nuclear power plants design, and assessment methods that evaluate probable risks. (author)

  6. 77 FR 42462 - Hawaii State Plan for Occupational Safety and Health; Proposed Modification of 18(e) Plan Approval

    Science.gov (United States)

    2012-07-19

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration 29 CFR Part 1952 [Docket ID. OSHA 2012-0029] RIN 1218-AC78 Hawaii State Plan for Occupational Safety and Health; Proposed Modification of 18(e) Plan Approval AGENCY: Occupational Safety and Health Administration (OSHA), Department of...

  7. Health and safety plan for operations performed for the Environmental Restoration Program

    International Nuclear Information System (INIS)

    Trippet, W.A. II; Reneau, M.; Morton, S.L.

    1992-04-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG ampersand G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP

  8. Health and safety plan for operations performed for the Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Trippet, W.A. II (IT Corp., (United States)); Reneau, M.; Morton, S.L. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

    1992-04-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP.

  9. 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

  10. Independent Safety Assessment of the TOPAZ-II space nuclear reactor power system (Revised)

    International Nuclear Information System (INIS)

    1993-09-01

    The Independent Safety Assessment described in this study report was performed to assess the safety of the design and launch plans anticipated by the U.S. Department of Defense (DOD) in 1993 for a Russian-built, U.S.-modified, TOPAZ-II space nuclear reactor power system. Its conclusions, and the bases for them, were intended to provide guidance for the U.S. Department of Energy (DOE) management in the event that the DOD requested authorization under section 91b. of the Atomic Energy Act of 1954, as amended, for possession and use (including ground testing and launch) of a nuclear-fueled, modified TOPAZ-II. The scientists and engineers who were engaged to perform this assessment are nationally-known nuclear safety experts in various disciplines. They met with participants in the TOPAZ-II program during the spring and summer of 1993 and produced a report based on their analysis of the proposed TOPAZ-II mission. Their conclusions were confined to the potential impact on public safety and did not include budgetary, reliability, or risk-benefit analyses

  11. Revised Fifth Five Year Economic and Social Development Plan, 1984-1986.

    Science.gov (United States)

    1987-01-01

    This document contains provisions of chapter 6 (Promoting Social Development) of the Revised Fifth Five-Year Economic and Social Development Plan (1984-86) of the Republic of Korea. The plan calls for the efficient control of population growth by targeting intensive efforts to women 20-30 years old, eradicating the traditional preference for male children, providing incentives to foster a small family norm, and discouraging couples from having too many children. Family planning (FP) programs will be expanded to increase the contraceptive prevalence rate and improve the quality of contraceptive services. Emphasis will be placed on women 34 years or younger residing in poor urban and remote rural areas. The emphasis of the evaluations of FP guidance and evaluation teams will be on the actual prevention of birth rather than on the contraceptive use ratio, and the FP program will be linked to other health and medical schemes. Families with 2 children or less will receive extended medical services and free kindergarten tuition. Families with 3 or more children may face discriminatory policy measures. The Family Law will be amended to allow daughters to inherit, the Medical Insurance Law will be changed to allow family members dependent upon female workers to be insured, and social institutions hindering female participation in the work force will be banned. The dissemination of FP information and population education will be expanded.

  12. Westinghouse Hanford Company plan for certifying newly generated contact -- handled transuranic waste. Revision 1

    International Nuclear Information System (INIS)

    Lipinski, R.M.; Backlund, E.G.

    1995-09-01

    All transuranic (TRU) waste generators are required by US Department of Energy (DOE) Order 5820.2A to package their TRU waste in order to comply wit the Waste Isolation Pilot Plant (WIPP) -- Waste Acceptance Criteria (WAC) or keep non-certifiable containers segregated. The Westinghouse Hanford Company (WHC) Transuranic Waste Certification Plan was developed to ensure that TRU newly generated waste at WHC meets the DOE Order 5820.2A and the WHC-WAC which includes the State of Washington Department of Ecology -- Washington Administrative Code (DOE-WAC). The metho used at WHC to package TRU waste are described in sufficient detail to meet the regulations. This document is organized to provide a brief overview of waste generation operations at WHC. The methods used to implement this plan are discussed briefly along with the responsibilities and authorities of applicable organizations. This plan describes how WHC complies with all applicable regulations and requirements set forth in the latest approved revision of WHC-EP-0063-4

  13. Bioconversion of plant biomass to ethanol. Annual report and revised research plan, January 1977--January 1978

    Energy Technology Data Exchange (ETDEWEB)

    Brooks, R.E.; Bellamy, W.D.; Su, T.M.

