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Sample records for fluor hanford alara

  1. Fluor Hanford ALARA Center is a D and D Resource

    International Nuclear Information System (INIS)

    Waggoner, L.O.

    2008-01-01

    The mission at the Hanford Nuclear Reservation changed when the last reactor plant was shut down in 1989 and work was started to place all the facilities in a safe condition and begin decontamination, deactivation, decommissioning, and demolition (D and D). These facilities consisted of old shutdown reactor plants, spent fuel pools, processing facilities, and 177 underground tanks containing 53 million gallons of highly radioactive and toxic liquids and sludge. New skills were needed by the workforce to accomplish this mission. By 1995, workers were in the process of getting the facilities in a safe condition and it became obvious improvements were needed in their tools, equipment and work practices. The Hanford ALARA Program looked good on paper, but did little to help contractors that were working in the field. The Radiological Control Director decided that the ALARA program needed to be upgraded and a significant improvement could be made if workers had a place they could visit that had samples of the latest technology and could talk to experienced personnel who have had success doing D and D work. Two senior health physics personnel who had many years experience in doing radiological work were chosen to obtain tools and equipment from vendors and find a location centrally located on the Hanford site. Vendors were asked to loan their latest tools and equipment for display. Most vendors responded and the Hanford ALARA Center of Technology opened on October 1, 1996. Today, the ALARA Center includes a classroom for conducting training and a mockup area with gloveboxes. Two large rooms have a containment tent, several glove bags, samples of fixatives/expandable foam, coating displays, protective clothing, heat stress technology, cutting tools, HEPA filtered vacuums, ventilation units, pumps, hydraulic wrenches, communications equipment, shears, nibblers, shrouded tooling, and several examples of innovative tools developed by the Hanford facilities. See Figures I and

  2. Fluor Hanford Project Focused Progress at Hanford

    International Nuclear Information System (INIS)

    HANSON, R.D.

    2000-01-01

    Fluor Hanford is making significant progress in accelerating cleanup at the Hanford site. This progress consistently aligns with a new strategic vision established by the U.S. Department of Energy's Richland Operations Office (RL)

  3. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    Energy Technology Data Exchange (ETDEWEB)

    GARVIN, L. J.; JENSEN, M. A.

    2004-04-13

    This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

  4. Fluor Daniel Hanford contract standards/requirements identification document

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, G.L.

    1997-04-24

    This document, the Standards/Requirements Identification Document (S/RID) for the Fluor Daniel Hanford Contract, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment.

  5. Fluor Daniel Hanford company standards requirements identification document

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1997-01-01

    This document, the Standards/Requirements Identification Document (S/RID) for the Fluor Daniel Hanford Contract, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment

  6. FLUOR HANFORD (FH) MAKES CLEANUP A REALITY IN NEARLY 11 YEARS AT HANFORD

    Energy Technology Data Exchange (ETDEWEB)

    GERBER, M.S.

    2007-05-24

    For nearly 11 years, Fluor Hanford has been busy cleaning up the legacy of nuclear weapons production at one of the Department of Energy's (DOE'S) major sites in the United States. As prime nuclear waste cleanup contractor at the vast Hanford Site in southeastern Washington state, Fluor Hanford has changed the face of cleanup. Fluor beginning on October 1, 1996, Hanford Site cleanup was primarily a ''paper exercise.'' The Tri-Party Agreement, officially called the Hanford Federal Facility Agreement and Consent Order - the edict governing cleanup among the DOE, U.S. Environmental Protection Agency (EPA) and Washington state - was just seven years old. Milestones mandated in the agreement up until then had required mainly waste characterization, reporting, and planning, with actual waste remediation activities off in the future. Real work, accessing waste ''in the field'' - or more literally in huge underground tanks, decaying spent fuel POO{approx}{approx}S, groundwater, hundreds of contaminated facilities, solid waste burial grounds, and liquid waste disposal sites -began in earnest under Fluor Hanford. The fruits of labors initiated, completed and/or underway by Fluor Hanford can today be seen across the site. Spent nuclear fuel is buttoned up in secure, dry containers stored away from regional water resources, reactive plutonium scraps are packaged in approved containers, transuranic (TRU) solid waste is being retrieved from burial trenches and shipped offsite for permanent disposal, contaminated facilities are being demolished, contaminated groundwater is being pumped out of aquifers at record rates, and many other inventive solutions are being applied to Hanford's most intransigent nuclear wastes. (TRU) waste contains more than 100 nanocuries per gram, and contains isotopes higher than uranium on the Periodic Table of the Elements. (A nanocurie is one-billionth of a curie.) At the same time, Fluor Hanford

  7. Fluor Hanford Nuclear Material Stabilization Project Welding Manual

    International Nuclear Information System (INIS)

    BERKEY, J.R.

    2000-01-01

    The purpose of this section of the welding manual is to: (1) Provide a general description of the major responsibilities of the organizations involved with welding. (2) Provide general guidance concerning the application of codes related to welding. This manual contains requirements for welding for all Fluor Hanford (FH) welding operators working on the W460 Project, in the Plutonium Finishing Plant (PFP) at the U. S. Department of Energy (DOE) Hanford facilities. These procedures and any additional requirements for these joining processes can be used by all FH welding operators that are qualified. The Welding Procedure Specifications (WPS) found in this document were established from Procedure Qualification Records (PQR) qualified by FH specifically for the W460 Project. PQRs are permanent records of the initial testing and qualification program and are used to backup, and support, the WPS. The identification numbers of the supporting PQR(s) are recorded on each WPS. All PQRs are permanently stored under the supervision of the Fluor Hanford Welding Engineer (FHWE). New PQRs and WPSs will continue to be developed as necessary. The qualification of welders, welding operators and welding procedures will be performed for FH under supervision and concurrent of the FHWE. All new welding procedures to be entered in this manual or welder personnel to be added to the welder qualification database, shall be approved by the FHWE

  8. Safety At Fluor Hanford (B) Case Study - Prepared By The Thunderbird School Of Global Management

    International Nuclear Information System (INIS)

    Arnold, L.D.

    2009-01-01

    One year into the Hanford contract, Fluor had learned a number of hard lessons very quickly. Although the Hanford remediation contract was in many ways a new endeavor for Fluor and a different kind of contract, the organization moved quickly to increase communication with all employees, attack head-on what it considered unsafe and inappropriate safety practices, and strongly inject its own corporate cultural beliefs into the Hanford organization. It wasn't easy, and it didn't happen overnight. From the beginning, Fluor established processes and programs to drive down injury rates. For example, whereas the previous contractor's approach to injuries had been passive, Fluor took a much more aggressive approach to worker injuries. The previous contractor had established a practice of sending injured workers home with the basic directive 'to come back when you are well'. Instead of using outsourced medical assessment, Fluor internalized it and evaluated all claims aggressively. Legitimate claims were quickly settled, and management moved to identify 'repeat offenders' when it came to reportable safety incidents. In the first year of Fluor's management, reportable injuries dropped from 5.37 to 2.99 per 200,000 man-hours. Despite the drop in injury rates, the safety record at Fluor Hanford was not at a level that met either Fluor or the Department of Energy's expectations. Earlier in 1997, Fluor Hanford's proposed safety program was rejected by the DOE. The DOE was not satisfied with Fluor Hanford's proposal for various reasons, including insufficient worker involvement and a lack of accountability. With the need for change clearly established, Fluor Hanford management embarked on a decade-long mission to change the safety culture and improve safety performance. This case describes the key changes and their impact on Fluor Hanford.

  9. SAFETY AT FLUOR HANFORD (B) CASE STUDY - PREPARED BY THE THUNDERBIRD SCHOOL OF GLOBAL MANAGEMENT

    Energy Technology Data Exchange (ETDEWEB)

    ARNOLD LD

    2009-09-25

    One year into the Hanford contract, Fluor had learned a number of hard lessons very quickly. Although the Hanford remediation contract was in many ways a new endeavor for Fluor and a different kind of contract, the organization moved quickly to increase communication with all employees, attack head-on what it considered unsafe and inappropriate safety practices, and strongly inject its own corporate cultural beliefs into the Hanford organization. It wasn't easy, and it didn't happen overnight. From the beginning, Fluor established processes and programs to drive down injury rates. For example, whereas the previous contractor's approach to injuries had been passive, Fluor took a much more aggressive approach to worker injuries. The previous contractor had established a practice of sending injured workers home with the basic directive 'to come back when you are well'. Instead of using outsourced medical assessment, Fluor internalized it and evaluated all claims aggressively. Legitimate claims were quickly settled, and management moved to identify 'repeat offenders' when it came to reportable safety incidents. In the first year of Fluor's management, reportable injuries dropped from 5.37 to 2.99 per 200,000 man-hours. Despite the drop in injury rates, the safety record at Fluor Hanford was not at a level that met either Fluor or the Department of Energy's expectations. Earlier in 1997, Fluor Hanford's proposed safety program was rejected by the DOE. The DOE was not satisfied with Fluor Hanford's proposal for various reasons, including insufficient worker involvement and a lack of accountability. With the need for change clearly established, Fluor Hanford management embarked on a decade-long mission to change the safety culture and improve safety performance. This case describes the key changes and their impact on Fluor Hanford.

  10. Environmental Solutions, A Summary of Contributions for FY04: PNNL Contributions to Fluor Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Fassbender, Linda L.

    2005-03-08

    Pacific Northwest National Laboratory managed a variety of technical and scientific efforts to support Fluor Hanford's work in cleaning up the Hanford Site. Work done for other Hanford contractors, the Waste Treatment Plant, and directly for the U.S. Department of Energy is summarized in the other booklets in this series.

  11. SAFETY AT FLUOR HANFORD (A) CASE STUDY - PREPARED BY THUNDERBIRD SCHOOL OF GLOBAL MANAGEMENT

    Energy Technology Data Exchange (ETDEWEB)

    ARNOLD LD

    2009-09-25

    By November of 1997, Fluor Hanford (Fluor) had been the site manager of the Hanford nuclear reservation for a year. The Hanford site had been established as part of the Manhattan Project in the 1940s that gave birth to the atomic bomb. Hanford produced two thirds of U.S. plutonium during the Cold War period. The Hanford site was half the size of Rhode Island and occupied 586 square miles in southeastern Washington State. The production of plutonium for more than 40 years left a huge legacy of chemical and radiological contamination: 80 square miles of contaminated groundwater; 2,300 tons of spent nuclear fuel stored in underwater basins; 20 tons of plutonium-laced contaminated materials; and 500 contaminated facilities. The cleanup involved a challenging combination of radioactive material handling within an infrastructure constructed in the 1940s and 1950s. The cleanup that began in 1988 was expected to take 30 years or more. Improving safety at Hanford had already proven to be a significant challenge. As the new site manager at Hanford, Fluor Hanford inherited lower- and mid-level managers and thousands of unionized employees, many of whom were second or third generation Hanford employees. These employees had seen many contractors come and go over the years. Some of the managers who had worked with the previous contractor saw Fluor's emphasis on safety as getting in the way of operations. Union-management relations were fractious. Hanford's culture was described as 'production driven-management told everyone what to do, and, if you didn't do it, there were consequences'. Worker involvement in designing and implementing safety programs was negligible. Fluor Hanford also was having trouble satisfying its client, the Department of Energy (DOE). The DOE did not see a clear path forward for performance improvements at Hanford. Clearly, major change was necessary, but how and where should it be implemented?

  12. SAFETY AT FLUOR HANFORD (A) CASE STUDY - PREPARED BY THUNDERBIRD SCHOOL OF GLOBAL MANAGEMENT

    International Nuclear Information System (INIS)

    Arnold, L.D.

    2009-01-01

    By November of 1997, Fluor Hanford (Fluor) had been the site manager of the Hanford nuclear reservation for a year. The Hanford site had been established as part of the Manhattan Project in the 1940s that gave birth to the atomic bomb. Hanford produced two thirds of U.S. plutonium during the Cold War period. The Hanford site was half the size of Rhode Island and occupied 586 square miles in southeastern Washington State. The production of plutonium for more than 40 years left a huge legacy of chemical and radiological contamination: 80 square miles of contaminated groundwater; 2,300 tons of spent nuclear fuel stored in underwater basins; 20 tons of plutonium-laced contaminated materials; and 500 contaminated facilities. The cleanup involved a challenging combination of radioactive material handling within an infrastructure constructed in the 1940s and 1950s. The cleanup that began in 1988 was expected to take 30 years or more. Improving safety at Hanford had already proven to be a significant challenge. As the new site manager at Hanford, Fluor Hanford inherited lower- and mid-level managers and thousands of unionized employees, many of whom were second or third generation Hanford employees. These employees had seen many contractors come and go over the years. Some of the managers who had worked with the previous contractor saw Fluor's emphasis on safety as getting in the way of operations. Union-management relations were fractious. Hanford's culture was described as 'production driven-management told everyone what to do, and, if you didn't do it, there were consequences'. Worker involvement in designing and implementing safety programs was negligible. Fluor Hanford also was having trouble satisfying its client, the Department of Energy (DOE). The DOE did not see a clear path forward for performance improvements at Hanford. Clearly, major change was necessary, but how and where should it be implemented?

  13. SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

    International Nuclear Information System (INIS)

    GERBER MS

    2007-01-01

    This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site

  14. SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    GERBER MS

    2007-12-05

    This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site.

  15. Westinghouse Hanford Company ALARA year-end report, Calendar Year 1994: Revision 3A, Radiological engineering and ALARA

    International Nuclear Information System (INIS)

    Berglund, O.D.

    1995-06-01

    It has long been the US Department of Energy's (DOE's) Policy that radiation doses should be maintained as far below the dose limits as is reasonably achievable. This policy, known as the ''ALARA Principle of radiation protection,'' maintains that radiation exposures should be maintained as low as reasonably achievable, taking into account social, technical, economic, practical, and public policy considerations. The ALARA Principle is based on the hypothesis that even very low radiation doses carry some risk. As a result, it is not enough to maintain doses at/or slightly below limits; the lower the doses, the lower the risks. Because it is not possible to reduce all doses at DOE facilities to zero, economic and social factors must be considered to determine the optimal level of radiation doses. According to the ALARA Principle, if doses are too high, resources should be well spent to reduce them. At some point, the resources being spent to maintain low doses are exactly balanced by the risks avoided. Reducing doses below this point results in a misallocation of resources; the resources could be spent elsewhere and have a greater positive impact on health and safety. The objective of the Westinghouse Hanford Company (WHC) ALARA/Contamination Control Improvement Project (CCIP) Program is to manage and control exposures (both individual and collective) to the work force, the general public, and the environment to levels as low as is reasonable using the aforementioned ALARA Principle

  16. Fluor Daniel Hanford Inc. integrated safety management system phase 1 verification final report

    International Nuclear Information System (INIS)

    PARSONS, J.E.

    1999-01-01

    The purpose of this review is to verify the adequacy of documentation as submitted to the Approval Authority by Fluor Daniel Hanford, Inc. (FDH). This review is not only a review of the Integrated Safety Management System (ISMS) System Description documentation, but is also a review of the procedures, policies, and manuals of practice used to implement safety management in an environment of organizational restructuring. The FDH ISMS should support the Hanford Strategic Plan (DOE-RL 1996) to safely clean up and manage the site's legacy waste; deploy science and technology while incorporating the ISMS theme to ''Do work safely''; and protect human health and the environment

  17. Fluor Daniel Hanford Inc. integrated safety management system phase 1 verification final report

    Energy Technology Data Exchange (ETDEWEB)

    PARSONS, J.E.

    1999-10-28

    The purpose of this review is to verify the adequacy of documentation as submitted to the Approval Authority by Fluor Daniel Hanford, Inc. (FDH). This review is not only a review of the Integrated Safety Management System (ISMS) System Description documentation, but is also a review of the procedures, policies, and manuals of practice used to implement safety management in an environment of organizational restructuring. The FDH ISMS should support the Hanford Strategic Plan (DOE-RL 1996) to safely clean up and manage the site's legacy waste; deploy science and technology while incorporating the ISMS theme to ''Do work safely''; and protect human health and the environment.

  18. Fluor Hanford Integrated Safety Management System Phase II Verification Vol 1 & Vol 2

    Energy Technology Data Exchange (ETDEWEB)

    PARSONS, J.E.

    2000-07-15

    The U.S. Department of Energy (DOE) is committed to conducting work efficiently and in a manner that ensures protection of the workers, public, and environment. DOE policy mandates that safety management systems be used to systematically integrate safety into management and work practices at all levels while accomplishing mission goals in an effective and efficient manner. The purpose of the Fluor Hanford (FH) Integrated Safety Management System (ISMS) verification was to determine whether FH's ISM system and processes are sufficiently implemented to accomplish the goal of ''Do work safely.'' The purpose of the DOE, Richland Operations Office (RL) verification was to determine whether RL has established processes that adequately describe RL's role in safety management and if those processes are sufficiently implemented.