    1978-03-23

    The objective of this research is to demonstrate on a laboratory scale the technical feasibility of the direct microbial conversion of pretreated wood to ethanol. During the first year of this contract, we investigated the feasibility of biologically delignifying wood with C. pruinosum and directly fermenting the pretreated wood to ethanol with a mixed culture. Bench-top fermentations of a thermophilic bacillus growing on glucose and of a mixed culture of thermophilic sporocytophaga (US) and a thermophilic bacillus growing on microcrystalline and amorphous cellulose were evaluated for growth and ethanol production. In the mixed culture fermentation of amorphous and microcrystalline cellulose, the specific rate of substrate depletion was calculated to be 0.087 hr/sup -1/ and 0.0346 hr/sup -1/, respectively. However, defining the growth requirements of C. pruinosum and sporocytophaga (US) proved more difficult than originally anticipated. In order to achieve the program objectives within the contract period, a revised research plan was developed based upon chemical pretreatment and the direct fermentation of pretreated hardwood to ethanol. In place of the biological delignification pretreatment step, we have substituted a chemically supplemented steam pretreatment step to partially delignify wood and to enhance its accessibility to microbial utilization. Clostridium thermocellum, which ferments cellulose directly to ethanol and acetic acid, has replaced the mixed culture fermentation stage for ethanol production. Research on the production of ethanol from xylose by the thermophilic bacillus ZB-B2 is retained as one means of utilizing the hemicellulose fraction of hardwood. Work on the genetic improvement of the ethanol yields of both cultures by suppressing acetic acid production is also retained. The rationale, experimental approach, and economic considerations of this revised research plan are also presented.

  14. Plan of Nordic research in nuclear safety 1994-97

    International Nuclear Information System (INIS)

    1993-04-01

    A new four-year Nordic research programme in the field of nuclear safety and radiation protection is to start in 1994 as a followup of several preceding Nordic programmes. It will include seven projects and a joint coordination function. The programme is intended to sustain a common understanding among safety authorities in the Nordic countries with respect to reactor safety and radiation protection. It mainly deals with questions that are actual within the Nordic region, but it may also include problems of concern to its eastern neighbours. Two of the projects deal with reactor safety, and one with radioactive waste. The other four projects are on environmental aspects: two of them deal with radioecology, and two with questions related to emergency preparedness. The programme is managed by the Nordic Committee for Safety Research, NKS, consisting of representatives from regulatory authorities, research bodies, and industry. Basic financing is provided by one consortium member from each of the five Nordic countries, whereby an annual budget of approximately 8 million Danish Kroner will be provided. Additional financing comes from sponsors interested in the programme as well as from those organizations taking part in the project work. Definite project plans are to be elaborated within the more general frames described in the present outline. The flexibility of the programme is enhanced by limiting the duration of individual activities to one or two years. This will make it possible to adjust the programme to actual needs in the Nordic countries. (au)

  15. The emergency plan of the ININ; El plan de emergencia del ININ

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz C, M A [ININ, Salazar, Estado de Mexico (Mexico)

    1991-07-01

    The emergency plan of the ININ, it was elaborated in 1988 and revised by the National Commission of Nuclear Safety and Safeguards (CNSNS) in 1989. At the beginning of 1990 and with the support of the IAEA it was practiced the first revision to the text of this plan, for what the proposal revision is what constitutes the development of this report.

  16. 12 CFR 308.303 - Filing of safety and soundness compliance plan.

    Science.gov (United States)

    2010-01-01

    ... time within which those steps will be taken. (c) Review of safety and soundness compliance plans... PRACTICE RULES OF PRACTICE AND PROCEDURE Submission and Review of Safety and Soundness Compliance Plans and... compliance plan. (a) Schedule for filing compliance plan—(1) In general. A bank shall file a written safety...

  17. 76 FR 17808 - Final Vehicle Safety Rulemaking and Research Priority Plan 2011-2013

    Science.gov (United States)

    2011-03-31

    ... [Docket No. NHTSA-2009-0108] Final Vehicle Safety Rulemaking and Research Priority Plan 2011- 2013 AGENCY... availability. SUMMARY: This document announces the availability of the Final NHTSA Vehicle Safety and Fuel.... This Priority Plan is an update to the Final Vehicle Safety Rulemaking and Research Priority Plan 2009...

  18. Planned revision to DOE Order 5820.2A, Radioactive Waste Management

    Energy Technology Data Exchange (ETDEWEB)

    Duggan, G.J. [Dept. of Energy, Washington, DC (United States); Williams, R.E.; Kudera, D.E. [EG and G Idaho, Inc., Idaho Falls, ID (United States). Idaho National Engineering Lab.; Bailey, D.E. [NJG, Inc. (United States)

    1993-03-01

    US Department of Energy Headquarters initiated efforts to revise DOE Order 5820.2A, ``Radioactive Waste Management``. The purpose of the revision is to enhance DOE waste management requirements, reflect new DOE organizational responsibilities, and consolidate requirements for management of all waste, under the responsibility of Environmental Restoration and Waste Management, into a single order. This paper discusses the revision philosophy, objectives of the revision, and strategy for the revision. Issues being considered for inclusion in the revision and recommended methods of resolving each issue are also discussed.

  19. Intersection planning in Safer Transportation Network Planning : safety principles, planning framework, and library information.

    NARCIS (Netherlands)

    Hummel, T.

    2001-01-01

    This report is one in a series of publications, used in the development of the network planning tool ‘Safer Transportation Network Planning’ (Safer-TNP). The publications were used to guide the development of planning structures, diagnostic tools, planning recommendations, and research information

  20. Land use planning in Safer Transportation Network Planning : safety principles, planning framework, and library information.

    NARCIS (Netherlands)

    Hummel, T.

    2001-01-01

    This report is one in a series of publications, used in the development of the network planning tool ‘Safer Transportation Network Planning’ (Safer-TNP). The publications were used to guide the development of planning structures, diagnostic tools, planning recommendations, and research information

  1. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  2. 76 FR 55581 - Revision to the California State Implementation Plan; Yolo-Solano Air Quality Management District

    Science.gov (United States)

    2011-09-08

    ... California State Implementation Plan; Yolo-Solano Air Quality Management District AGENCY: Environmental... revision to the Yolo-Solano Air Quality Management District portion of the California State Implementation...-Solano Air Quality Management District (YSAQMD) Rule 2.41, adopted on September 10, 2008, and submitted...

  3. 77 FR 23133 - Revisions to the California State Implementation Plan, Yolo-Solano Air Quality Management District

    Science.gov (United States)

    2012-04-18

    ... the California State Implementation Plan, Yolo- Solano Air Quality Management District AGENCY... approve revisions to the Yolo-Solano Air Quality Management District (Yolo-Solano AQMD) portion of the.... * * * * * (381) * * * (i) * * * (I) Yolo-Solano Air Quality Management District. (1) Rule 2.3, ``Ringelmann Chart...

  4. 78 FR 47241 - Amendments to the Water Quality Regulations, Water Code and Comprehensive Plan To Revise the...

    Science.gov (United States)

    2013-08-05

    ... DELAWARE RIVER BASIN COMMISSION 18 CFR Part 410 Amendments to the Water Quality Regulations, Water Code and Comprehensive Plan To Revise the Human Health Water Quality Criteria for PCBs in Zones 2... hold a public hearing to receive comments on proposed amendments to the Commission's Water Quality...

  5. 76 FR 53482 - Endangered and Threatened Wildlife and Plants; Notice of Availability of a Revised Recovery Plan...

    Science.gov (United States)

    2011-08-26

    ... and revised the recovery plan accordingly. The desert tortoise is a large, herbivorous reptile that... tortoise populations. Disease and increased incidence of fire in the Mojave Desert have also been... tortoises, there are few data available to evaluate or quantify the effects of threats on desert tortoise...

  6. Planning the Marketing Strategy. PACE Revised. Level 3. Unit 6. Research & Development Series No. 240CB6.

    Science.gov (United States)

    Ashmore, M. Catherine; Pritz, Sandra G.

    This individualized, competency-based unit on planning marketing strategy, the sixth of 18 modules, is on the third level of the revised Program for Acquiring Competence in Entrepreneurship (PACE). Intended for the advanced secondary and postsecondary levels and for adults wanting training or retraining, this unit, together with the other…

  7. Planning the Marketing Strategy. PACE Revised. Level 2. Unit 6. Research & Development Series No. 240BB6.

    Science.gov (United States)

    Ashmore, M. Catherine; Pritz, Sandra G.

    This unit on planning marketing strategy for a small business, the sixth in a series of 18 modules, is on the second level of the revised PACE (Program for Acquiring Competence in Entrepreneurship) comprehensive curriculum. Geared to advanced secondary and beginning postsecondary or adult students, the modules provide an opportunity to learn about…

  8. 40 CFR Appendix A to Subpart III... - States With Approved State Implementation Plan Revisions Concerning CAIR SO2 Opt-In Units

    Science.gov (United States)

    2010-07-01

    ... Implementation Plan Revisions Concerning CAIR SO2 Opt-In Units A Appendix A to Subpart III of Part 97 Protection... BUDGET TRADING PROGRAM AND CAIR NOX AND SO2 TRADING PROGRAMS CAIR SO2 Opt-in Units Pt. 97, Subpt. III... Concerning CAIR SO2 Opt-In Units 1. The following States have State Implementation Plan revisions under § 51...

  9. Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

    International Nuclear Information System (INIS)

    1991-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  10. Revised ground-water monitoring compliance plan for the 183-H Solar Evaporation Basins

    International Nuclear Information System (INIS)

    1986-09-01

    This document contains ground-water monitoring plans for a mixed waste storage facility located on the Hanford Site in southeastern Washington State. This facility has been used since 1973 for storage of mixed wastes, which contain both chemicals and radionuclides. The ground-water monitoring plans presented here represent revision and expansion of an effort in June 1985. At that time, a facility-specific monitoring program was implemented at the 183-H Basins as part of the regulatory compliance effort being conducted on the Hanford Site. This monitoring program was based on the ground-water monitoring requirements for interimstatus facilities, which are those facilities that do not yet have final permits, but are authorized to continue interim operations while engaged in the permitting process. The program initially implemented for the 183-H Basins was designed to be an alternate program, which is required instead of the standard detection program when a facility is known or suspected to have contaminated the ground water in the uppermost aquifer. This effort, named the RCRA Compliance Ground-Water Monitoring Project for the 183-H Basins, was implemented. A supporting project involving ground-water flow modeling for the area surrounding the 183-H Basins was also initiated during 1985. Those efforts and the results obtained are described in subsequent chapters of this document. 26 refs., 55 figs., 14 tabs

  11. Implementing the 2012 North American Waterfowl Management Plan revision: Populations, habitat, and people

    Science.gov (United States)

    Humburg, Dale D.; Anderson, Michael G.; Brasher, Michael G.; Carter, Michael F.; Eadie, John M.; Fulton, David C.; Johnson, Fred A.; Runge, Michael C.; Vrtiska, Mark P.