  19. Fluor Hanford Integrated Safety Management System Phase II Verification Vol 1 and Vol 2

    CERN Document Server

    Parsons, J E

    2000-01-01

    The U.S. Department of Energy (DOE) is committed to conducting work efficiently and in a manner that ensures protection of the workers, public, and environment. DOE policy mandates that safety management systems be used to systematically integrate safety into management and work practices at all levels while accomplishing mission goals in an effective and efficient manner. The purpose of the Fluor Hanford (FH) Integrated Safety Management System (ISMS) verification was to determine whether FH's ISM system and processes are sufficiently implemented to accomplish the goal of ''Do work safely.'' The purpose of the DOE, Richland Operations Office (RL) verification was to determine whether RL has established processes that adequately describe RL's role in safety management and if those processes are sufficiently implemented.

  20. Fluor Hanford Integrated Safety Management System Phase II Verification Vol 1 and Vol 2

    International Nuclear Information System (INIS)

    PARSONS, J.E.

    2000-01-01

    The U.S. Department of Energy (DOE) is committed to conducting work efficiently and in a manner that ensures protection of the workers, public, and environment. DOE policy mandates that safety management systems be used to systematically integrate safety into management and work practices at all levels while accomplishing mission goals in an effective and efficient manner. The purpose of the Fluor Hanford (FH) Integrated Safety Management System (ISMS) verification was to determine whether FH's ISM system and processes are sufficiently implemented to accomplish the goal of ''Do work safely.'' The purpose of the DOE, Richland Operations Office (RL) verification was to determine whether RL has established processes that adequately describe RL's role in safety management and if those processes are sufficiently implemented

  1. Fluor Daniel Hanford implementation plan for DOE Order 5480.28. Natural phenomena hazards mitigation

    International Nuclear Information System (INIS)

    Conrads, T.J.

    1997-01-01

    Natural phenomena hazards (NPH) are unexpected acts of nature that pose a threat or danger to workers, the public, or the environment. Earthquakes, extreme winds (hurricane and tornado), snow, flooding, volcanic ashfall, and lightning strikes are examples of NPH that could occur at the Hanford Site. U.S. Department of Energy (DOE) policy requires facilities to be designed, constructed, and operated in a manner that protects workers, the public, and the environment from hazards caused by natural phenomena. DOE Order 5480.28, Natural Phenomena Hazards Mitigation, includes rigorous new natural phenomena criteria for the design of new DOE facilities, as well as for the evaluation and, if necessary, upgrade of existing DOE facilities. The Order was transmitted to Westinghouse Hanford Company in 1993 for compliance and is also identified in the Project Hanford Management Contract, Section J, Appendix C. Criteria and requirements of DOE Order 5480.28 are included in five standards, the last of which, DOE-STD-1023, was released in fiscal year 1996. Because the Order was released before all of its required standards were released, enforcement of the Order was waived pending release of the last standard and determination of an in-force date by DOE Richland Operations Office (DOE-RL). Agreement also was reached between the Management and Operations Contractor and DOE-RL that the Order would become enforceable for new structures, systems, and components (SSCS) 60 days following issue of a new order-based design criteria in HNF-PRO-97, Engineering Design and Evaluation. The order also requires that commitments addressing existing SSCs be included in an implementation plan that is to be issued 1 year following the release of the last standard. Subsequently, WHC-SP-1175, Westinghouse Hanford Company Implementation Plan for DOE Order 5480.28, Natural Phenomena Hazards Mitigation, Rev. 0, was issued in November 1996, and this document, HNF-SP-1175, Fluor Daniel Hanford

  2. Integration of Formal Job Hazard Analysis and ALARA Work Practice

    International Nuclear Information System (INIS)

    NELSEN, D.P.

    2002-01-01

    ALARA work practices have traditionally centered on reducing radiological exposure and controlling contamination. As such, ALARA policies and procedures are not well suited to a wide range of chemical and human health issues. Assessing relative risk, identifying appropriate engineering/administrative controls and selecting proper Personal Protective Equipment (PPE) for non nuclear work activities extends beyond the limitations of traditional ALARA programs. Forging a comprehensive safety management program in today's (2002) work environment requires a disciplined dialog between health and safety professionals (e.g. safety, engineering, environmental, quality assurance, industrial hygiene, ALARA, etc.) and personnel working in the field. Integrating organizational priorities, maintaining effective pre-planning of work and supporting a team-based approach to safety management represents today's hallmark of safety excellence. Relying on the mandates of any single safety program does not provide industrial hygiene with the tools necessary to implement an integrated safety program. The establishment of tools and processes capable of sustaining a comprehensive safety program represents a key responsibility of industrial hygiene. Fluor Hanford has built integrated safety management around three programmatic attributes: (1) Integration of radiological, chemical and ergonomic issues under a single program. (2) Continuous improvement in routine communications among work planning/scheduling, job execution and management. (3) Rapid response to changing work conditions, formalized work planning and integrated worker involvement

  3. Applied ALARA techniques

    International Nuclear Information System (INIS)

    Waggoner, L.O.

    1998-01-01

    The presentation focuses on some of the time-proven and new technologies being used to accomplish radiological work. These techniques can be applied at nuclear facilities to reduce radiation doses and protect the environment. The last reactor plants and processing facilities were shutdown and Hanford was given a new mission to put the facilities in a safe condition, decontaminate, and prepare them for decommissioning. The skills that were necessary to operate these facilities were different than the skills needed today to clean up Hanford. Workers were not familiar with many of the tools, equipment, and materials needed to accomplish:the new mission, which includes clean up of contaminated areas in and around all the facilities, recovery of reactor fuel from spent fuel pools, and the removal of millions of gallons of highly radioactive waste from 177 underground tanks. In addition, this work has to be done with a reduced number of workers and a smaller budget. At Hanford, facilities contain a myriad of radioactive isotopes that are 2048 located inside plant systems, underground tanks, and the soil. As cleanup work at Hanford began, it became obvious early that in order to get workers to apply ALARA and use hew tools and equipment to accomplish the radiological work it was necessary to plan the work in advance and get radiological control and/or ALARA committee personnel involved early in the planning process. Emphasis was placed on applying,ALARA techniques to reduce dose, limit contamination spread and minimize the amount of radioactive waste generated. Progress on the cleanup has,b6en steady and Hanford workers have learned to use different types of engineered controls and ALARA techniques to perform radiological work. The purpose of this presentation is to share the lessons learned on how Hanford is accomplishing radiological work

  4. Applied ALARA techniques

    Energy Technology Data Exchange (ETDEWEB)

    Waggoner, L.O.

    1998-02-05

    The presentation focuses on some of the time-proven and new technologies being used to accomplish radiological work. These techniques can be applied at nuclear facilities to reduce radiation doses and protect the environment. The last reactor plants and processing facilities were shutdown and Hanford was given a new mission to put the facilities in a safe condition, decontaminate, and prepare them for decommissioning. The skills that were necessary to operate these facilities were different than the skills needed today to clean up Hanford. Workers were not familiar with many of the tools, equipment, and materials needed to accomplish:the new mission, which includes clean up of contaminated areas in and around all the facilities, recovery of reactor fuel from spent fuel pools, and the removal of millions of gallons of highly radioactive waste from 177 underground tanks. In addition, this work has to be done with a reduced number of workers and a smaller budget. At Hanford, facilities contain a myriad of radioactive isotopes that are 2048 located inside plant systems, underground tanks, and the soil. As cleanup work at Hanford began, it became obvious early that in order to get workers to apply ALARA and use hew tools and equipment to accomplish the radiological work it was necessary to plan the work in advance and get radiological control and/or ALARA committee personnel involved early in the planning process. Emphasis was placed on applying,ALARA techniques to reduce dose, limit contamination spread and minimize the amount of radioactive waste generated. Progress on the cleanup has,b6en steady and Hanford workers have learned to use different types of engineered controls and ALARA techniques to perform radiological work. The purpose of this presentation is to share the lessons learned on how Hanford is accomplishing radiological work.

  5. An effective ALARA [As Low As Reasonably Achievable] Awareness Program

    International Nuclear Information System (INIS)

    Aldridge, T.L.; Hammond, D.A.

    1990-10-01

    Following the January 1, 1989 issue of the US Department of Energy (DOE) revised Order 5480.1, Chapter XI (DOE 1985), the Westinghouse Hanford Company (Westinghouse Hanford) As Low As Reasonably Achievable (ALARA) Program Office (APO) began an aggressive ALARA Awareness Campaign. The revised DOE Order 5480.11 (DOE 1988) required the documentation and tracking of ALARA practices and principles. This major challenge for compliance to the new requirements necessitated an enhanced awareness of the goals and objectives of the APO. The Westinghouse Hanford APO began the expansion of the ALARA Program. The ''classic concept'' of radiological exposure minimization, which began in the early 1940's, increased in scope to include the new concept of exposure minimization for all hazardous materials and conditions commensurate with sound economics and operating practices. This expansion could only be implemented by bringing about a cultural change. Therefore, the attempt to introduce this change in thinking created a second major challenge for the Westinghouse Hanford APO. The direct result of the identification of these two major goals was the creation of an effective ALARA Awareness for Westinghouse Hanford. This paper describes this program. 3 refs

  6. Alara in industry

    International Nuclear Information System (INIS)

    Croft, J.R.

    1989-01-01

    This paper reviews how the general frameworks of the ALARA procedures, ALARA Audits and Predictive ALARA Plans can be used in the non-nuclear power sector to give practical effect to the concept of optimization. The development of the use of ALARA Audits as an integral part of a Radiation Protection Adviser service and our experience of this structured approach is described. Particular attention is drawn to the use of site specific reference levels to trigger graded levels of response to increasing doses. Also several examples of the use of Cost Benefit Analysis within the ALARA Procedure are briefly described

  7. ALARA development in Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, M.A.M. [Instituto Nacional de Investigaciones Nucleares, Col Lomas de Barrilaco (Mexico)

    1995-03-01

    Even though the ALARA philosophy was formally implemented in the early 1980`s, to some extent, ALARA considerations already had been incorporated into the design of most commercial equipment and facilities based on experience and engineering development. In Mexico, the design of medical and industrial facilities were based on international recommendations containing those considerations. With the construction of Laguna Verde Nuclear Power Station, formal ALARA groups were created to review some parts of its design, and to prepare the ALARA Program and related procedures necessary for its commercial operation. This paper begins with a brief historical description of ALARA development in Mexico, and then goes on to discuss our regulatory frame in Radiation Protection, some aspects of the ALARA Program, efforts in controlling and reducing of sources of radiation, and finally, future perspectives in the ALARA field.

  8. ALARA Review of 233-S Process Hood D and D and Related Activities

    International Nuclear Information System (INIS)

    Landsman, S.D.

    1999-01-01

    This document is an as low as reasonably achievable (ALARA) review of design packages for planned work at the 233-S Facility. The ALARA review was initiated in accordance with the Bechtel Hanford, Inc. (BHI) Integrated Environmental, Safety, and Health Management System (ISMS) workflow process

  9. What is ALARA

    International Nuclear Information System (INIS)

    Auxier, J.A.; Dickson, H.W.

    1981-01-01

    The as-low-as-reasonably-achievable (ALARA) philosophy as it applies to personnel radiation exposure has been with us for a long time. The essential tenets of this philosophy surfaced quite early in the history of the Manhattan Project. Although the terminology has suffered through various translations and the application has seen many organizations and agencies come and go, the principles remain as valid today as ever. It is regretable that some regulatory agencies claim ALARA as their newfound miracle drug and that application according to their prescriptions will result in endless rounds of cyclical improvement in radiation protection practices. Others have taken advantage of the popularity of ALARA and have bastardized the philosophy to mean whatever is expedient for their purposes. In this paper, we review briefly the history of ALARA and what it seemingly means to different interest groups and offer a balanced viewpoint that health physicists should adopt

  10. The european ALARA network

    International Nuclear Information System (INIS)

    Croueail, P.; Lefaure, C.; Croft, J.

    2000-01-01

    Throughout the 1980s and early 1990s the European Commission sponsored projects on the understanding and practical implementation of the ALARA principle. These projects helped ensure that ALARA was integrated into many organisations radiation protection programmes, particularly in the nuclear industry. However there was still much to be done in the non-nuclear sector, as well as for the management of internal exposure. Therefore, the European Commission decided to set up, as of the first January 1996, a European ALARA Network (EAN) whose main goals are to: Further promote ALARA within non nuclear industry, research and the nuclear cycle; Provide a means for feedback experience and the exchange and dissemination of good radiological protection practices in these areas; Initiate proposals for research projects and workshops on topics dealing with optimisation of radiological protection for all types of occupational exposure. The Network has a Steering Committee of experts from 11 countries, with CEPN being the co-ordinator. Twice yearly, the EAN products for the international community a European ALARA Newsletter that reaches several thousand individuals or institutions, mainly in Europe. Each year since 1997, the EAN has organised an ALARA workshop attended by 60 to 80 experts from about ten countries. The first three Workshops were devoted to: ALARA and Decommissioning (1997, Saclay, France), Good Radiation Practices in Industry and Research (1998, Chilton, United Kingdam), and ALARA and Internal Exposure (1999, Munich, Germany). Each of these Workshops gave rise to sets of recommendations to the European Commission which included proposals for further research, modification of regulations, and actions to support feedback experience within the member states. (author)

  11. FLUOR DAN KESEHATAN GIGI

    Directory of Open Access Journals (Sweden)

    Magdarina Destri Agtini

    2012-10-01

    Full Text Available Most fluoride is found in the form of chemical compounds, and the availability of free fluoride ions in soils and water is varied. Laboratory research suggests that fluoride is most effective in caries prevention when a low level of fluoride is constantly maintained in the oral cavity. Fluoride controls effectively, it acts in several different ways. Fluoride is being used widely on a global scale. The estimation of  number of people throughout the world using various types of fluoride therapy and preventive measures, they are the clinical topical fluorides (20 millions, mouth-rinses (20 millions, drops/tablets (20 millions, salt fluoridation (40 millions. water fluoridation (210 millions, and fluoridated toothpaste (500 millions. The study results of water fluoridation in USA, New Zealand, Canada, and Netherlands consequently reduces about 50% caries in community. The study of fluor tablet 1 ppm/day at primary school children in Indonesia after one year study result show that fluor tablet can inhibit the caries experience 0.2 person/year, and in control group shows the increasing of caries experience 0.8 person/year, and there is no dental fluorosis found. There are some undesirable side-effects, however, that can accompany the desirable outcome of reduced caries in the community. Experience has shown that it is not possible to achieve effective fluoride­ based caries prevention without the development of some degree of dental fluorosis, a defect of enamel caused by excess fluoride disrupting the developing enamel prior to tooth eruption. This means that whatever methods are chosen to maintain the low level of fluoride in the mouth, the results will be accompanied by some degree of dental fluorosis. Dental public health administrators should be aware of the total fluoride exposure in the population before introducing any additional fluoride programme for caries prevention, and the cost-effentiveness of such programmes should be carefully

  12. Alara and radiodiagnostics

    International Nuclear Information System (INIS)

    Vano, E.; Gonzalez, L.; Wall, B.F.

    1989-01-01

    Specific items of diagnostic radiology facing the application to the ALARA approach are described, there differentiating among workers and patients. The convenience of assessing monetary values for the person. Sv in both cases is emphasized. The paper analyses some of the different steps to be considered in the optimization of diagnostic radiology installations, namely, rooms design and equipment selection, possibly modifications in installations currently working, requesting of radiological examinations, performing examinations and information exploitation. Some practical matters related to workers and patients are discussed, quoting several specific examples of optimization. The paper suggests, as conclusion, some practical guidelines of the stages to be covered along with the application of the ALARA approach

  13. ALARA training at INSTN

    International Nuclear Information System (INIS)

    Nolibe, D.; Lefaure, C.

    1994-01-01

    Since 1990 the CEPN, the National Radiological Protection Board and the INSTN organized for the first time in Europe one teaching specifically established to radioprotection optimization. This training has allowed to spread the experience of the best european specialists while guaranteeing a wide exchange between the participants coming from different countries. At the national level the training ALARA goes on at the INSTN-Saclay. Its aim is to give base notions, the methods and the tools allowing the implementation of the ALARA concept, and to privilege the exchange between the participants coming from different horizons. 2 refs., 2 figs

  14. BNL ALARA Center: ALARA Notes, No. 9

    International Nuclear Information System (INIS)

    Khan, T.A.; Xie, J.W.; Beckman, M.C.

    1994-02-01

    This issue of the Brookhaven National Laboratory's Alara Notes includes the agenda for the Third International Workshop on ALARA and specific instructions on the use of the on-line fax-on-demand service provided by BNL. Other topics included in this issue are: (1) A discussion of low-level discharges from Canadian nuclear plants, (2) Safety issues at French nuclear plants, (3) Acoustic emission as a means of leak detection, (4) Replacement of steam generators at Doel-3, Beaznau, and North Anna-1, (5) Remote handling equipment at Bruce, (6) EPRI's low level waste program, (7) Radiation protection during concrete repairs at Savannah River, (8) Reactor vessel stud removal/repair at Comanche Peak-1, (9) Rework of reactor coolant pump motors, (10) Restoration of service water at North Anna-1 and -2, (11) Steam generator tubing problems at Mihama-1, (12) Full system decontamination at Indian Point-2, (13) Chemical decontamination at Browns Ferry-2, and (14) Inspection methodolody in France and Japan

  15. ALARA for the practical person

    International Nuclear Information System (INIS)

    Kathren, R.L.

    1991-01-01

    The increasing significance of ALARA in recent years has spawned numerous articles and complex technological means to achieve as low as reasonably achievable. The available body of literature on ALARA has grown so large and complex that it is an overwhelming and virtually impossible task for a single individual to remain abreast of it. Regulatory requirements and interpretations of ALARA further add to the difficulties of the operational radiation protection staff seeking ALARA. The practical person can, however, promote and provide ALARA by recalling and applying certain simple principles, including the following, which will be discussed in depth: (1) ALARA is basic and fundamental to any program of radiological protection, and as such the ALARA program or practices must be specifically identifiable. (2) ALARA is a never ending quest, and much like the speed of light or halving the distance to the goal, can really never be reached in a theoretical sense. (3) ALARA is not necessarily synonymous with dose reduction, and certainly does not involve ever continuous reduction in dose. (4) There is no single monetary value applicable to a unit of dose; rather each incremental unit of dose must be examined in the total context of the exposure situation. (5) ALARA involves professional opinion and judgment; responsible and qualified professional health physicists may differ in their opinions as to what constitutes ALARA

  16. How reasonable is ALARA?

    International Nuclear Information System (INIS)

    Kiefer, H.

    1991-01-01

    The linear extrapolation of the established dose-effect relation at higher doses was accepted as a simple working hypothesis to determine dose limits for professional radiation personnel. It has been misused, however, for calculations of population risks in the very low dose region. This lead to an overestimation of radiation hazards by the public, followed by an overregulation of radiation protection. The ALARA recommendations of ICRP - justification of radiation application, optimisation of protection, and protection of the individual, - was aimed at counterpoising this trend and elucidate the aims of radiation protection. But even the ALARA principle will only be successful if it is applied with reason. The lend more weight to reason in radiation protection, an award for FS members is proposed, as well as an anti-award for the most nonsensical action in radiation protection. (orig.) [de

  17. ALARA: Progress and prospects

    International Nuclear Information System (INIS)

    Khan, T.A.; Baum, J.W.

    1988-01-01

    This paper has two main topics. The first part describes the establishment and work of the ALARA Center; the second part presents some results of studies at the Center with international data on doses at PWR plants. This data then is used to reach a preliminary understanding of some of the factors that are causing high doses at PWRs. This approach should help in reducing occupational exposures in a more effective manner

  18. ALARA/ALARP distinguished

    International Nuclear Information System (INIS)

    Riley, P.

    1992-01-01

    In the United Kingdom the term ALARA, ''as low as reasonably achievable'' and the term ALARP ''as low as reasonably practicable'' are used in regulations, in conditions in licenses, in assessment principles and in guidance notes used in the nuclear industry. In fact the ALARA principle is a cornerstone on which much of radiation protection regulation is based. The words ''reasonably practicable'' in ALARP have an established meaning in UK law and are used extensively in statutes and regulations, in particular The Health and Safety Act 1974. The Select Committee of the House of Lords on the European Communities in 1986 concluded that public opinion will play a much larger part in deciding the future of nuclear power than is usual with questions of science and technology. Under the circumstances it is important to industry and the general public for the terms used in legislation to be clear and unambiguous. This paper by distinguishing the terms ALARA/ALARP, sets the scene for a more disciplined use of the terms. (author)

  19. What is Alara

    International Nuclear Information System (INIS)

    Oudiz, A.; Lochard, J.; Lombard, J.; Croft, J.; Fleishman, A.; Webb, G.

    1986-09-01

    The system of dose limitation recommended by the International Commission on Radiological Protection formulates three radiation protection principles: 1) the so-called justification principle which states that no practice shall be adopted unless its introduction produces a positive net benefit; 2) the so-called optimisation principle which states that all exposures shall be kept as low as reasonably achievable, economic and social factors being taken into account; 3) the limitation of individual dose which insures that the dose equivalent to an individual shall not exceed the limits recommended by the ICRP. Acknowledging the fact that these requirements are interrelated, this report is devoted to a presentation of the second principle, assuming that the two other ones are satisfied. As defined by ICRP, the optimisation principle is strictly equivalent with the commonly known ALARA principle (As Low As Reasonably Achievable). ALARA may be considered altogether as a guiding principle for radiological protection management, as well as a procedure allowing the implementation of this principle

  20. EAN - The European ALARA Network; EAN - Le Reseau ALARA Europeen

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt-Hanning, A. [Office federal de la radioprotection (BfS) (Germany); Crouail, P.; Drouet, F. [Centre d' etude sur l' evaluation de la protection dans le domaine nucleaire (CEPN) (France); Shaw, P. [Agence de protection sanitaire (HPA) (United Kingdom); Vermeersch, F. [EAN, Centre d' etude de l' energie nucleaire (SCK-CEN) (Belgium)

    2010-11-15

    The optimisation of radiation protection, or ALARA principle, which requires that exposures to ionising radiation be kept as low as reasonably achievable taking into account economic and societal factors, is the cornerstone of the radiation protection system since the late eighties. For many years now, cooperation of experts from different professional backgrounds and different organisations in the European ALARA Network (EAN) has significantly contributed to the development of the ALARA principle and its practical implementation in a range of radiation protection areas in Europe. This contribution presents the evolution and key activities of EAN as well as its mode of operation aiming at sharing experience and disseminating the ALARA culture in all relevant domains. It also describes the new challenges facing EAN and the strategic objectives of the Network for the forthcoming years. (author)

  1. NHC's contribution to cleanup of the Hanford Site

    International Nuclear Information System (INIS)

    Chauve, H.D.

    1998-01-01

    The one billion dollars per year Project Hanford Management Contract (PHMC), managed by Fluor Daniel Hanford, calls for cleanup of the Hanford Site for the Department of Energy. Project Hanford comprises four major subprojects, each managed by a different major contractor. Numatec Hanford Corporation (NHC) is a fifth major subcontractor which provides energy and technology to each of the Hanford projects. NHC draws on the experience and capabilities of its parent companies, COGEMA and SGN, and relies on local support from its sister Company in Richland, COGEMA Engineering Corporation, to bring the best commercial practices and new technology to the Project

  2. Alara and work management

    International Nuclear Information System (INIS)

    Wahlstrom, B.

    1989-01-01

    All occupational radiation doses come out as a product of dose rates and exposure time, ie man-hours. In most cases there is not very much to be done about the dose rates, but by means of work management a lot can still be achieved. Non-technical factors which have an influence on the radiation doses are, for instance, work planning and co-ordination, training and know-how, optimization of the work force, health physics practice and time scheduling. These work management factors can be put to use at any nuclear power plant, regardless modern and clean or old and hot. As ALARA through work management in most cases means minimization of man-hours, it is worth while in two senses: One can save radiation doses and one can save money at the same time

  3. Project W-320 ALARA Plan

    International Nuclear Information System (INIS)

    Harty, W.M.

    1995-01-01

    This supporting document establishes the As Low As Reasonable Achievable (ALARA) Plan to be followed during Sluicing Project W-320 design and construction activities to minimize personnel exposure to radiation and hazardous materials

  4. Project W-320 ALARA Plan

    Energy Technology Data Exchange (ETDEWEB)

    Harty, W.M.

    1995-06-06

    This supporting document establishes the As Low As Reasonable Achievable (ALARA) Plan to be followed during Sluicing Project W-320 design and construction activities to minimize personnel exposure to radiation and hazardous materials.

  5. ALARA in European nuclear installations

    International Nuclear Information System (INIS)

    Lefaure, C.; Croft, J.; Pfeffer, W.; Zeevaert, T.

    1995-01-01

    For over a decade the Commission of the European Community has sponsored research projects on the development and practical implementation of the Optimization principle, or as it is often referred to, ALARA. These projects have given rise to a series of successful international Optimization training courses and have provided a significant input to the periodic European Seminars on Optimization, the last one of which took place in April 1993. This paper reviews the approaches to Optimization that have development within Europe and describes the areas of work in the current project. The on-going CEC research project addresses the problem of ALARA and internal exposures, and tries to define procedures for ALARA implementation, taking account of the perception of the hazard as well as the levels of probability of exposure. The relationships between ALARA and work management, and ALARA and decommissioning of installations appear to be other fruitful research areas. Finally, this paper introduces some software for using ALARA decision aiding techniques and databases containing feed back experience developed in Europe

  6. ALARA in European nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Lefaure, C. [CEPN, Fontenay-Aux-Roses (France); Croft, J. [NRPB, Chilton, Didcot (United Kingdom); Pfeffer, W. [GRS, Koeln (Germany); Zeevaert, T. [SCK/CEN, Mol (Belgium)

    1995-03-01

    For over a decade the Commission of the European Community has sponsored research projects on the development and practical implementation of the Optimization principle, or as it is often referred to, ALARA. These projects have given rise to a series of successful international Optimization training courses and have provided a significant input to the periodic European Seminars on Optimization, the last one of which took place in April 1993. This paper reviews the approaches to Optimization that have development within Europe and describes the areas of work in the current project. The on-going CEC research project addresses the problem of ALARA and internal exposures, and tries to define procedures for ALARA implementation, taking account of the perception of the hazard as well as the levels of probability of exposure. The relationships between ALARA and work management, and ALARA and decommissioning of installations appear to be other fruitful research areas. Finally, this paper introduces some software for using ALARA decision aiding techniques and databases containing feed back experience developed in Europe.

  7. ALARA for nuclear power plant operation

    International Nuclear Information System (INIS)

    Knapp, P.J.

    1979-01-01

    The concept of maintaining radiation exposures as low as reasonably achievable (ALARA) is outlined in connection with nuclear power plant operations. The basis of the concept is reviewed and a specific example of ALARA action is presented. (author)

  8. Radiation worker: the ALARA key

    International Nuclear Information System (INIS)

    Weedon, R.R.

    1985-01-01

    As low as reasonably achievable (ALARA) is a simple concept that has come to be a complicated and expensive regulatory goal. There are essentially three factors that can be manipulated to achieve ALARA: (1) radionuclide inventory (source), (2) physical arrangement (primarily distance and shielding); (3) radiation worker performance (radiation safety responsibilities and functions). Of these three elements, item 3 is utilized the least and yet has the greatest potential for reducing exposure per dollar expended. By establishing a relationship with radiation workers consisting of credible leadership and expecting the radiation workers to be responsible for specific elements of radiological safety. Health Physics can gain a degree of cooperation and performance that will provide significant ALARA gains at a very small expense

  9. ALARA at nuclear power plants

    International Nuclear Information System (INIS)

    Baum, J.W.

    1991-01-01

    Implementation of the ALARA principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed through a variety of dose reduction techniques. Initiatives by the ICRP, NCRP, NRC, INPO, EPRI, and BNL ALARA Center have all contributed to a heightened interest and emphasis on dose reduction. The NCRP has formed Scientific Committee 46-9 which is developing a report on ALARA at Nuclear Power Plants. It is planned that this report will include material on historical aspects, management, valuation of dose reduction ($/person-Sv), quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report

  10. Gentilly - 2 NGS ALARA program

    International Nuclear Information System (INIS)

    Rheaume, Michel R.

    1998-01-01

    This is a slide-based oral presentation given to the COG/IAEA: Fifth technical committee meeting on 'Exchange of operating experience of pressurized heavy water reactors' held in Mangalia, Romania on 7-10 September 1998. The operation experience of Gentilly -1 and Gentilly - 2 nuclear power stations is summarized. The radiation protection philosophy is addressed, the orange/yellow/green RP qualifications are explained and the ALARA Program objectives are described. The criteria used to develop the Gentilly - 2 station ALARA Program are presented. The program is based on: strong Hydro Quebec commitments, organization (responsibilities well defined); ALARA Committee; tools; procedures; good documentation. Description of the program is given then in details. Measures for dose and radioactive sources reduction are presented. Collective doses recorded at Gentilly - 2 between 1984 and 1997 are plotted and figures are given in a table

  11. Methodology for making environmental as low as reasonably achievable (ALARA) determinations

    International Nuclear Information System (INIS)

    Brown, R.C.; Speer, D.R.

    1982-01-01

    An overall evaluation concept for use in making differential cost-benefit analyses in environmental as low as reasonably achievable (ALARA) determinations is being implemented by Rockwell Hanford Operations. This evaluation includes consideration of seven categories: (1) capital costs; (2) operating costs; (3) state of the art; (4) safety; (5) accident or upset consequences; (6) reliability, operability, and maintainability; and (7) decommissionability. Appropriate weighting factors for each of these categories are under development so that ALARA determinations can be made by comparing scores of alternative proposals for facility design, operations, and upgrade. This method of evaluation circumvents the traditional basis of a stated monetary sum per person-rem of dose commitment. This alternative was generated by advice from legal counsel who advised against formally pursuing this avenue of approach to ALARA for environmental and occupational dose commitments

  12. ALARA Design Review for the Resumption of the Plutonium Finishing Plant (PFP) Cementation Process Project Activities

    CERN Document Server

    Dayley, L

    2000-01-01

    The requirements for the performance of radiological design reviews are codified in 10CFR835, Occupational Radiation Protection. The basic requirements for the performance of ALARA design reviews are presented in the Hanford Site Radiological Control Manual (HSRCM). The HSRCM has established trigger levels requiring radiological reviews of non-routine or complex work activities. These requirements are implemented in site procedures HNF-PRO-1622 and 1623. HNF-PRO-1622 Radiological Design Review Process requires that ''radiological design reviews [be performed] of new facilities and equipment and modifications of existing facilities and equipment''. In addition, HNF-PRO-1623 Radiological Work Planning Process requires a formal ALARA Review for planned activities that are estimated to exceed 1 person-rem total Dose Equivalent (DE). The purpose of this review is to validate that the original design for the PFP Cementation Process ensures that the principles of ALARA (As Low As Reasonably Achievable) were included...

  13. ALARA and planning of interventions

    Energy Technology Data Exchange (ETDEWEB)

    Rocaboy, A. [Electricite de France, Avoine (France)

    1995-03-01

    The implementation of ALARA programs implies integration of radiation protection criterion at all stages of outage management. Within the framework of its ALARA policy, Electricide de France (EDF) has given an incentive to all of its nuclear power plants to develop {open_quotes}good practices{close_quotes} in this domain, and to exchange their experience by the way of a national feed back file. Among the developments in the field of outage organization, some plants have focused on the planning stage of activities because of its influence on the radiological conditions of interventions and on the good succession of tasks within the radiological controlled areas. This paper presents the experience of Chinon nuclear power plant. At Chinon, we are pursuing this goal through careful outage planning. We want the ALARA program during outages to be part of the overall maintenance task planning. This planning includes the provision of the availability of every safety-related component, and of the variations of water levels in hthereactor and steam generators to take advantage of the shield created by the water. We have developed a computerized data base with the exact position of all the components in the reactor building in order to avoid unnecessary interactions between different tasks performed in the same room. A common language between Operation and Maintenance had been established over the past years, using {open_quotes}Milestones and Corridors{close_quotes}. A real time dose rate counting system enables the Radiation Protection (RP) Department to do an accurate and efficient follow up during the outage for all the {open_quotes}ALARA{close_quotes} maintenance tasks.

  14. Catawba nuclear station preoperational ALARA review

    International Nuclear Information System (INIS)

    Deal, W.P.

    1985-01-01

    This paper describes the particular emphasis placed on preoperational as los as reasonably achievable (ALARA) considerations at Duke Power's Catawba Nuclear Station. A strong station commitment to the ALARA philosophy, and review of existing capabilities, led to development of an aggressive two-part ALARA program. Capabilities consisted of sufficient numbers of available personnel, lengthy lead time during construction, a very detailed plastic model, and a sister plant of similar design. The program, as developed, consisted of a preoperational program, which looked at design and construction aspects of ALARA, and the operational program, dealing with the ALARA committee and operational problems. MAnagement's philosophy of holding everyone responsible for ALARA provided the motivation to organize the preoperational program to use that resource. The Health Physics group accepted responsibility for development, coordination, and reviewer training. The problem provided a base to build on as station personnel gained experience in their own crafts and radiation protection in general

  15. ALARA Center of Technology -- resource guide

    International Nuclear Information System (INIS)

    Waggoner, L.O.