    2018-01-01

    The North American Waterfowl Management Plan (NAWMP) has established a model for wildlife conservation planning over the last 3 decades. Management at a continental scale, leveraged funding, regional partnerships, and a strong science basis have been notable features. Periodic updates to the NAWMP occurred since implementation in 1986; however, a fundamental revision was accomplished in 2012 after extensive stakeholder engagement. An explicit fundamental goal for waterfowl conservation supporters was added in 2012, complementing existing goals for sustainable populations and sufficient habitat found in previous updates. We present a synopsis of progress toward implementation of the 2012 NAWMP and challenge the waterfowl management community to continue with meaningful steps toward achieving NAWMP goals. Adding goals and objectives for supporters increases potential relevance of NAWMP; however, it also presents a level of complexity that was not entirely anticipated. Additionally, the 2012 NAWMP recognized that traditional support from waterfowl hunters alone will not be sufficient to support waterfowl conservation in the future. Simultaneous consideration of multiple objectives, although implicit before, now is a specific focus for habitat and harvest management affecting hunters and other users of the waterfowl resource. The waterfowl management community is faced with revisiting objectives and management actions related to harvest regulations, landscape priorities, habitat conservation, and public engagement to garner broader support. These persistent management challenges are tangible and relevant candidates for greater integration. Ultimately, the structures and processes supporting waterfowl management also will need to be reconsidered.

  12. Groundwater Monitoring Plan for the Z-Area Saltstone Disposal Facility, Revision 3

    International Nuclear Information System (INIS)

    WELLS, DANIEL

    2005-01-01

    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. At the time of the 1996 permit renewal, it was determined that a more robust monitoring program was needed. The draft permit required new monitoring wells within 25 feet of each active disposal cell. As an alternative, 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), and was incorporated by reference into the Z-Area Saltstone Industrial Solid Waste Permit, No.025500-1603. The Industrial Solid Waste Landfill Regulations were revised in 1998 and now include specific requirements for groundwater monitoring. SRS's plan for complying with those regulations is discussed below. The plan calls for a return to traditional monitoring with permanent wells. It also proposes a more technically sound monitoring list based on the actual composition of saltstone

  13. National plan to enhance aviation safety through human factors improvements

    Science.gov (United States)

    Foushee, Clay

    1990-01-01

    The purpose of this section of the plan is to establish a development and implementation strategy plan for improving safety and efficiency in the Air Traffic Control (ATC) system. These improvements will be achieved through the proper applications of human factors considerations to the present and future systems. The program will have four basic goals: (1) prepare for the future system through proper hiring and training; (2) develop a controller work station team concept (managing human errors); (3) understand and address the human factors implications of negative system results; and (4) define the proper division of responsibilities and interactions between the human and the machine in ATC systems. This plan addresses six program elements which together address the overall purpose. The six program elements are: (1) determine principles of human-centered automation that will enhance aviation safety and the efficiency of the air traffic controller; (2) provide new and/or enhanced methods and techniques to measure, assess, and improve human performance in the ATC environment; (3) determine system needs and methods for information transfer between and within controller teams and between controller teams and the cockpit; (4) determine how new controller work station technology can optimally be applied and integrated to enhance safety and efficiency; (5) assess training needs and develop improved techniques and strategies for selection, training, and evaluation of controllers; and (6) develop standards, methods, and procedures for the certification and validation of human engineering in the design, testing, and implementation of any hardware or software system element which affects information flow to or from the human.

  14. Work plan, health and safety plan, and site characterization for the Rust Spoil Area (D-106)

    International Nuclear Information System (INIS)

    Bohrman, D.E.; Uziel, M.S.; Landguth, D.C.; Hawthorne, S.W.

    1990-06-01

    As part of the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) of the Department of Energy's Y-12 Plant located in Oak Ridge, Tennessee, this work plan has been developed for the Rust Spoil Area (a solid waste disposal area). The work plan was developed by the Measurement Applications and Development Group (MAD) of the Health and Safety Research Division (HASRD) at Oak Ridge National Laboratory (ORNL) and will be implemented jointly by ORNL/MAD and the Y-12 Environmental Surveillance Section. This plan consists of four major sections: (1) a project description giving the scope and objectives of the investigation at the Rust Spoil Area; (2) field and sampling procedures describing sample documentation, soil sampling techniques, sample packaging and preservation, equipment decontamination, and disposal of investigation generated wastes; (3) sample analysis procedures detailing necessary analytical laboratory procedures to ensure the quality of chemical results from sample receipt through analysis and data reporting; and (4) a health and safety plan which describes general site hazards and particular hazards associated with specific tasks, assigns responsibilities, establishes personnel protection standards and mandatory safety procedures, and provides emergency information for contingencies that may arise during the course of field operations