    1998-01-01

    The purpose is to provide a source of information that can be used to assist personnel in the planning, training, and execution of radiological work using the principles of ALARA. This document is not intended to replace HNF or WHC Control Manual requirements. The ALARA Tools-List provides detailed information on the use and procurement of engineered controls, mockup training guidelines, and good radiological work practices that have been proven to be ALARA

  16. ALARA Center of Technology -- resource guide

    Energy Technology Data Exchange (ETDEWEB)

    Waggoner, L.O.

    1998-02-05

    The purpose is to provide a source of information that can be used to assist personnel in the planning, training, and execution of radiological work using the principles of ALARA. This document is not intended to replace HNF or WHC Control Manual requirements. The ALARA Tools-List provides detailed information on the use and procurement of engineered controls, mockup training guidelines, and good radiological work practices that have been proven to be ALARA.

  17. Integrating ALARA into work planning and organization

    International Nuclear Information System (INIS)

    Croft, J.R.; Robb, J.D.

    1993-01-01

    This paper presents various organizational structures and systematic approaches that can be of benefit in integrating ALARA into work planning and organization. It is possible to have elegant policy statements, procedures and organizations and yet fail to implement ALARA effectively. The real key to success in ALARA work management is to recognize that ALARA is primarily a way of thinking and to secure the commitment of individuals at all levels within the organization, from senior management to workers carrying out specific tasks. The authors explain that the recommendations of ICRP Publication 60 will have an impact and will maintain the downward pressure on individual doses. 6 figs

  18. Chernobyl information: The ALARA backlash

    International Nuclear Information System (INIS)

    Samuelsson, C.

    2000-01-01

    The risk information to the public failed after the Chernobyl accident, also in countries where radiation protection authorities and experts initially enjoyed public confidence. In contrast to many other large accidents, the responsibility for the information failure stays mainly with the authorities and experts themselves, not with the mass media. Many factors together caused the radiation risk information from SSI (Swedish Radiation Protection Institute), and its sister authorities in many other countries, to be confusing and inadequate, despite the best of intentions. The two major malefactors were the handling of food contamination restrictions and the short-sighted risk optimisation by applying the ALARA principle. In addition, the assurance that the Chernobyl contamination was fairly harmless made no sense to the layman, as a massive array of controlling procedures was enforced simultaneously. The food regulations became unfortunately focused on becquerel per kilogram limits instead of the primary goal, a dose reduction per year, corresponding to an yearly intake of Cs-137. The lesson learned is that the risk significant long-term intake ambition must be understood and digested by laymen and media, before any secondary limits, e.g. the activity concentration of foodstuffs expressed as becquerel per kg, for controlling or trading purposes, are introduced. As it were, the experts and authorities lost credibility, due to what people considered as ambiguities. The concept of ALARA (As Low As Readily Achievable) is in the backbone of every ionising radiation expert, and a useful strategy for optimising dose burdens during controlled situations. In connection to the Chernobyl accident many advices to the public was given based on the ALARA principle. 'Rinse leafy vegetables' sounds at first very reasonable, cheap and innocent, but if the averted dose is low, such an advice should not be given. The individual dose-reduction should be weighted against all negative

  19. QUEST Hanford Site Computer Users - What do they do?

    Energy Technology Data Exchange (ETDEWEB)

    WITHERSPOON, T.T.

    2000-03-02

    The Fluor Hanford Chief Information Office requested that a computer-user survey be conducted to determine the user's dependence on the computer and its importance to their ability to accomplish their work. Daily use trends and future needs of Hanford Site personal computer (PC) users was also to be defined. A primary objective was to use the data to determine how budgets should be focused toward providing those services that are truly needed by the users.

  20. Computer and computer graphics support for the ALARA program

    International Nuclear Information System (INIS)

    Paine, D.; Hall, C.J.

    1984-01-01

    Computer programs have been developed which support three aspects of the ALARA program at Rockwell Hanford Operations (RHO): 1) Setting annual dose and skin contamination goals, 2) Analyzing trends in operational organizations' dose, numbers of skin contaminations, or radiation occurrences, and 3) Presenting graphic displays to enhance worker safety awareness. Programs have been written which search dosemetry files and produce histograms of annual occupational exposure and skin contamination histories utilizing the DISSPLA software or a desk top color graphics terminal. These programs and associated graphics are used to assemble dose and skin contamination information in a summary format so that ALARA teams can assess the past year's performance and establish reduction goals for the coming year. In addition, the graphics provide a management tool for recognizing desirable or undesirable trends in an organization's occupational dose or number of skin contaminations. Desk top graphics capabilities have been used to display safety-related data to enhance management review and worker awareness of radiological and industrial safety conditions in the work area. The following graphs are prepared on a monthly basis: 1) Numbers of skin contaminations company wide and for specific operating organizations within the company, 2) Numbers of radiation occurrences, 3) Dose histories for specific operational organizations, 4) Numbers of OSHA recordable incidents, 5) OSHA recordable incident rates and severity levels and 6) Lost workday cases

  1. Practical quantitative measures of ALARA

    International Nuclear Information System (INIS)

    Kathren, R.L.; Larson, H.V.

    1982-06-01

    Twenty specific quantitative measures to assist in evaluating the effectiveness of as low as reasonably achievable (ALARA) programs are described along with their applicability, practicality, advantages, disadvantages, and potential for misinterpretation or dortion. Although no single index or combination of indices is suitable for all facilities, generally, these five: (1) mean individual dose equivalent (MIDE) to the total body from penetrating radiations; (2) statistical distribution of MIDE to the whole body from penetrating radiations; (3) cumulative penetrating whole body dose equivalent; (4) MIDE evaluated by job classification; and (5) MIDE evaluated by work location-apply to most programs. Evaluation of other programs may require other specific dose equivalent based indices, including extremity exposure data, cumulative dose equivalent to organs or to the general population, and nonpenetrating radiation dose equivalents. Certain nondose equivalent indices, such as the size of the radiation or contamination area, may also be used; an airborne activity index based on air concentration, room volume, and radiotoxicity is developed for application in some ALARA programs

  2. Applied ALARA Workshops Richland, Washington

    International Nuclear Information System (INIS)

    DECKER, W.A.

    1999-01-01

    The purpose of this standard is to provide Project Hanford Management Contractors (PHMC) with guidance for ensuring radiological considerations are adequately addressed throughout the work planning process. Incorporating radiological controls in the planning process is a requirement of the Hanford Site Radiological Control Manual (HSRCM-I), Chapter 3, Part 1. This standard is applicable to all PHMC contractors and subcontractors. The essential elements of this standard will be incorporated into the appropriate site level work control standard upon implementation of the anticipated revision of the PHMC Administration and Procedure System

  3. Preliminary ALARA design concept for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyo Youn; Kim, Seung Nam; Kim, Ha Yong; Zee, Sung Quun; Chang, Moon Hee

    1999-03-01

    SMART(System-integrated Modular Advanced ReacTor) is a space saving integral type nuclear rector with the thermal power of 330 MW. This report provides general design guide and authority in NSSS designs for SMART needed to maintain the occupational doses and doses to members of public ALARA to meet the regulatory requirements. Paragraph 20.1 of 10 CFR 20, ''Standards for Protection Against Radiation'', states that licensee should make every reasonable effort to maintain exposures to radiation as far below the limits specified in Part 20 as is reasonably achievable. The ALARA (as low as is reasonably achievable) principle is incorporated into Korean radiation protection law as paragraph one Article 97 of the Atomic Energy Act. (Jan. 1995). This ALARA Design Concept for SMART provides 1) description of the organization and responsibilities needed for upper level management support and authority in order for the implementation of ALARA, 2) guidance and procedures for design, review, and evaluation needed for SMART ALARA program implementation, 3) general design guidelines for SMART NSSS and BOP designers to implement ALARA principles in design stage, and 4) training and instruction requirement of SMART NSSS and BOP designers for the familiarization of ALARA principles to be implemented in NSSS designs. (Author). 4 refs., 1 tabs.

  4. Preliminary ALARA design concept for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyo Youn; Kim, Seung Nam; Kim, Ha Yong; Zee, Sung Quun; Chang, Moon Hee

    1999-03-01

    SMART(System-integrated Modular Advanced ReacTor) is a space saving integral type nuclear rector with the thermal power of 330 MW. This report provides general design guide and authority in NSSS designs for SMART needed to maintain the occupational doses and doses to members of public ALARA to meet the regulatory requirements. Paragraph 20.1 of 10 CFR 20, ''Standards for Protection Against Radiation'', states that licensee should make every reasonable effort to maintain exposures to radiation as far below the limits specified in Part 20 as is reasonably achievable. The ALARA (as low as is reasonably achievable) principle is incorporated into Korean radiation protection law as paragraph one Article 97 of the Atomic Energy Act. (Jan. 1995). This ALARA Design Concept for SMART provides 1) description of the organization and responsibilities needed for upper level management support and authority in order for the implementation of ALARA, 2) guidance and procedures for design, review, and evaluation needed for SMART ALARA program implementation, 3) general design guidelines for SMART NSSS and BOP designers to implement ALARA principles in design stage, and 4) training and instruction requirement of SMART NSSS and BOP designers for the familiarization of ALARA principles to be implemented in NSSS designs. (Author). 4 refs., 1 tabs.

  5. Preliminary ALARA design concept for SMART

    International Nuclear Information System (INIS)

    Kim, Kyo Youn; Kim, Seung Nam; Kim, Ha Yong; Zee, Sung Quun; Chang, Moon Hee

    1999-03-01

    SMART(System-integrated Modular Advanced ReacTor) is a space saving integral type nuclear rector with the thermal power of 330 MW. This report provides general design guide and authority in NSSS designs for SMART needed to maintain the occupational doses and doses to members of public ALARA to meet the regulatory requirements. Paragraph 20.1 of 10 CFR 20, ''Standards for Protection Against Radiation'', states that licensee should make every reasonable effort to maintain exposures to radiation as far below the limits specified in Part 20 as is reasonably achievable. The ALARA (as low as is reasonably achievable) principle is incorporated into Korean radiation protection law as paragraph one Article 97 of the Atomic Energy Act. (Jan. 1995). This ALARA Design Concept for SMART provides 1) description of the organization and responsibilities needed for upper level management support and authority in order for the implementation of ALARA, 2) guidance and procedures for design, review, and evaluation needed for SMART ALARA program implementation, 3) general design guidelines for SMART NSSS and BOP designers to implement ALARA principles in design stage, and 4) training and instruction requirement of SMART NSSS and BOP designers for the familiarization of ALARA principles to be implemented in NSSS designs. (Author). 4 refs., 1 tabs

  6. Fluor group all around the world

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    A brief survey of world-wide activities of Fluor Corp. and Fluor Engineers and Constructors Inc. in 1977-78 covers the participation of the Fluor Group in the construction of the Trans-Alaskan pipeline; management of Saudi Arabia's gas gathering and treatment program; construction of a 500 million cu ft/day gas processing plant in Abu Dhabi; a contract from Sonatrach to build by 1981 a 600 million cu ft/day gas processsing plant and pipelines for the Alrar field in Algeria; a $600 million modernization of the Amuay refinery in Venezuela and an $8 million project for lowering the pour point of gas oil at Mobil A.G.'s Wilhelmshaven refinery; offshore oil and gas development projects off the Ivory Coast and in the Aegean sea; construction of a 568 km subsea and 176 km onshore gas pipeline and gas-processing facilities in Thailand; and a long-term program for the industrialization of Ruwais, in Abu Dhabi, including the construction of a port with a major LNG terminal.

  7. Overview, what is ALARA? Are we there?

    International Nuclear Information System (INIS)

    Baum, J.W.

    1987-01-01

    As low as reasonably achievable (ALARA) in radiation protection at nuclear power plants is a complex criterion involving decisions requiring both professional judgement and quantitation. Professional judgement has been emphasized in most plants to date. However, unless quantitative studies are made it will be difficult to judge if doses at US plants are ALARA. An ALARA assessment for each plant is suggested, which would include evaluations of both qualitative, e.g., organizational, and quantitative, e.g., cost-benefit or cost-effectiveness, efforts. 15 refs., 4 tabs

  8. Alara - from theory towards practice

    International Nuclear Information System (INIS)

    Lochard, J.; Lombard, J.; Stokell, P.J.; Croft, J.R.

    1991-01-01

    The Alara principle states that all exposures shall be kept as low as reasonably achievable, economic and social factors being taken into account. It is a simple concept - the idea behind it is widely used in nearly all spheres of life, i.e. to do the best one can under the given circumstances. This book aims to help define what is meant by best in the context of radiation protection. It describes a procedure that is useful in structuring one's approach to any particular situation where a decision as to the best course of action is required. It also provides practical guidance on how the concept can be incorporated into radiation protection programmes. This book has been written as a reference manual on both the theoretical and practical aspects of the subject. But it is especially targeted at those involved in radiation protection at the practical level

  9. Can practical ALARA be taught?

    International Nuclear Information System (INIS)

    Guest, R. Monty

    2008-01-01

    Full text: Purpose: Outside of the nuclear industry, many users of sources of ionising radiation may be characterised as 'High Frequency/Low Dose' users. It is argued here that they have special training requirements in order to understand the ICRP concept ALARA, indeed all the fundamental concepts of radiological protection and their relevance to the workplace. It is not practicable to practise dose avoidance in many situations so dose reduction becomes even more important. For example, laboratory life sciences researchers often have to use very small quantities and activities of beta emitting radioisotopes which give small or minuscule external doses to well trained workers but can give extremely serious high doses if mishandled Similarly, dentists routinely use 60- 100 kV X-ray generators to diagnose abnormalities and disease which other techniques would fail to detect. By practising simple and effective dose reduction methods, they can reduce the dose to themselves and their patients to arguably trivial levels. Method: The paper will use examples from Radiation Protection Supervisors courses run over the past 6 years for UK pharmaceutical companies and research into courses for general dental practitioners run over the past 8 years in East Anglia, England. The latter courses must meet the requirements laid down in the Ionising Radiation (Medical Exposure) Regulations 2000 and the requirements of the professional dental association, the British Dental Council, and the continuing professional development requirements of the dental registration body, the General Dental Council. Major Findings and Conclusions: The research findings show an urgent need to train dental practitioners in the concepts and practical aspects of dose avoidance and dose minimisation, social and economic factors being considered. Pharmaceutical company research Radiation Protection Supervisors are generally well trained but also need to know the practical implications of the ALARA principle

  10. ALARA trademark 1146 strippable coating

    International Nuclear Information System (INIS)

    Fricke, V.

    1999-01-01

    Strippable or temporary coatings are innovative technologies for decontamination that effectively reduce loose contamination at low cost. These coatings have become a viable option during the deactivation and decommissioning of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. The ALARA trademark 1146 strippable coating was demonstrated as part of the Savannah River Site LSDDP and successfully removed transferable (surface) contamination from multiple surfaces (metal and concrete) with an average decontamination factor for alpha contamination of 6.68 and an average percentage of alpha contamination removed of 85.0%. Beta contamination removed was an average DF of 5.55 and an average percentage removed of 82.0%. This paper is an Innovative Technology Summary Report designed to provide potential users with the information they need to quickly determine if a technology would apply to a particular environmental management problem. They also are designed for readers who may recommend that a technology be considered by prospective users. This Innovative Technology offers a 35% cost savings over the Baseline Technology

  11. Hanford Waste Vitrification Project overview and status

    International Nuclear Information System (INIS)

    Swenson, L.D.; Smets, J.L.

    1993-01-01

    The Hanford Waste Vitrification Project (HWVP) is being constructed at the US DOE's Hanford Site in Richland, WA. Engineering and design are being accomplished by Fluor Daniel Inc. in Irvine, CA. Technical input is furnished by Westinghouse Hanford Co. and construction management services by UE ampersand C-Catalytic Inc. The HWVP will immobilize high level nuclear waste in a glass matrix for eventual disposal in the federal repository. The HWVP consists of several structures, the major ones being the Vitrification Building, the Canister Storage Building, fan house, sand filter, waste hold tank, pump house, and administration and construction facilities. Construction started in April 1992 with the clearing and grubbing activities that prepared the site for fencing and construction preparation. Several design packages have been released for procurement activities. The most significant package release is for the Canister Storage Building, which will be the first major structure to be constructed

  12. The organization of ALARA program at a DOE facility

    International Nuclear Information System (INIS)

    Setaro, J.A.

    1992-01-01

    The organization of an ALARA Program at a DOE Facility (Oak Ridge National Laboratory), it's relationship with laboratory management, facility operators, and the radiation protection program is described. The use of chartered ALARA committees at two distinct levels is discussed

  13. Fuel transfer system ALARA design review - Project A.15

    International Nuclear Information System (INIS)

    KUEBERTH, L.R.

    2001-01-01

    One mission of the Spent Nuclear Fuel (SNF) Project is to move the SNF from the K Basins in the Hanford 100K Area to an interim dry storage at the Canister Storage Building (CSB) in the Hanford 200 East Area. The Fuel Transfer System (FTS) is a subproject that will move the SNF from the 105K East (KE) Facility to the 105K West (KW) Facility. The SNF will be treated for shipment to the Cold Vacuum Drying (CVD) facility at the KW Basin. The SNF canisters will be loaded underwater into a Shielded Transfer Cask (STC) in the KE Basin. The fully loaded STC will be brought out of the water and placed into a Cask Transfer Overpack (CTO) by the STC Straddle Carrier. As the STC is removed from the water, it will be washed down with demineralized water by an manual rinse system. The CTO with the STC inside will be placed on a transport trailer and transferred to the KW Basin as an intra-facility transfer. The CTO will be unloaded from the shipping trailer at the KW Basin and the STC will be removed from the CTO. The STC will then be lowered into the KW Basin water and the fuel will be removed. The SNF will then be processed for shipment to the CVD. As soon as all of the fuel has been removed from the STC, the cask will be removed from the KW Basin water and placed into the CTO. The CTO will again be placed on the trailer for transport back to the KE Basin where the entire cycle will be repeated approximately 400 times. This document records the As Low As Reasonably Achievable (ALARA) findings and design recommendations/requirements by the SNF Project noted during the Final Design Review of the STC, CTO, STC Transfer System, Annexes and Roadways for support of FTS. This document is structured so that all statements that include the word ''shall'' represent design features that have been or will be implemented within the project scope. Statements that include the words ''should'' or ''recommend'' represent ALARA design features to be evaluated for future implementation

  14. UPDATE HANFORD SITE D and D PROGRAMS ACCELERATE EXPAND

    International Nuclear Information System (INIS)

    GERBER, M.S.

    2004-01-01

    A large, new decontamination and decommissioning organization targeted toward rapid, focused work on aging and highly contaminated structures was formed at the DOE's Hanford Site in southeast Washington state in autumn 2003. Managed by prime contractor Fluor Hanford, the new organization has made significant progress during its first six months. Under the direction of Mike Lackey, who recently joined Fluor from the Portland General Electric Trojan Plant, the Fluor Hanford DandD organization is tackling the Plutonium Finishing Plant (PFP) complex and the Fast Flux Test Facility (FFTF), and is nearly finished demolishing the 233-S Plutonium Concentration Facility. In addition, the DandD organization is progressing through the development and public comment phases of its required environmental permitting, planning work and procurement services to DandD three other Hanford facilities: 224-T and 224-B Plutonium Concentration Facilities, and the U Plant radiochemical processing facility. It is also planning and beginning to DandD the spent fuel handling areas of the Site's 100-K Reactor Area. The 586-square mile Hanford Site, the oldest plutonium production center in the world, served as the ''workhorse'' of the American nuclear defense arsenal from 1944 through 1989. Hanford produced the special nuclear material for the plutonium cores of the Trinity (test) and Nagasaki explosions, and then went on to produce more than half of the weapons plutonium ever manufactured by the United States, and about one-fourth of that manufactured worldwide. As a result, Hanford, the top-secret ''Paul Bunyan'' in the desert, is one of the most contaminated areas in the world. Its cleanup agreement with state and federal regulators, known as the ''Tri-Party Agreement,'' celebrates its 15th anniversary this spring, at a time when operations dealing with unstable plutonium leftovers, corroded spent fuel, and liquids wastes in single-shelled tanks conclude. As these crucial jobs are coming to

  15. ALARA implementation throughout project life cycle

    Energy Technology Data Exchange (ETDEWEB)

    Haynes, M.J. [Ontario Hydro, Whitby, Ontario (Canada)

    1995-03-01

    A strength of radiation protection programs generally has been endorsement and application of the ALARA principle. In Ontario Hydro, which currently operates 20 commercial size nuclear units, great strides have been made in the last three decades in reducing occupational radiation exposure per unit of electricity generated. This paper will discuss specific applications of elements of the overall ALARA program which have most contributed to dose reduction as the nuclear program has expanded. This includes such things as management commitment, ALARA application in the design phase and major rehabilitation work, the benefits of the self protection concept, a specific example of elimination (or reduction) of the source term and the importance of dose targets. Finally, it is concluded that the major opportunities for further improvements may lie in the area of information management.

  16. Maintaining occupational dose ALARA through work management

    International Nuclear Information System (INIS)

    Khan, A. H.

    1999-01-01

    Canadian philosophy in keeping occupational dose ALARA has been to train staff in radiation safety so that they can be fully responsible for participating in minimizing the risks associated with the hazardous work. Senior managers actively promote high standards of performance in dose reduction techniques as a means for integrating ALARA into the operation and maintenance of the station by all personnel. Minimizing radiation dose is accomplished by applying cost effective work management techniques such as Job Safety Analysis, pre-job briefings and establishing and achieving radiation dose goals. Radiation dose goals are used as a management tool for involving all work groups in reducing doses as well as providing a means of assessing the effectiveness of dose reduction actions. ALARA, along with conventional safety, is used as a lever to raise the standard of quality of work and to overall build a safety culture. (author). 4 figs

  17. SGN-Reseau Eurisys participates to the Hanford military site rehabilitation

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    Numatec Hanford Corporation, a subsidiary company of SGN-Reseau Eurisys and Cogema, gained with Fluor Daniel the contract for the rehabilitation of the old military nuclear centre of Hanford (Washington, USA). This contract of 5 years represents 5 billions of US dollars with 300 millions of dollars for the French part. This short paper gives a general description of the Hanford installations and of the partners involved in the contract: Fluor Daniel consortium, Lockheed Martin, Babcock and Wilcox, Duke Engineering and Services, Rust Federal Services, Numatec Hanford Corporation (NHC), SGN-Eurisys Services Corporation (SESC). The schedule comprises: the stabilisation of the residual plutonium in all installations before December 1999, the removal of muds and debris from the K storage pool of irradiated fuels before June 2000, the draining and cleaning of the high activity storage tanks before December 2001 and the general decontamination of the installations up to the year 2005. (J.S.)

  18. ALARA in practice: How is it working

    International Nuclear Information System (INIS)

    Webb, G.A.M.; Lochard, J.

    1984-01-01

    At the first CEC scientific seminar on optimisation in 1979 (21) most of the papers were concerned with possible methodologies for quantification of the ALARA concept and difficulties in applying them. Very few gave even theoretical examples of how it could be applied in practice. In contrast, at this second seminar most of the papers are examples of how quantified techniques have been used to assist towards ALARA decisions. This rapporteurs paper examines the quantification frameworks available and how they are being used in practice on the basis of the papers presented at this meeting

  19. ALARA efforts in nordic BWRs

    Energy Technology Data Exchange (ETDEWEB)

    Ingemansson, T.; Lundgren, K.; Elkert, J. [ABB Atom, Vaesteraes (Sweden)

    1995-03-01

    Some ALARA-related ABB Atom projects are currently under investigation. One of the projects has been ordered by the Swedish Radiation Protection Institute, and two others by the Nordic BWR utilities. The ultimate objective of the projects is to identify and develop methods to significantly decrease the future exposure levels in the Nordic BWRS. As 85% to 90% of the gamma radiation field in the Nordic BWRs originates from Co-60, the only way to significantly decrease the radiation doses is to effect Co and Co-60. The strategy to do this is to map the Co sources and estimate the source strength of Co from these sources, and to study the possibility to affect the release of Co-60 from the core surfaces and the uptake on system surfaces. Preliminary results indicate that corrosion/erosion of a relatively small number of Stellite-coated valves and/or dust from grinding of Stellite valves may significantly contribute to the Co input to the reactors. This can be seen from a high measured Co/Ni ratio in the feedwater and in the reactor water. If stainless steel is the only source of Co, the Co/Ni ratio would be less than 0.02 as the Co content in the steel is less than 0.2%. The Co/Ni ratio in the reactor water, however, is higher than 0.1, indicating that the major fraction of the Co originates from Stellite-coated valves. There are also other possible explanations for an increase of the radiation fields. The Co-60 inventory on the core surfaces increases approximately as the square of the burn-up level. If the burn-up is increased from 35 to 5 MWd/kgU, the Co-60 inventory on the core surfaces will be doubled. Also the effect on the behavior of Co-60 of different water chemistry and materials conditions is being investigated. Examples of areas studied are Fe and Zn injection, pH-control, and different forms of surface pre-treatments.

  20. ALARA and radiation protection optimization status of Cernavoda NPP

    International Nuclear Information System (INIS)

    Hau, D.I.

    2000-01-01

    ALARA in Radiation Protection is specifically applied as a tool in lowering B the risk of high exposure when performing necessary activities by reducing the doses as much and as reasonably possible. Is ALARA also a matter of IMAGE? ALARA is one of the main aspects that contributes to forming the image of a certain facility. Many experiences in the world show a decrease in the collective dose per station after proper ALARA implementation. This trend is more relevant for 'adult' nuclear sites. At Cernavoda NPP the authorization process itself included implementation of an effective ALARA program. (author)

  1. Shippingport station decommissioning project ALARA Program

    Energy Technology Data Exchange (ETDEWEB)

    Crimi, F.P. [Lockheed Environmental Systems and Technology Co., Houston, TX (United States)

    1995-03-01

    Properly planned and implemented ALARA programs help to maintain nuclear worker radiation exposures {open_quotes}As Low As Reasonably Achievable.{close_quotes}. This paper describes the ALARA program developed and implemented for the decontamination and decommissioning (D&D) of the Shippingport Atomic Power Station. The elements required for a successful ALARA program are discussed along with examples of good ALARA practices. The Shippingport Atomic Power Station (SAPS) was the first commercial nuclear power plant to be built in the United States. It was located 35 miles northwest of Pittsburgh, PA on the south bank of the Ohio river. The reactor plant achieved initial criticality in December 1959. During its 25-year life, it produced 7.5 billion kilowatts of electricity. The SAPS was shut down in October 1982 and was the first large-scale U.S. nuclear power plant to be totally decommissioned and the site released for unrestricted use. The Decommission Project was estimated to take 1,007 man-rem of radiation exposure and $.98.3 million to complete. Physical decommissioning commenced in September 1985 and was completed in September 1989. The actual man-rem of exposure was 155. The project was completed 6 months ahead of schedule at a cost of $91.3 million.

  2. ALARA in radioactive waste management- Summary and recommendations of the 11. European ALARA Network Workshop

    International Nuclear Information System (INIS)

    Shaw, P.; Crouail, P.; Drouet, F.

    2008-01-01

    The 11. European ALARA Network (E.A.N.) workshop on 'ALARA in radioactive waste management' took place in Athens (Greece) in April 2008. The aim of that workshop was to focus on the implementation of the ALARA principle with regard to occupational and public exposures arising from the management of radioactive waste in all sectors (nuclear, medical, industrial, etc.). This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. Individual presentations (papers and slides) are available to download from the E.A.N. web site (http://www.eu-alara.net). Based on report backs from the groups and discussions with all the participants, five formal recommendations have been formulated. These recommendations, addressed to international organisations (International Atomic Energy Agency, European Commission, Nuclear Energy Agency), national authorities, national and local stake holders and to E.A.N. itself, deal with the following themes: international guidance on ALARA in radioactive waste management, harmonization issues at the international level, ALARA approach in non-nuclear waste management, 'broader approach' in the radioactive waste management process, stake holder involvement. The objective of this paper is to present the main conclusions and the five recommendations produced during the workshop. (authors)

  3. Tolerancing requirements for remote handling at the Hanford vitrification project

    International Nuclear Information System (INIS)

    Keenan, R.M.; Bullis, R.E.; Van Katwijk, C.

    1993-01-01

    The Hanford Waste Vitrification Plant is being designed by Fluor Daniel, Inc. with WasteChem Corporation as Fluor Daniel's major subcontractor specializing in vitrification and remote system technologies. United Engineers and Constructors/Catalytic (UE ampersand C) will construct the plant. Westinghouse Hanford Company (WHC) is the Project Integration manager, manager and as the plant operator provides technical direction to the Architect/Engineer team (A/E) and constructor on behalf of the Department of Energy - Richland Field Office. The A/E has developed, in cooperation with UE ampersand C, WHC and DOE, a new and innovative approach to installations of the many remote nozzles and electrical connectors that must be installed to demanding tolerances. This paper summarizes the key elements of the HWVP approach

  4. Steam generator replacement from ALARA aspects

    International Nuclear Information System (INIS)

    Terry, I.; Breznik, B.

    2003-01-01

    This paper is going to consider radiological related parameters important for steam generator replacement (SGR) implementation. These parameters are identified as ALARA related parameters, owner-contractor relationship, planning, health physics with logistic services, and time required for the replacement. ALARA related parameters such as source or initial dose rate and plant system configuration define the initial conditions for the planning. There is room to optimise work planning. managerial procedures and also the staff during the implementation phase. The overview of these general considerations is based on the following background: using internationally available data and the experience of one of the vendors, i.e. Siemens-Framatome, and management experience of SG replacement which took place at Krsko NPP in the spring of 2000. Generally plant decisions on maintenance or repair procedures under radiation conditions take into account ALARA considerations. But in the main it is difficult to adjudge the results of an ALARA study, usually in the form of a collective dose estimate, because a comparison standard is missing. That is, very often the planned work is of a one-off nature so comparisons are not possible or the scopes are not the same. In such a case the collective doses for other types of work are looked at and a qualitative evaluation is made. In the case of steam generator replacement this is not the case. Over years of steam generator replacements world-wide a standard has been developed gradually. The first part of the following displays an overview of SGR and sets the Krsko SGR in perspective by applying dose analysis. The second part concentrates on the Krsko SGR itself and its ALARA aspects. (authors)

  5. Hanford wells

    International Nuclear Information System (INIS)

    McGhan, V.L.; Myers, D.A.; Damschen, D.W.

    1976-03-01

    The Hanford Reservation contains about 2100 wells constructed from pre-Hanford Works to the present. As of Jan. 1976, about 1800 wells still exist, 850 of which were drilled to the groundwater table; 700 still contain water. This report provides the most complete documentation of these wells and supersedes all previous compilations, including BNWL-1739

  6. Reengineering Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Badalamente, R.V.; Carson, M.L.; Rhoads, R.E.

    1995-03-01

    The Department of Energy Richland Operations Office is in the process of reengineering its Hanford Site operations. There is a need to fundamentally rethink and redesign environmental restoration and waste management processes to achieve dramatic improvements in the quality, cost-effectiveness, and timeliness of the environmental services and products that make cleanup possible. Hanford is facing the challenge of reengineering in a complex environment in which major processes cuts across multiple government and contractor organizations and a variety of stakeholders and regulators have a great influence on cleanup activities. By doing the upfront work necessary to allow effective reengineering, Hanford is increasing the probability of its success.

  7. Reengineering Hanford

    International Nuclear Information System (INIS)

    Badalamente, R.V.; Carson, M.L.; Rhoads, R.E.

    1995-03-01

    The Department of Energy Richland Operations Office is in the process of reengineering its Hanford Site operations. There is a need to fundamentally rethink and redesign environmental restoration and waste management processes to achieve dramatic improvements in the quality, cost-effectiveness, and timeliness of the environmental services and products that make cleanup possible. Hanford is facing the challenge of reengineering in a complex environment in which major processes cuts across multiple government and contractor organizations and a variety of stakeholders and regulators have a great influence on cleanup activities. By doing the upfront work necessary to allow effective reengineering, Hanford is increasing the probability of its success

  8. Cost basis for implementing ALARA programs

    International Nuclear Information System (INIS)

    Kent, C.E.

    1985-01-01

    A method of implementing effective ALARA programs is discussed. A basic element of the cost benefit methodology is the valuation of a man-rem. In the program, this is derived from an assessment of radiation exposure risk and societal valuation of harmful effects. The man-rem value is used as an element in the cost benefit analysis. The analysis includes an assessment of the differential man-rem resulting from the action, implementation cost, and operational savings

  9. ALARA in the radiation protection training

    International Nuclear Information System (INIS)

    Nolibe, D.; Lefaure, Ch.

    1998-01-01

    This part treats especially the question of the training in radiation protection. The electro nuclear sector has given an ALARA principle culture and succeeded to sensitize each level of hierarchy, but for small industry, the research and the medical world the same method appears more difficult to use. It seems better to reinforce the importance of the competent person and to include a training in radiation protection on the initial formation in numerous professional categories. (N.C.)

  10. Management organization and administration for ALARA

    International Nuclear Information System (INIS)

    Kathren, R.L.