  15. Review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Tetsuya; Araki, Masaaki; Ohba, Toshinobu; Torii, Yoshiya [Japan Atomic Energy Agency, Tokai, Ibaraki (Japan); Takeuchi, Masaki [Nuclear Safety Commission (Japan)

    2012-03-15

    JRR-3(Japan Research Reactor No.3) with the thermal power of 20MW is a light water moderated and cooled, swimming pool type research reactor. JRR-3 has been operated without major troubles. This paper presents about review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors. In addition, some topics concerning damages in JRR-3 due to the Great East Japan Earthquake are presented. (author)

  16. Groundwater well services site safety and health plan

    International Nuclear Information System (INIS)

    Tuttle, B.G.

    1996-08-01

    This Site Specific Health and Safety Plan covers well servicing in support of the Environmental Restoration Contractor Groundwater Project. Well servicing is an important part of environmental restoration activities supporting several pump and treat facilities and assisting in evaluation and servicing of various groundwater wells throughout the Hanford Site. Remediation of contaminated groundwater is a major part of the ERC project. Well services tasks help enhance groundwater extraction/injection as well as maintain groundwater wells for sampling and other hydrologic testing and information gathering

  17. UMTRA project technical assistance contractor quality assurance implementation plan for surface and ground water, Revision 2

    International Nuclear Information System (INIS)

    1995-11-01

    This document contains the Technical Assistance Contractor (TAC) Quality Assurance Implementation Plan (QAIP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project. The QAIP outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QA program is designed to use monitoring, audit, and surveillance activities as management tools to ensure that UMTRA Project activities are carried out in amanner to protect public health and safety, promote the success of the UMTRA Project, and meet or exceed contract requirements

  18. Looking Back to Move Forward: Collaborative Planning to Revise the Green Mountain and Finger Lakes National Forests Land and Resource Management Plans

    Directory of Open Access Journals (Sweden)

    Michael J Dockry

    2015-07-01

    Full Text Available The United States Department of Agriculture Forest Service (Forest Service manages 154 national forests and 20 grasslands in 44 states and Puerto Rico. National Forest Land and Resource Management Plans (forest plans form the basis for land and resource management of national forests in the United States. For more than a decade the Forest Service has been attempting to incorporate innovative, collaborative public involvement strategies into the process for revising forest plans. In 2012 and 2015 the Forest Service codified new regulations for developing, revising, and amending forest plans. Collaboration and public involvement are explicit goals of the new regulations. This paper briefly reviews the literature on collaborative planning on national forests and explores a successful collaborative planning process used by the Green Mountain and Finger Lakes National Forests, located in Vermont and New York respectively, to develop their 2006 forest plans. This paper shows how the Green Mountain and Finger Lakes National Forests developed parallel public and internal collaborative processes to build trust, relationships, and partnership, and discusses the implications for process design, capacity building, and facilitating agreements. By looking back at this successful case of collaborative forest planning, key lessons can provide ideas for developing collaborative processes for future planning efforts.

  19. Test plan for determining breathing rates in single shell tanks using tracer gases. Revision 1

    International Nuclear Information System (INIS)

    Andersen, J.A.

    1997-01-01

    This test plan specifies the requirements and conditions for the injection of tracer gas (Helium (He)) into single shell tanks to determine breathing rates using periodic sampling. The eight tanks which have been selected at the time this Test Plan was developed are A-101, AX-102, AX-103, BY-105, C-107, U-103 (U-103 is counted twice, once during the winter months and once during the summer), and U-105. Other tanks to be sampled will be assigned by Pacific Northwest National Laboratory (PNNL) at a later date in the study process as resources allow, the document shall be revised as required. The sampling of headspace for each of these tanks shall be performed using available risers or the Standard Hydrogen Monitoring System (SHMS) cabinet as available. The tank farm vapor cognizant engineer shall assign the injection and sample testing point for each tank and document the point in the field work package. SUMMA TMI canisters, equipped in-line with dual particulate air filters and two silica gel sorbent traps will be used to collect the gas samples. The purpose of dual particulate air filters is to ensure no radioactive particulates are transferred to the SUMMA TMI canisters. The silica gel sorbent traps will effectively eliminate any tritiated water vapor that may be present in the sample gas stream. PNNL shall supply the tracer gases injection system and shall perform the analysis on the headspace samples. TWRS Characterization project shall inject the tracer gas and perform the sampling. Refer to Engineering Task Plan HNF-SD-TWR-ETP-002 for a detailed description of the responsibilities for this task

  20. Revised ground-water monitoring compliance plan for the 300 area process trenches

    Energy Technology Data Exchange (ETDEWEB)

    Schalla, R.; Aaberg, R.L.; Bates, D.J.; Carlile, J.V.M.; Freshley, M.D.; Liikala, T.L.; Mitchell, P.J.; Olsen, K.B.; Rieger, J.T.

    1988-09-01

    This document contains ground-water monitoring plans for process-water disposal trenches located on the Hanford Site. These trenches, designated the 300 Area Process Trenches, have been used since 1973 for disposal of water that contains small quantities of both chemicals and radionuclides. The ground-water monitoring plans contained herein represent revision and expansion of an effort initiated in June 1985. At that time, a facility-specific monitoring program was implemented at the 300 Area Process Trenches as part of a regulatory compliance effort for hazardous chemicals being conducted on the Hanford Site. This monitoring program was based on the ground-water monitoring requirements for interim-status facilities, which are those facilities that do not yet have final permits, but are authorized to continue interim operations while engaged in the permitting process. The applicable monitoring requirements are described in the Resource Conservation and Recovery Act (RCRA), 40 CFR 265.90 of the federal regulations, and in WAC 173-303-400 of Washington State's regulations (Washington State Department of Ecology 1986). The program implemented for the process trenches was designed to be an alternate program, which is required instead of the standard detection program when a facility is known or suspected to have contaminated the ground water in the uppermost aquifer. The plans for the program, contained in a document prepared by the US Department of Energy (USDOE) in 1985, called for monthly sampling of 14 of the 37 existing monitoring wells at the 300 Area plus the installation and sampling of 2 new wells. 27 refs., 25 figs., 15 tabs.

  1. Savannah River Site mixed waste Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and reference document: Revision 2

    International Nuclear Information System (INIS)

    Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

    1995-01-01

    The DOE is required by the Resource Conservation and Recovery Act to prepare site treatment plans describing the development of treatment capacities and technologies for treating mixed waste. This proposed plan contains Savannah River Site's preferred options and schedules for constructing new facilities, and otherwise obtaining treatment for mixed wastes. The proposed plan consists of 2 volumes. Volume 1, Compliance Plan, identifies the capacity to be developed and the schedules as required. Volume 2, Background, provides a detailed discussion of the preferred options with technical basis, plus a description of the specific waste streams. Chapters are: Introduction; Methodology; Mixed low level waste streams; Mixed transuranic waste; High level waste; Future generation of mixed waste streams; Storage; Process for evaluation of disposal issues in support of the site treatment plans discussions; Treatment facilities and treatment technologies; Offsite waste streams for which SRS treatment is the Preferred Option (Naval reactor wastes); Summary information; and Acronyms and glossary. This revision does not contain the complete revised report, but only those pages that have been revised

  2. Stalking: A Multidimensional Framework for Assessment and Safety Planning.

    Science.gov (United States)

    Logan, T K; Walker, Robert

    2015-09-03

    Despite the high prevalence of stalking and the risk of harm it poses to victims, arrest rates, prosecutions, and convictions for stalking continue to be low in the United States. The overall goal of this article is to introduce a multidimensional framework of stalking that adds to the current literature by (1) providing a conceptual framework consistent with legal elements of many stalking statutes to facilitate assessment, communication, documentation, and safety planning for stalking several victims; (2) introducing a more systematic way of assessing course of conduct and the context of fear in stalking situations in order to increase the understanding of cumulative fear for stalking victims; (3) emphasizing the aspects of stalking harm that go beyond violence and that show how harm from stalking accumulates over time including life sabotage; and (4) discussing 12 risk factors derived from the overall multidimensional framework that can be used to describe the big picture of stalking and to facilitate safety planning for victims. Implications for future research are discussed. © The Author(s) 2015.

  3. Structural Design Requirements and Factors of Safety for Spaceflight Hardware: For Human Spaceflight. Revision A

    Science.gov (United States)

    Bernstein, Karen S.; Kujala, Rod; Fogt, Vince; Romine, Paul

    2011-01-01

    This document establishes the structural requirements for human-rated spaceflight hardware including launch vehicles, spacecraft and payloads. These requirements are applicable to Government Furnished Equipment activities as well as all related contractor, subcontractor and commercial efforts. These requirements are not imposed on systems other than human-rated spacecraft, such as ground test articles, but may be tailored for use in specific cases where it is prudent to do so such as for personnel safety or when assets are at risk. The requirements in this document are focused on design rather than verification. Implementation of the requirements is expected to be described in a Structural Verification Plan (SVP), which should describe the verification of each structural item for the applicable requirements. The SVP may also document unique verifications that meet or exceed these requirements with NASA Technical Authority approval.

  4. 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.

  5. 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

  6. Manpower development for safe operation of nuclear power plant. China. Revision of final safety analysis report. Activity: 5.1.3-Task-08. Technical report

    International Nuclear Information System (INIS)

    Almeida, C.; Elias, D.