    1982-01-01

    The fundamentals of organizational structure and administration as applied to the goal of keeping occupational radiation exposures as low as reasonably achievable are discussed, including consideration of management commitment, organizational separation of health physics functions, reporting levels, designation of responsibility and authority and adequacy of personnel and funding. Examples of good and poor organizational structures are shown, and the role and implementation of ALARA committees, effective communications, and review and audit processes are discussed. (author)

  11. ALARA Review of the SHAARS Operation

    International Nuclear Information System (INIS)

    Kekana, R.M.T.

    2010-01-01

    The SHARS mobile hot cell was designed and manufactured by Necsa intended to address the problem of disused Spent High Activity Radioactive Sources (SHARS) from teletherapy units, gamma irradiators and brachytherapy units. This unit is to be used in countries with no remote infrastructure to handle SHARS. The hot cell was designed for a 3.7E+13Bq (1000Ci) activity although it was demonstrated that it can handle even more than 7.4E+13Bq (2000Ci). The unit has a biological shield which consists of river sand sandwiched between metal plates and a viewing window filled with 50% zinc bromide solution. The unit was designed to provide sufficient shielding to ensure that doses are kept ALARA (As low As Reasonably Achieved). This paper compares the modelled dose rates with the actual measured doses during operations conducted in Sudan, Tanzania and Uruguay. It also presents the key lessons learned in the application of the ALARA principle during the SHARS missions. The new working practices and additional methods are proposed in order to reduce doses in accordance with the ALARA principle. (author)

  12. The Alara principle in backfitting Borssele

    International Nuclear Information System (INIS)

    Leurs, C.J.

    1998-01-01

    An extensive backfitting program, the Modifications Project, was carried out at the Borssele Nuclear Power Station. It involved sixteen modifications to technical systems. The scope of activities, and the dose rates encountered in places where work was to be performed, made it obvious from the outset that a high collective dose had to be anticipated. As a consequence, radiation protection within the project was organized in such a way that applicable radiation protection principles were applied in all phases of the project. From the point of view of radiation protection, the Modifications Project had to be subdivided into three phases, i.e., a conceptual design phase in which mainly the justification principle was applied; the engineering phase in which the Alara principle was employed; the execution phase in which management of the (internal) dose limits had to be observed in addition to the Alara principle. Throughout all project phases, radiation protection considerations and results were documented in so-called Alara reports and radiation protection checklists. As a result of the strictest possible observance of radiation protection principles in all phases of the project, a collective dose of 2505 mSv was achieved, which stands for a reduction by a factor of 4 compared to the very first estimate. In view of the scope and complex nature of the activities involved, and the radiation levels in the Borssele Nuclear Power Station, this is an excellent result. (orig.) [de

  13. ALARA application in Spanish NPP's. New approach

    International Nuclear Information System (INIS)

    O'Donnel, P.; Labarta, T.; Amor, I.

    1996-01-01

    One main objective of all nuclear installations is to underlie the principle of optimization. The focus in the application of this principle varies considerably, from cost-benefit techniques in the design phases to commitment, attitude and motivation in operation. The ALARA principle should permeate the entire organisation of the company during operation. Management should be the first link of a chain originating with explicit corporate commitment, leading to increasingly specific decisions, finally to reach those who are responsible for actual performance of each task. The safety culture is an element integrating the mentality that is to prevail throughout the organisation. The organisation shall contribute to incorporating the principle of optimization in all plant operations and all phases of activity. Management's commitment and motivation are transferred to all the workers and organisations involved. The ALARA commitment naturally extends to all outside organisations. The ultimate objective is to reduce collective doses through the promotion and enforcing of an ALARA culture and compliance with the operating collective dose objectives. (author)

  14. Optimization (ALARA) of radiation protection at Department of Energy facilities

    International Nuclear Information System (INIS)

    Weadock, A.A.; Jones, C.R.

    1992-01-01

    Maintaining worker and public exposures As Low As Reasonably Achievable (ALARA) is a key objective of the Department of Energy (DOE). Responsibility for occupational ALARA program policy and guidance resides within the DOE Office of Health. Current Office of Health initiatives related to ALARA include the development of additional regulatory guidance related to ALARA program implementation at DOE contractor facilities, the review of ALARA program status at various facilities and the production of technical reports summarizing this status, and the support of various mechanisms to improve communication among the DOE ALARA community. The Office of Health also monitors revisions to radiogenic risk estimates and radiation protection recommendations to evaluate adequacy of current DOE limits and impacts of potentially revised limits. (author)

  15. Hanford wells

    International Nuclear Information System (INIS)

    Chamness, M.A.; Merz, J.K.

    1993-08-01

    Records describing wells located on or near the Hanford Site have been maintained by Pacific Northwest Laboratory and the operating contractor, Westinghouse Hanford Company. In support of the Ground-Water Surveillance Project, portions of the data contained in these records have been compiled into the following report, which is intended to be used by those needing a condensed, tabular summary of well location and basic construction information. The wells listed in this report were constructed over a period of time spanning almost 70 years. Data included in this report were retrieved from the Hanford Envirorunental Information System (HEIS) database and supplemented with information not yet entered into HEIS. While considerable effort has been made to obtain the most accurate and complete tabulations possible of the Hanford Site wells, omissions and errors may exist. This document does not include data on lithologic logs, ground-water analyses, or specific well completion details

  16. Installation and routing of critical embedments at the Hanford Waste Vitrification Plant

    International Nuclear Information System (INIS)

    Van Katwijk, C.; Keenan, R.M.; Watts, C.

    1993-01-01

    The Hanford Waste Vitrification Plant (HWVP) is being designed by Fluor Daniel. Waste Chem Corporation is providing specialized expertise as Fluor Daniel's major subcontractor for vitrification and remote systems technologies. Westinghouse Hanford Company (Westinghouse Hanford) is the Project Integration manager and Business manager, and as the plant operator it provides technical direction to the Architect/Engineer team and constructor on behalf of the US Department of Energy, Richland Field Office. The Hot Cell portion of HWVP Vitrification Building contains very congested piping systems in the walls that penetrate in to the cells to nozzles for remote piping jumper assemblies. These nozzles require very tight tolerances to ensure a leak-tight fit to the jumpers. An approach has been developed that minimizes the time and expense of installing these nozzles in the wall to tight construction tolerances. This approach is called the Ganged Embed Plate (GEP) design

  17. Tolerancing requirements for remote handling at the Hanford Waste Vitrification Plant

    International Nuclear Information System (INIS)

    Van Katwijk, C.; Keenan, R.M.; Bullis, R.E.

    1993-01-01

    The Hanford Waste Vitrification Plant (HWVP) is being designed by Fluor Daniel, Inc. with Waste Chem Corporation as Fluor Daniel, Inc.'s major subcontractor specializing in vitrification and remote system technologies. United Engineers and Constructors (UE ampersand C)/Catalytic (UCAT) will construct the plant. Westinghouse Hanford Company is the Project Integration manager and Business manager, and as the plant operator it provides technical direction to the Architect/ Engineer team (A/E) and constructor on behalf of the US Department of Energy - Richland Field Office. The A/E has developed, in cooperation with UE ampersand C, Westinghouse Hanford Company, and the US Department of Energy, a new and innovative approach to installations of the many remote nozzles and electrical connectors that must be installed to demanding tolerances. This paper summarizes the key elements of the HWVP approach

  18. Proceedings of the Department of Energy ALARA Workshop

    International Nuclear Information System (INIS)

    Dionne, B.J.; Baum, J.W.

    1992-01-01

    The report contains summaries of papers, discussions, and operational exercises presented at the first Department of Energy ALARA Workshop held at Brookhaven National Laboratory, Upton, New York on April 21--22, 1992. The purpose of this workshop was to provide a forum for, and enhance communication among, ALARA personnel, as well as to inform DOE's field office and contractor personnel about the Office of Health's programs and expectations from the entire DOE complex efforts in the ALARA area.The two-day workshop consisted of one day dedicated to presentations on implementing various elements of a formal ALARA program at the DOE contractors' facilities, regulatory aspects of ALARA programs, and DOE Headquarters' ALARA expectations/initiatives. The second day was devoted to detailed discussions on ALARA improvements and problems, and operational exercises on cost-benefit analyses and on ALARA job/experiment reviews. At this workshop, 70 health physicists and radiation safety engineers from 5 DOE Headquarter Offices, 7 DOE operations/area offices, and 27 contractor facilities exchanged information, which is expected to stimulate further improvement in the DOE contractors' ALARA programs. Individual papers are indexed separately

  19. Proceedings of the Department of Energy ALARA Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Baum, J.W. [comps.

    1992-12-31

    The report contains summaries of papers, discussions, and operational exercises presented at the first Department of Energy ALARA Workshop held at Brookhaven National Laboratory, Upton, New York on April 21--22, 1992. The purpose of this workshop was to provide a forum for, and enhance communication among, ALARA personnel, as well as to inform DOE`s field office and contractor personnel about the Office of Health`s programs and expectations from the entire DOE complex efforts in the ALARA area.The two-day workshop consisted of one day dedicated to presentations on implementing various elements of a formal ALARA program at the DOE contractors` facilities, regulatory aspects of ALARA programs, and DOE Headquarters` ALARA expectations/initiatives. The second day was devoted to detailed discussions on ALARA improvements and problems, and operational exercises on cost-benefit analyses and on ALARA job/experiment reviews. At this workshop, 70 health physicists and radiation safety engineers from 5 DOE Headquarter Offices, 7 DOE operations/area offices, and 27 contractor facilities exchanged information, which is expected to stimulate further improvement in the DOE contractors` ALARA programs. Individual papers are indexed separately.

  20. Proceedings of the Department of Energy ALARA Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Baum, J.W. (comps.)

    1992-01-01

    The report contains summaries of papers, discussions, and operational exercises presented at the first Department of Energy ALARA Workshop held at Brookhaven National Laboratory, Upton, New York on April 21--22, 1992. The purpose of this workshop was to provide a forum for, and enhance communication among, ALARA personnel, as well as to inform DOE's field office and contractor personnel about the Office of Health's programs and expectations from the entire DOE complex efforts in the ALARA area.The two-day workshop consisted of one day dedicated to presentations on implementing various elements of a formal ALARA program at the DOE contractors' facilities, regulatory aspects of ALARA programs, and DOE Headquarters' ALARA expectations/initiatives. The second day was devoted to detailed discussions on ALARA improvements and problems, and operational exercises on cost-benefit analyses and on ALARA job/experiment reviews. At this workshop, 70 health physicists and radiation safety engineers from 5 DOE Headquarter Offices, 7 DOE operations/area offices, and 27 contractor facilities exchanged information, which is expected to stimulate further improvement in the DOE contractors' ALARA programs. Individual papers are indexed separately.

  1. Hanford Site Performance Report - March 1999

    International Nuclear Information System (INIS)

    EDER, D.M.

    2001-01-01

    The purpose of the Hanford Site Performance Report is to provide the Department of Energy Richland Operations Office's (DOE-RL's) report of Hanford's performance by: U.S. Department of Energy, Richland Operations Office, Project Hanford Management Contract (PHMC) through Fluor Daniel Hanford, Inc. (FDH) and its subcontractors, Environmental Restoration Contract through Bechtel Hanford, Inc. (BHI), and its subcontractors, and Pacific Northwest National Laboratories (PNNL) for Science and Technology (S and T) Mission and support to the Environmental Management (EM). This report is published monthly with the intent of relating work performance and progress in the context of the Success Indicators and Critical Success Factors as outlined in the Hanford Strategic Plan. On a quarterly basis, the report also addresses performance and progress related to the Science and Technology Mission's Critical Outcomes as derived from the Hanford Strategic Plan. Section A of this report is the Executive Summary, encapsulating high-level data in this report into an overall brief. Summary information provided includes Notable Accomplishments, a performance profile with associated analyses, Critical Issues, Key Integration Activities, and a ''quick list'' of Upcoming Key Events. Section B of this report, the Site Summary section, provides Environmental Management performance data specifically organized to the pertinent Critical Success Factors and Success Indicators, and Science and Technology data in the context of the Critical Outcomes. The Site Summary demonstrates the various missions' overall progress against these strategic objectives. The information is presented in both narrative and graphical formats. The remaining sections provide performance data relative to each individual mission area (e.g., Waste Management, Spent Nuclear Fuels, etc.). The information provided in the Mission Area sections is at a level of greater detail than is presented in either the Executive Summary or

  2. Hanford Site Performance Report - May 1999

    International Nuclear Information System (INIS)

    EDER, D.M.

    2001-01-01

    The purpose of the Hanford Site Performance Report is to provide the Department of Energy Richland Operations Office's (DOE-RL's) report of Hanford's performance by: U. S. Department of Energy, Richland Operations Office, Project Hanford Management Contract (PHMC) through Fluor Daniel Hanford, Inc. (FDH) and its subcontractors, Environmental Restoration Contract through Bechtel Hanford, Inc. (BHI), and its subcontractors, and Pacific Northwest National Laboratories (PNNL) for Science and Technology (S and T) Mission and support to the Environmental Management (EM). This report is published monthly with the intent of relating work performance and progress in the context of the Success Indicators and Critical Success Factors as outlined in the Hanford Strategic Plan. On a quarterly basis, the report also addresses performance and progress related to the Science and Technology Mission's Critical Outcomes as derived from the Hanford Strategic Plan. Section A of this report is the Executive Summary, encapsulating high-level data in this report into an overall brief. Summary information provided includes Notable Accomplishments, a performance profile with associated analyses, Critical Issues, Key Integration Activities, and a ''quick list'' of Upcoming Key Events. Section B of this report, the Site Summary section, provides Environmental Management performance data specifically organized to the pertinent Critical Success Factors and Success Indicators, and Science and Technology data in the context of the Critical Outcomes. The Site Summary demonstrates the various missions' overall progress against these strategic objectives. The information is presented in both narrative and graphical formats. The remaining sections provide performance data relative to each individual mission area (e.g., Waste Management, Spent Nuclear Fuels, etc.). The information provided in the Mission Area sections is at a level of greater detail than is presented in either the Executive Summary or

  3. Hanford Site Performance Report - April 1999

    International Nuclear Information System (INIS)

    EDER, D.M.

    2001-01-01

    The purpose of the Hanford Site Performance Report is to provide the Department of Energy Richland Operations Office's (DOE-RL's) report of Hanford's performance by: U.S. Department of Energy, Richland Operations Office, Project Hanford Management Contract (PHMC) through Fluor Daniel Hanford, Inc. (FDH) and its subcontractors, Environmental Restoration Contract through Bechtel Hanford, Inc. (BHI), and its subcontractors, and Pacific Northwest National Laboratories (PNNL) for Science and Technology (S and T) Mission and support to the Environmental Management (EM). This report is published monthly with the intent of relating work performance and progress in the context of the Success Indicators and Critical Success Factors as outlined in the Hanford Strategic Plan. On a quarterly basis, the report also addresses performance and progress related to the Science and Technology Mission's Critical Outcomes as derived from the Hanford Strategic Plan. Section A of this report is the Executive Summary, encapsulating high-level data in this report into an overall brief. Summary information provided includes Notable Accomplishments, a performance profile with associated analyses, Critical Issues, Key Integration Activities, and a ''quick list'' of Upcoming Key Events. Section B of this report, the Site Summary section, provides Environmental Management performance data specifically organized to the pertinent Critical Success Factors and Success Indicators, and Science and Technology data in the context of the Critical Outcomes. The Site Summary demonstrates the various missions' overall progress against these strategic objectives. The information is presented in both narrative and graphical formats. The remaining sections provide performance data relative to each individual mission area (e.g., Waste Management, Spent Nuclear Fuels, etc.). The information provided in the Mission Area sections is at a level of greater detail than is presented in either the Executive Summary or

  4. 1991 implementation of As Low As Reasonably Achievable (ALARA) administrative radiation exposure levels: Experiences and lessons learned

    International Nuclear Information System (INIS)

    Aldridge, T.L.; Baumann, B.L.

    1993-06-01

    As Low As Reasonably Achievable (ALARA) radiation exposure levels were implemented on January 1, 1991, by Westinghouse Hanford Company (WHC), a prime US Department of Energy (DOE) contractor, located in Richland, Washington. This paper describes the radiation exposure levels which were implemented and the associated experiences and lessons learned. The issue of a report from the Committee on Biological Effectiveness of Ionizing Radiation in 1989 prompted DOE to re-evaluate its position on radiation exposure limits and the resulting doses received by occupational radiation workers. DOE requested that all it's contractors determine the impacts to operations from reduced radiation exposure levels

  5. PROTECTING GROUNDWATER & THE COLUMBIA RIVER AT THE HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    GERBER, M.S.

    2006-06-29

    Along the remote shores of the Columbia River in southeast Washington state, a race is on. Fluor Hanford, a prime cleanup contractor to the U.S. Department of Energy (DOE) at the Hanford Site, is managing a massive, multi-faceted project to remove contaminants from the groundwater before they can reach the Columbia. Despite the daunting nature and size of the problem--about 80 square miles of aquifer under the site contains long-lived radionuclides and hazardous chemicals--significant progress is being made. Many groups are watching, speaking out, and helping. A large. passionate, diverse, and geographically dispersed community is united in its desire to protect the Columbia River--the eighth largest in the world--and have a voice in Hanford's future. Fluor Hanford and the DOE, along with the US. Environmental Protection Agency (EPA) and the Washington Department of Ecology (Ecology) interact with all the stakeholders to make the best decisions. Together, they have made some remarkable strides in the battle against groundwater contamination under the site.

  6. Reengineering and health physics within the project Hanford management contract

    International Nuclear Information System (INIS)

    Atencio, E.M.

    1997-01-01

    The impending transition of the Hartford Site management and operations (M ampersand O) contract to a management and integrating (M ampersand I) contract format, together with weak radiological performance assessments by external organizations and reduced financial budgets prompted the 're-engineering' of the previous Hanford prime contractor Radiological Control (Rad Con) organization. This paper presents the methodology, identified areas of improvements, and results of the re-engineering process. The conversion from the M ampersand O to the M ampersand I contract concept resulted in multiple independent Rad Con organizations reporting to separate major contractors who are managed by an integrating contractor. This brought significant challenges when establishing minimum site standards for sitewide consistency, developing roles and responsibilities, and maintaining site Rad Con goals. Championed by the previous contractor's Rad Con Director, Denny Newland, a five month planning effort was executed to address the challenges of the M ampersand I and to address identified weaknesses. Fluor Daniel Hanford assumed the responsibility as integrator of the Project Hanford Management Contract on October 1, 1996. The Fluor Daniel Hanford Radiation Protection Director Jeff Foster presents the results of the re-engineering effort, including the significant cost savings, process improvements, field support improvements, and clarification of roles and responsibilities that have been achieved

  7. ALARA engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

    International Nuclear Information System (INIS)

    Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

    1991-05-01

    Promoting the exchange of information related to implementation of the As Low As Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report, prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health, is the second in a series of bibliographies on dose reduction at DOE facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose reduction activities, with a specific focus towards DOE facilities. Facility types and activities covered in the scope of this report include: radioactive waste; uranium enrichment; fuel fabrication, storage, and reprocessing; facility decommissioning; hot laboratories; tritium production; research, test and production reactors; weapons fabrication and testing; and accelerators. Material on improved shielding design, decontamination, containments, robotics, job planning, improved operational techniques, and other topics has also been included. This volume (Volume 2 of the series) contains 127 abstracts numbered from 69 through 195, as well as author and subject indices. The subject index contains the abstract numbers from both the previous volume and the current volume, the latter being indicated in boldface. Information that the reader feels should be included in the next volume of this bibliography should be submitted to the BNL ALARA Center

  8. ALARA engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

    International Nuclear Information System (INIS)

    Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

    1991-03-01

    This report is the second in the series of bibliographies supporting the efforts at the Brookhaven National Laboratory ALARA Center on dose reduction at US Department of Energy (DOE) facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the US Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE's Office of Environment, Safety and Health to include DOE nuclear facilities. Abstracts for this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy Data Base, and reprints of published articles provided by the authors. Information that the reader feels should be included in the next volume of this bibliography may be submitted to the BNL ALARA Center. These abstracts, which have a bearing on dose reduction, consolidates information from publications pertinent to Radiological Engineers and Operational Health Physicists. Volume 2 contains 127 abstracts numbered from 69 through 195 as well as author and subject indices. The subject index contains the abstract numbers from both the previous volume and the current volume, the latter being indicated in boldface

  9. ALARA at Tyco Health care-Mallinckrodt

    International Nuclear Information System (INIS)

    Rijpkema, J.

    2002-01-01

    How to approach the ALARA requirement? That was one of the question in the beginning of the 1990's at the Mallinckrodt site for the preparation of radiopharmaceuticals. This question was raised after the ICRP published their guidelines in the ICRP 60 publication, with the average effective dose limit that was changed from 50 to 20 mSv per year. In the early 1990's the individual effective dose at Mallinckrodt was up to 20 mSv7year and some of the people over this number. As a first result of the discussion Mallinckrodt adopted the 20 mSv/year as being the legal limit, although it finally took over a decade to incorporate this ICRP limit into legislation. A second action was to introduce a site internal limit: if a person would exceed 75% of the legal limit, the person would be restrained from radiation work. This restriction forced everybody to look for solutions to decrease dose and area dose rate. This was the beginning and resulted in nobody exceeding 15 mSv/year after a couple of years and a lower average dose than before, with no extra employees. The second stage in the process of ALARA was a systematic approach of the decrease in personal dose. This systematic approach consists of three phases. The first phase is dose assessment followed by routine measurements. The third phase is the ALARA step. First phase, dose assessment. Normally this could be done in a meeting or even behind the desk: assess the dose per department or per group or per activity. Make a decision on which party will get high priority, medium priority and low priority. Normally this means that the department with the highest dose will get the highest priority. (Author)

  10. Hanford spent nuclear fuel project update

    Energy Technology Data Exchange (ETDEWEB)

    Williams, N.H.

    1997-08-19

    Twenty one hundred metric tons of spent nuclear fuel (SNF) are currently stored in the Hanford Site K Basins near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported to the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building.

  11. Alara applied to iter design and operation

    International Nuclear Information System (INIS)

    Uzan-Elbez, Joelle; Rodriguez-Rodrigo, Lina; Porfiri, Maria Teresa; Taylor, Neil; Gordon, Charles; Garin, Pascal; Girard, Jean-Philippe

    2005-01-01

    Based on the existing data on ITER and the safety options for licensing ITER in Cadarache, the present work assesses the application of the as-low-as-reasonably-achievable (ALARA) principle, as it has been implemented in the design of ITER and will be applied during ITER operation, as well as the compliance of the design with EUR/96-29 directive and regulation applicable in France. The preliminary occupational radiation exposure estimate gives a value of about 250 man mSv/a, which is half the annual target for ITER and comes essentially from maintenance activities. Some examples of the approach are presented

  12. Strengthening ALARA approach in work management at Krsko NPP

    International Nuclear Information System (INIS)

    Breznik, B.; Kovac, Z.; Sirola, P.

    1999-01-01

    As Low As Reasonably Achievable (ALARA) occupational exposures at nuclear power plants should be included in work management as a concept. There are world-wide trends required by the utilities for improved design, operation and maintenance. Within the period of seventeen years of plant operation maintaining low radiation exposures requires additional efforts. The benefit of this effort should be reducing risks to nuclear workers, better work planning and performance. The Krsko Plant ALARA organisations has been revised recently and built on different levels of the hierarchy. The goal is to promote good industry practice and the management of work on primary systems. The established ALARA programme describes the objectives and defines the procedures and tools for its implementation. Brief presentation of the programme as well as organisational responsibilities of dedicated ALARA committee and working groups is the scope of this paper. The management tools and ALARA indicators are discussed to implement the programme and to evaluate the results.(author)

  13. ALARA and an integrated approach to radiation protection

    International Nuclear Information System (INIS)

    Hendee, W.R.; Edwards, F.M.

    1986-01-01

    Exposures of individuals to ionizing radiation have been restricted for many years by a number of guidelines and rules developed by various advisory and regulatory groups. Accompanying these restrictions has been an evolving principle that exposures to individuals and groups should be kept as low as reasonably achievable (ALARA), consistent with provision of the benefits of radiation use to society. Although the ALARA concept is a laudable goal in principle, its implementation in a clinical facility has not been a straightforward process. Problems of implementing ALARA have been confounded further by the efforts of regulatory agencies to incorporate the ALARA concept into regulations governing radiation exposures. To facilitate the implementation of ALARA as a workable construct in a clinical facility, guidelines are needed for its application to both individual and collective exposures to radiation. The provision of such guidelines, including action and inaction levels for both individual and collective exposures, are presented here

  14. Hanford Site performance report - December 1998

    International Nuclear Information System (INIS)

    EDER, D.M.

    2001-01-01

    The purpose of the Hanford Site Performance Report is to provide the Department of Energy Richland Operations Office's (DOE-RL's) report of Hanford's performance by: U. S. Department of Energy, Richland Operations Office, Project Hanford Management Contract (PHMC) through Fluor Daniel Hanford, Inc. (FDH) and its subcontractors, Environmental Restoration Contract through Bechtel Hanford, Inc. (BHI), and its subcontractors, and Pacific Northwest National Laboratories (PNNL) for Science and Technology support to the Environmental Management (EM) mission. This report is published monthly with the intent of relating work performance and progress in the context of the Success Indicators and Critical Success Factors as outlined in the Hanford Strategic Plan. Currently, the report focuses on the EM mission, and will be expanded in the future to include non-EM activities. Section A of this report is the Executive Summary, encapsulating high-level data in this report into an overall brief. Summary information provided includes Notable Accomplishments, a tabular performance profile with associated analyses, Critical Issues, Key Integration Activities, a look at Significant Trends, and a ''quick list'' of Upcoming Key Events. Section B of this report, the Site Summary section, provides Environmental Management performance data specifically organized to the pertinent Critical Success Factors and Success Indicators. The Site Summary is a compilation of performance data from all of the Mission Areas and the Projects that comprise these Mission Areas; the information is presented in both narrative and graphical formats. The remaining sections provide performance data relative to each individual mission area (e.g., Waste Management, Spent Nuclear Fuels, etc.). The information provided in the Mission Area sections is at a level of greater detail than is presented in either the Executive Summary or the Site Summary sections. At the end of this report, a glossary of terms is provided

  15. FINAL FRONTIER AT HANFORD TACKLING THE CENTRAL PLATEAU

    International Nuclear Information System (INIS)

    GERBER MS

    2008-01-01

    The large land area in the center of the vast Department of Energy (DOE) Hanford Site in southeast Washington State is known as 'the plateau'--aptly named because its surface elevations are 250-300 feet above the groundwater table. By contrast, areas on the 585-square mile Site that border the Columbia River sit just 30-80 feet above the water table. The Central Plateau, which covers an ellipse of approximately 70 square miles, contains Hanford's radiochemical reprocessing areas--the 200 East and 200 West Areas--and includes the most highly radioactive waste and contaminated facilities on the Site. Five 'canyons' where chemical processes were used to separate out plutonium (Pu), 884 identified soil waste sites (including approximately 50 miles of solid waste burial trenches), more than 900 structures, and all of Hanford's liquid waste storage tanks reside in the Central Plateau. (Notes: Canyons is a nickname given by Hanford workers to the chemical reprocessing facilities. The 177, underground waste tanks at Hanford comprise a separate work scope and are not under Fluor's management). Fluor Hanford, a DOE prime cleanup contractor at the Site for the past 12 years, has moved aggressively to investigate Central Plateau waste sites in the last few years, digging more than 500 boreholes, test pits, direct soil 'pushes' or drive points; logging geophysical data sets; and performing electrical-resistivity scans (a non-intrusive technique that maps patterns of sub-surface soil conductivity). The goal is to identify areas of contamination areas in soil and solid waste sites, so that cost-effective and appropriate decisions on remediation can be made. In 2007, Fluor developed a new work plan for DOE that added 238 soil waste-site characterization activities in the Central Plateau during fiscal years (FYs) 2007-2010. This number represents a 50 percent increase over similar work previously done in central Hanford. Work Plans are among the required steps in the Comprehensive

  16. Application of the ALARA concept to the field situation

    International Nuclear Information System (INIS)

    Johnson, La Mar J.; Ahlquist, A. John

    1978-01-01

    It has been a long accepted practice in radiation protection that exposure to radiation should not only meet legal requirements but should be as far below these requirements as is reasonably achievable (ALARA). The ALARA concept is difficult to define, thus, there is a tendency by regulatory agencies (often at the request of the regulated) to attach a number to ALARA for environmental considerations. Presently, there are proposals to apply numbers to ALARA for soils contaminated by transuranics. Our actual field experience is determining ALARA for a large-scale land decontamination project suggests ALARA for contaminated soils cannot be determined on the basis of a single number. This paper will focus on the factors that were considered in determining the land had been decontaminated to ALARA. Details of the paper will include difficulties in determining contamination levels in the soil, dollar and man-power costs to remove contaminated soil, time constraints on the analytical procedures, safety considerations, depth of contamination versus costs to remove that contamination, disposal costs and considerations, and likelihood of additional undiscovered contamination. This experience suggests that numbers ought to be developed but should be used as goals or as a basis for decisions and not as blanket rules for all situations. (author)

  17. Towards the development of an ALARA culture

    International Nuclear Information System (INIS)

    Schieber, C.; Thezee, C.

    2000-01-01

    The ALARA principle, which states, for each exposure situation, that doses must be kept As Low As Reasonably Achievable, taking into account economic and social factors' represents the basis of the > developed to manage the radiological risk in a responsible manner. The practical implementation of the ALARA principle is complex. It requires defining transaction mechanisms which enable a responsible management of the radiological risk, taking into account, among other things, possible risk transfers in groups and the allocation of protection resources. The players who can take part in radiological risk management are numerous and have different functions: from the authorities to exposed workers, together with company managers. They all possess specific knowledge and have objectives which are not necessarily compatible. The transactions and negotiations initiated between these players during decision-taking relative to exposure management will therefore only be efficient and productive if there exists both a mutual comprehension of individual objectives and a readiness to collaborate on a common objective: keeping the residual risk at a level both acceptable to, and accepted by, the various parties involved. A fundamental element of this process therefore lies in the development among the various players concerned of a common culture with respect to radiological risks and the methods used for their management, in order to facilitate transactions by the sharing of a common language and system of values. A possible definition of > could be: >. Based on this statement, the paper presents, illustrated by the experience of the French Utility Electricite de France, the main components which should enter into consideration for the development of an ALARA culture for the management of occupational exposures. It concludes on the necessity to construct and transmit a common patrimony of a radiological risk management system comprising the scientific and technical knowledge

  18. Comments on two American justice decisions founded on ALARA

    International Nuclear Information System (INIS)

    Boehler, M.C.

    1996-01-01

    The role of the ALARA principle in the American justice is considered as a very important part of the law in evolution. The first decision called 'James decision' was the case of a worker who received a dose under the dose limit and was agreed in his demand. The second one,'Three Miles Island decision', was to refuse the ALARA principle as a norm because it would consider that the justice is more able to pilot a nuclear power plant than competent authorities. These two examples show that the ALARA principle must stay an operational guide and not a legal norm of precautions susceptible to impose sanctions by justice. (N.C.)

  19. Dose reduction and optimization studies (ALARA) at nuclear power facilities

    International Nuclear Information System (INIS)

    Baum, J.W.; Meinhold, C.B.

    1983-01-01

    Brookhaven National Laboratory (BNL) has been commissioned by the Nuclear Regulatory Commission (NRC) to study dose-reduction techniques and effectiveness of as low as reasonably achievable (ALARA) planning at LWR plants. These studies have the following objectives: identify high-dose maintenance tasks; identify dose-reduction techniques; examine incentives for dose reduction; evaluate cost-effectiveness and optimization of dose-reduction techniques; and compile an ALARA handbook on data, engineering modifications, cost-effectiveness calculations, and other information of interest to ALARA practioners

  20. Hanford recycling

    Energy Technology Data Exchange (ETDEWEB)

    Leonard, I.M.

    1996-09-01

    This paper is a study of the past and present recycling efforts on the Hanford site and options for future improvements in the recycling program. Until 1996, recycling goals were voluntarily set by the waste generators: this year, DOE has imposed goals for all its sites to accomplish by 1999. Hanford is presently meeting the voluntary site goals, but may not be able to meet all the new DOE goals without changes to the program. Most of these new DOE goals are recycling goals: * Reduce the generation of radioactive (low-level) waste from routine operations 50 percent through source reduction and recycling. * Reduce the generation of low-level mixed waste from routine operations 50 percent through source reduction and recycling. * Reduce the generation of hazardous waste from routine operations 50 percent through source reduction and recycling. * Recycle 33 percent of the sanitary waste from all operations. * Increase affirmative procurement of EPA-designated recycled items to 100 percent. The Hanford recycling program has made great strides-there has been a 98 percent increase in the amount of paper recycled since its inception in 1990. Hanford recycles paper, chemicals cardboard, tires, oil, batteries, rags, lead weights, fluorescent tubes, aerosol products, concrete, office furniture, computer software, drums, toner cartridges, and scrap metal. Many other items are recycled or reused by individual groups on a one time basis without a formal contract. Several contracts are closed-loop contracts which involve all parts of the recycle loop. Considerable savings are generated from recycling, and much more is possible with increased attention and improvements to this program. General methods for improving the recycling program to ensure that the new goals can be met are: a Contract and financial changes 0 Tracking database and methods improvements 0 Expanded recycling efforts. Specifically, the Hanford recycling program would be improved by: 0 Establishing one overall

  1. Electricite de France`s ALARA policy

    Energy Technology Data Exchange (ETDEWEB)

    Stricker, L. [EDF - DEPT, Paris la Defense (France); Rollin, P. [EDF Radioprotection Committee, Paris (France)

    1995-03-01

    In 1992, Electricite de France - EDF decided to improve the degree to which radiological protection is incorporated in overall management of the utility and set itself the objective of ensuring the same level of protection for workers from contractors as for those from EDF. This decision was taken in a context marked by a deterioration in exposure figures for French plants and by the new recommendations issued by the ICRP. This document describes the policy adopted by EDF at both corporate and plant level to meet these objectives, by: (1) setting up management systems which were responsive but not cumbersome; (2) a broad policy of motivation; (3) the development and use of suitable tools. The document then describes some quite positive results of EDF`s ALARA policy, giving concrete examples and analyzing the changes in global indicators.