    1994-01-01

    The objectives of this mission included providing assistance for the revision of the FSAR including: national practices, administrative procedures, required staffing level, other resources, planning, scheduling, content, and organization of the revision. Activities included several days of lectures regarding worldwide practices including the United States and Commonwealth Edison Company (ComEd), interaction with Chinese counterparts re. their FSAR and Technical Specification revision and two visits to the Qin Shan NPP

  7. The Revised WIPP Passive Institutional Controls Program - A Conceptual Plan - 13145

    International Nuclear Information System (INIS)

    Patterson, Russ; Klein, Thomas; Van Luik, Abraham

    2013-01-01

    with the international guidance being developed. International guidance currently under development may suggest that the inter-generational equity principle strives to warn the future, however, in doing so not to unduly burden present generations. Building markers and monuments that are out of proportion to the risk being presented to the future is not in keeping with generational equity. With this in mind the DOE/CBFO is developing conceptual plans for re-evaluating and revising the current WIPP PIC's program. These conceptual plans will suggest scientific and technical work that must be completed to develop a 'new' PICs program that takes the best ideas of the present plan, blended with new ideas from the RK and M project, and proposed alternative permanent markers designs and materials in consideration. (authors)

  8. Feed Materials Production Center waste management plan (Revision to NLCO-1100, R.6)

    International Nuclear Information System (INIS)

    Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

    1986-01-01

    In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the wastes generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF 2 , slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program

  9. Plan for characterization of K Basin Spent Nuclear Fuel and sludge. Revision 1

    International Nuclear Information System (INIS)

    Lawrence, L.A.

    1995-01-01

    This plan outlines a Characterization Program that provides the necessary data to support the Integrated Process Strategy scope and schedules for the Spent Nuclear Fuel (SNF) and sludge stored in the Hanford K Basins. The plan is driven by the schedule to begin fuel transfer by December 1997. The program is structured for 4 years (i.e., FY 1995 through FY 1998) and is limited to in-situ and laboratory examinations of the SNF and sludge in the K East and K West Basins. In order to assure the scope and schedule of the Characterization Program fully supports the Integrated Process Strategy, key project management has approved the plan. The intent of the program is to provide bounding behavior for the fuel, and acceptability for the transfer of the sludge to the Double Shell Tanks. Fuel examinations are based on two shipping compains from the K West Basin and one from the K East Basin with coincident sludge sampling campaings for the associated canister sludge. Sampling of the basin floor and pit sludge will be conducted independent of the fuel and canister sludge shipping activities. Fuel behavior and properties investigated in the laboratory include physical condition, hydride and oxide content, conditioning testing, oxidation kinetics, and dry storage behavior. These laboratory examinations are expected to provide the necessary data to establish or confirm fuel conditioning process limits and support safety analysis. Sludge laboratory examinations include measurement of quantity and content, measurement of properties for equipment design and recovery process limits and support safety analysis. Sludge laboratory examinations include measurement of quantity and content, measurement of properties for equipment design and recovery precesses, tank farm acceptance, simulant development, measurement of corrosion products, and measurements of drying behavior

  10. 12 CFR 30.4 - Filing of safety and soundness compliance plan.

    Science.gov (United States)

    2010-01-01

    ... steps the bank will take to correct the deficiency and the time within which those steps will be taken. (c) Review of safety and soundness compliance plans. Within 30 days after receiving a safety and... AND SOUNDNESS STANDARDS § 30.4 Filing of safety and soundness compliance plan. (a) Schedule for filing...

  11. RCRA Part A permit characterization plan for the U-2bu subsidence crater. Revision 1

    International Nuclear Information System (INIS)

    1998-04-01

    This plan presents the characterization strategy for Corrective Action Unit (CAU) 109, U-2bu Subsidence Crater (referred to as U-2bu) in Area 2 at the Nevada Test Site (NTS). The objective of the planned activities is to obtain sufficient characterization data for the crater soils and observed wastes under the conditions of the current Resource Conservation and Recovery Act (RCRA) Part A permit. The scope of the characterization plan includes collecting surface and subsurface soil samples with hand augers and for the purpose of site characterization. The sampling strategy is to characterize the study area soils and look for RCRA constituents. Observable waste soils and surrounding crater soils will be analyzed and evaluated according to RCRA closure criteria. Because of the status of the crater a RCRA Part A permit site, acquired radionuclide analyses will only be evaluated in regards to the health and safety of site workers and the disposition of wastes generated during site characterization. The U-2bu Subsidence Crater was created in 1971 by a Lawrence Livermore National Laboratory underground nuclear test, event name Miniata, and was used as a land-disposal unit for radioactive and hazardous waste from 1973 to 1988

  12. [Post-marketing drug safety-risk management plan(RMP)].

    Science.gov (United States)

    Ezaki, Asami; Hori, Akiko

    2013-03-01

    The Guidance for Risk Management Plan(RMP)was released by the Ministry of Health, Labour and Welfare in April 2012. The RMP consists of safety specifications, pharmacovigilance plans and risk minimization action plans. In this paper, we outline post-marketing drug safety operations in PMDA and the RMP, with examples of some anticancer drugs.

  13. A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I. [SAQ Kontroll AB, Stockholm (Sweden)

    1999-12-01

    given objectives, the handbook contains solutions for the stress intensity factor and the limit load for a number of crack geometries of importance for applications. It also contains rules for defect characterization, recommendations for estimation of residual stresses, material data for nuclear applications and a safety evaluation system. To ensure conservatism, the procedure with the given solutions of the stress intensity factor and the limit load has been validated. Predictions of the procedure were compared with the actual outcome of full scale experiments reported in the literature. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A new safety evaluation system has been introduced. The conservatism in the method for assessment of secondary stresses has been reduced. The solutions for the stress intensity factor and the limit load, the recommendations for estimation of residual stresses and the given material data for nuclear applications have been updated. A modern Windows based PC-program SACC has been developed which can perform the assessments described in this handbook including calculation of crack growth due to stress corrosion and fatigue. The program also has an option which enables assessment of cracks according to the 1995 edition of the ASME Boiler and Pressure Vessel Code, Section XI. Appendices A, C and H for assessment of cracks in ferritic pressure vessels, austenitic piping and ferritic piping, respectively.

  14. A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

    International Nuclear Information System (INIS)

    Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I.

    1999-12-01

    , the handbook contains solutions for the stress intensity factor and the limit load for a number of crack geometries of importance for applications. It also contains rules for defect characterization, recommendations for estimation of residual stresses, material data for nuclear applications and a safety evaluation system. To ensure conservatism, the procedure with the given solutions of the stress intensity factor and the limit load has been validated. Predictions of the procedure were compared with the actual outcome of full scale experiments reported in the literature. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A new safety evaluation system has been introduced. The conservatism in the method for assessment of secondary stresses has been reduced. The solutions for the stress intensity factor and the limit load, the recommendations for estimation of residual stresses and the given material data for nuclear applications have been updated. A modern Windows based PC-program SACC has been developed which can perform the assessments described in this handbook including calculation of crack growth due to stress corrosion and fatigue. The program also has an option which enables assessment of cracks according to the 1995 edition of the ASME Boiler and Pressure Vessel Code, Section XI. Appendices A, C and H for assessment of cracks in ferritic pressure vessels, austenitic piping and ferritic piping, respectively

  15. 78 FR 71033 - Pipeline Safety: Information Collection Activities, Revisions to Incident and Annual Reports for...

    Science.gov (United States)

    2013-11-27

    ... Reduction Act of 1995, PHMSA published a notice in the Federal Register of its intent to revise six forms... the failure of a piece of equipment is always due to a flaw in the equipment and never due to a...

  16. Oak Ridge National Laboratory Waste Management Plan, fiscal year 1994. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Turner, J.W. [ed.

    1993-12-01

    US Department of Energy (DOE) Order 5820.2A was promulgated in final form on September 26, 1988. The order requires heads of field organizations to prepare and to submit updates on the waste management plans for all operations under their purview according to the format in Chap. 6, {open_quotes}Waste Management Plan Outline.{close_quotes} These plans are to be submitted by the DOE Oak Ridge Operations Office (DOE-ORO) in December of each year and distributed to the DP-12, ES&H-1, and other appropriate DOE Headquarters (DOE-HQ) organizations for review and comment. This document was prepared in response to this requirement for fiscal year (FY) 1994. The Oak Ridge National Laboratory (ORNL) waste management mission is reduction, collection, storage, treatment, and disposal of DOE wastes, generated primarily in pursuit of ORNL missions, in order to protect human health and safety and the environment. In carrying out this mission, waste management staff in the Waste Management and Remedial Action Division (WMRAD) will (1) guide ORNL in optimizing waste reduction and waste management capabilities and (2) conduct waste management operations in a compliant, publicly acceptable, technically sound, and cost-efficient manner. Waste management requirements for DOE radioactive wastes are detailed in DOE Order 5820.2A, and the ORNL Waste Management Program encompasses all elements of this order. The requirements of this DOE order and other appropriate DOE orders, along with applicable Tennessee Department of Environment and Conservation and US Environmental Protection Agency (EPA) rules and regulations, provide the principal source of regulatory guidance for waste management operations at ORNL. The objective of this document is compilation and consolidation of information on how the ORNL Waste Management Program is conducted, which waste management facilities are being used to manage wastes, what activities are planned for FY 1994, and how all of the activities are documented.

  17. 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

  18. Jefferson Proving Ground, South of the Firing Line Health and Safety Plan, Volume 4

    National Research Council Canada - National Science Library

    1992-01-01

    .... The purpose of this Site Health and Safety Plan (SHSP) is to assign SECD personnel health and safety responsibilities, to prescribe mandatory operating procedures, and to establish personal-protective-equipment (PPE...

  19. Implementing 10 CFR 830 at the FEMP Silos: Nuclear Health and Safety Plans as Documented Safety Analysis

    International Nuclear Information System (INIS)

    Fisk, Patricia; Rutherford, Lavon

    2003-01-01

    The objective of the Silos Project at the Fernald Closure Project (FCP) is to safely remediate high-grade uranium ore residues (Silos 1 and 2) and metal oxide residues (Silo 3). The evolution of Documented Safety Analyses (DSAs) for these facilities has reflected the changes in remediation processes. The final stage in silos DSAs is an interpretation of 10 CFR 830 Safe Harbor Requirements that combines a Health and Safety Plan with nuclear safety requirements. This paper will address the development of a Nuclear Health and Safety Plan, or N-HASP

  20. Sodium fast reactor safety and licensing research plan. Volume II.

    Energy Technology Data Exchange (ETDEWEB)

    Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

    2012-05-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.