  2. Procedure for preparation of 3-fluor-D-alanine, 2-deutero-3-fluor-D-alanine and 2,3,3-trideutero-3-fluor-D-alanine and their salts

    International Nuclear Information System (INIS)

    Kollonitsch, J.; Kahan, F.M.

    1971-01-01

    Procedures for the preparation of 3-fluor-D-alanine, 2-deutero-3-fluor-D-alanine and 2,3,3-trideutero-3-fluor-D-alanine, and salts of these compounds, are described. These new compounds are useful antibacterial substances not only applicable in the disinfection of pharmaceutical, dental and medical equipment, but also in the treatment of diseases caused by bacteria, and may be administered orally. While 3-fluor-L-alanine metabolises rapidly with toxic results, 3-fluor-D-alanine is much more slowly broken down in vivo and is not harmful in normal doses. Further it has been found that deuteration gives new deutero-analogues which are less subject to metabolic breaking down and still retain the antibacterial strength of the original compound. The in vivo activity is thereby increased and maintained. (JIW)

  3. Remote observations with FLUOR and the CHARA Array

    Science.gov (United States)

    Merand, Antoine; Birlan, Mirel; Lelu de Brach, Remi; Coudé du Foresto, Vincent

    2004-10-01

    Two years ago, the FLUOR interferometric beam combiner moved from IOTA (Infrared Optical Telescopes Array, Mount Hopkins, AZ) to the Center for High Angular Resolution Astronomy (CHARA) Array (Mount Wilson, CA). Apart from offering the largest baselines in the northern hemisphere, this array can be fully operated remotely to allow observations from a distant place. We present here the automations added to the FLUOR hardware, as well as software modifications made in order to allow us to observe from Paris Observatory. We required the remote service to be as reactive as local observations, implying frequent communications between the instrument and the remote observer. We took particular attention to the available bandwidth and reactivity imposed by the secured connection (Virtual Private Network). The first tests are presented.

  4. Action of fluor and its compounds on plants

    Energy Technology Data Exchange (ETDEWEB)

    Kluczynski, B

    1976-01-01

    This paper contains a brief synthesis of data available from the literature and experimental studies on the influence of fluor and its compounds on plants. The basic part of the paper consists of a list of 301 plants (separately for trees and shrubs and separately for other plants) the resistance of which to fluor compounds has been estimated. The information on resistance has been collected either from field observations or from cabin studies (artificial gassing of plants). The plants have been assigned to three classes: resistant, medium resistant and susceptible. When the resistance has been reported on a more detailed scale than a 3 point one, the data was compressed with some approximation to these three classes. In the list only plants are included with a definite specific or varietal name.

  5. The effects of NaF, Fluor-protector and Aminofluoride on the enamel of permanent teeth in children

    OpenAIRE

    Beloica, Dragan

    1984-01-01

    The effects of three fluor preparation (NaF, Fluor-Protector and Aminofluoride) on the enamel of permanent teeth has been studied by determinig the fluor concentrations in the enamel surface layer and the resistance of enamel to the effects of acids. The fluor preparations were applied to intact extracted teeth. Fluor concentrations were determined in the enamel samples using a Bedkman electrode with pH meter for fliuorides. Acid resistance was established by etching the enamnel samples, prev...

  6. Environmental ALARA Program at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G.T.

    1993-01-01

    The Savannah River Site (SRS) follows the ALARA (As Low As Reasonably Achievable) philosophy of keeping radiation doses to the general public as low as practical by minimizing radioactive releases to the environment. SRS accomplishes this goal by establishing challenging sitewide and area-specific Environmental ALARA Release Guides and trending radioactive releases against these guides on a monthly basis. The SRS Environmental ALARA Program, mandated by DOE Order 5400.5, is a dose-based program that has gone through many changes and improvements in recent years. A description of the SRS Environmental ALARA Program and its performance is presented in this paper. Recent SRS studies of the ''Zero Release'' option also are described

  7. Integration of Formal Job Hazard Analysis and ALARA Work Practice

    CERN Document Server

    Nelsen, D P

    2002-01-01

    ALARA work practices have traditionally centered on reducing radiological exposure and controlling contamination. As such, ALARA policies and procedures are not well suited to a wide range of chemical and human health issues. Assessing relative risk, identifying appropriate engineering/administrative controls and selecting proper Personal Protective Equipment (PPE) for non nuclear work activities extends beyond the limitations of traditional ALARA programs. Forging a comprehensive safety management program in today's (2002) work environment requires a disciplined dialog between health and safety professionals (e.g. safety, engineering, environmental, quality assurance, industrial hygiene, ALARA, etc.) and personnel working in the field. Integrating organizational priorities, maintaining effective pre-planning of work and supporting a team-based approach to safety management represents today's hallmark of safety excellence. Relying on the mandates of any single safety program does not provide industrial hygien...

  8. Dose reduction through an ALARA program at Almaraz NPP

    International Nuclear Information System (INIS)

    Leal, A.; Sustacha, D.; Aneiros, J.M.

    1987-01-01

    Radiation exposure is in keeping with the rate at which nuclear power production is increased. Therefore, it becomes more and more important that nuclear power producing plants develop an effective dose optimization and minimization [as-low-as-rasonably-achievable (ALARA)] program. Although radiation exposure suffered by the workers is carefully kept below administrative limits, there is a moral obligation to keep these exposures as low as possible. This requirement becomes apparent in the ALARA principle, supported and accepted by all countries with nuclear power plants in operation. Empresarios Agrupados (a Spanish architect engineer company) collaborates with nuclear power producing plants in an effort to maintain the collective ALARA doses through the efforts of a group of engineers specializing in dose minimization and optimization techniques. This group is organized as a radiation protection and maintenance team (ALARA team)

  9. Dose control and ALARA at nuclear power plants

    International Nuclear Information System (INIS)

    Xia Yihua; Li Xutong

    1999-01-01

    With the development of NPPs in China, paying attention to dose control and ALARA at NPPs is very important. The author briefly introduces two primary tasks for exposure control at NPPs, primary consideration of ALARA and the common technical methods. It points out that adoption of some quantitative indicators is useful, but it is important to bear it in mind that these ' values of dose avoided' are situation specific

  10. Air and smear sample calculational tool for Fluor Hanford Radiological control

    International Nuclear Information System (INIS)

    BAUMANN, B.L.

    2003-01-01

    A spreadsheet calculation tool was developed to automate the calculations performed for determining the concentration of airborne radioactivity and smear counting as outlined in HNF--13536, Section 5.2.7, ''Analyzing Air and Smear Samples''. This document reports on the design and testing of the calculation tool. Radiological Control Technicians (RCTs) will save time and reduce hand written and calculation errors by using an electronic form for documenting and calculating work place air samples. Current expectations are RCTs will perform an air sample and collect the filter or perform a smear for surface contamination. RCTs will then survey the filter for gross alpha and beta/gamma radioactivity and with the gross counts utilize either hand calculation method or a calculator to determine activity on the filter. The electronic form will allow the RCT with a few key strokes to document the individual's name, payroll, gross counts, instrument identifiers; produce an error free record. This productivity gain is realized by the enhanced ability to perform mathematical calculations electronically (reducing errors) and at the same time, documenting the air sample

  11. Fluor-Hanford 3013 Digital Radiography Dead Zone Mitigation Project Pressure Test Report

    International Nuclear Information System (INIS)

    Gibbs, K.

    2003-01-01

    The use of digital radiographic (DR) measurement of lid deflection as an indication of pressurization of the 3013 inner can was first reported by the Savannah River Technology Center (SRTC). The conclusions of this report were that for cans with relatively large initial concavity, lid deflection could be used to meet the 3013 standard (DOE-STD-3013-2000) requirement for a nondestructive indication of a pressurization of 100 psig. During acceptance testing of the system in the Spring of 2003, it was confirmed that for some cans the DR measured lid deflection could become insensitive to the change in lid deflection when compared to actual mechanical measurements. The basic explanation of this phenomenon is that characteristics of the lid geometry such as tilt and wobble can obfuscate the bottom of the lid where the deflection is measured. The purpose of this report is to document the results of the pressure testing and the efficacy of the alternate imaging and analysis methods developed to mitigate the dead zone problem. Prior to review of the results, a review of the current method and an introduction to the newly developed methods and techniques is provided

  12. Training survey -- educational profile for Hanford HANDI 2000 project

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, D.

    1998-08-25

    Fluor Daniel Hanford, Inc. (FDH) is currently adopting streamlined business processes through integrated software solutions. Replacing the legacy software (current/replacement systems, attached) also avoids significant maintenance required to resolve Year 2000 issues. This initiative is being referred to as `HANDI 2000`. The software being implemented in the first phase of this project includes Indus International`s PASSPORT Software, Peoplesoft and Primavera P3 Software. The project, which encompasses all the system replacements that will occur, has been named `HANDI 2000.` The PASSPORT applications being implemented are Inventory Management, Purchasing, Contract Management, Accounts Payable, and MSDS (Material Safety Data Sheets).

  13. Hanford Site near-facility environmental monitoring data report for calendar year 1998

    Energy Technology Data Exchange (ETDEWEB)

    DIEDIKER, L.P.

    1999-07-29

    This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.

  14. Hanford Site near-facility environmental monitoring data report for calendar year 1998

    International Nuclear Information System (INIS)

    DIEDIKER, L.P.

    1999-01-01

    This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years

  15. An evaluation of the management system verification pilot at Hanford

    International Nuclear Information System (INIS)

    Briggs, C.R.; Ramonas, L.; Westendorf, W.

    1998-01-01

    The Chemical Management System (CMS), currently under development at Hanford, was used as the ''test program'' for pilot testing the value added aspects of the Chemical Manufacturers Association's (CMA) Management Systems Verification (MSV) process. The MSV process, which was developed by CMA's member chemical companies specifically as a tool to assist in the continuous improvement of environment, safety and health (ESH) performance, represents a commercial sector ''best practice'' for evaluating ESH management systems. The primary purpose of Hanford's MSV Pilot was to evaluate the applicability and utility of the MSV process in the Department of Energy (DOE) environment. However, because the Integrated Safety Management System (ISMS) is the framework for ESH management at Hanford and at all DOE sites, the pilot specifically considered the MSV process in the context of a possible future adjunct to Integrated Safety Management System Verification (ISMSV) efforts at Hanford and elsewhere within the DOE complex. The pilot involved the conduct of two-hour interviews with four separate panels of individuals with functional responsibilities related to the CMS including the Department of Energy Richland Operations (DOE-RL), Fluor Daniel Hanford (FDH) and FDH's major subcontractors (MSCS). A semi-structured interview process was employed by the team of three ''verifiers'' who directed open-ended questions to the panels regarding the development, integration and effectiveness of management systems necessary to ensure the sustainability of the CMS effort. An ''MSV Pilot Effectiveness Survey'' also was completed by each panel participant immediately following the interview

  16. Plans and Progress on Hanford MLLW Treatment and Disposal

    International Nuclear Information System (INIS)

    McDonald, K. M.; Blackford, L. T.; Nester, D. E.; Connolly, R. R.; McKenney, D. E.; Moy, S. K.

    2003-01-01

    Mixed low-level waste (MLLW) contains both low-level radioactive materials and low-level hazardous chemicals. The hazardous component of mixed waste has characteristics identified by any or all of the following statutes: the Resource Conservation and Recovery Act of 1976 (RCRA), as amended; the Toxic Substances Control Act of 1976; and Washington State dangerous waste regulations. The Fluor Hanford Waste Management Project (WMP) is responsible for storing, treating, and disposing of solid MLLW, which includes organic and inorganic solids, organics and inorganic lab packs, debris, lead, mercury, long-length equipment, spent melters, and remote-handled (RH) and oversized MLLW. Hanford has 7,000 cubic meters, or about 25%, of the MLLW in storage at U.S. Department of Energy (DOE) sites. Hanford plans to receive 57,000 cubic meters from on-site generators, or about 50% of DOE's newly generated MLLW. In addition, the Hanford Environment Restoration Program and off-site generators having approved Federal Facility Consent Agreement site treatment plans will most likely send 200 cubic meters of waste to be treated and returned to the generators. Volumes of off-site waste receipts will be affected when the MLLW Record of Decision is issued as part of the process for the Hanford Site Solid Waste Environmental Impact Statement (EIS). The WMP objective relative to MLLW is to treat and dispose of ∼8000 cubic meters of existing inventory and newly-generated waste by September 30, 2006

  17. ALARA ASSESSMENT OF SETTLER SLUDGE SAMPLING METHODS

    International Nuclear Information System (INIS)

    Nelsen, L.A.

    2009-01-01

    The purpose of this assessment is to compare underwater and above water settler sludge sampling methods to determine if the added cost for underwater sampling for the sole purpose of worker dose reductions is justified. Initial planning for sludge sampling included container, settler and knock-out-pot (KOP) sampling. Due to the significantly higher dose consequence of KOP sludge, a decision was made to sample KOP underwater to achieve worker dose reductions. Additionally, initial plans were to utilize the underwater sampling apparatus for settler sludge. Since there are no longer plans to sample KOP sludge, the decision for underwater sampling for settler sludge needs to be revisited. The present sampling plan calls for spending an estimated $2,500,000 to design and construct a new underwater sampling system (per A21 C-PL-001 RevOE). This evaluation will compare and contrast the present method of above water sampling to the underwater method that is planned by the Sludge Treatment Project (STP) and determine if settler samples can be taken using the existing sampling cart (with potentially minor modifications) while maintaining doses to workers As Low As Reasonably Achievable (ALARA) and eliminate the need for costly redesigns, testing and personnel retraining

  18. ALARA ASSESSMENT OF SETTLER SLUDGE SAMPLING METHODS

    Energy Technology Data Exchange (ETDEWEB)

    NELSEN LA

    2009-01-30

    The purpose of this assessment is to compare underwater and above water settler sludge sampling methods to determine if the added cost for underwater sampling for the sole purpose of worker dose reductions is justified. Initial planning for sludge sampling included container, settler and knock-out-pot (KOP) sampling. Due to the significantly higher dose consequence of KOP sludge, a decision was made to sample KOP underwater to achieve worker dose reductions. Additionally, initial plans were to utilize the underwater sampling apparatus for settler sludge. Since there are no longer plans to sample KOP sludge, the decision for underwater sampling for settler sludge needs to be revisited. The present sampling plan calls for spending an estimated $2,500,000 to design and construct a new underwater sampling system (per A21 C-PL-001 RevOE). This evaluation will compare and contrast the present method of above water sampling to the underwater method that is planned by the Sludge Treatment Project (STP) and determine if settler samples can be taken using the existing sampling cart (with potentially minor modifications) while maintaining doses to workers As Low As Reasonably Achievable (ALARA) and eliminate the need for costly redesigns, testing and personnel retraining.

  19. Incremental ALARA cost/benefit computer analysis

    International Nuclear Information System (INIS)

    Hamby, P.

    1987-01-01

    Commonwealth Edison Company has developed and is testing an enhanced Fortran Computer Program to be used for cost/benefit analysis of Radiation Reduction Projects at its six nuclear power facilities and Corporate Technical Support Groups. This paper describes a Macro-Diven IBM Mainframe Program comprised of two different types of analyses-an Abbreviated Program with fixed costs and base values, and an extended Engineering Version for a detailed, more through and time-consuming approach. The extended engineering version breaks radiation exposure costs down into two components-Health-Related Costs and Replacement Labor Costs. According to user input, the program automatically adjust these two cost components and applies the derivation to company economic analyses such as replacement power costs, carrying charges, debt interest, and capital investment cost. The results from one of more program runs using different parameters may be compared in order to determine the most appropriate ALARA dose reduction technique. Benefits of this particular cost / benefit analysis technique includes flexibility to accommodate a wide range of user data and pre-job preparation, as well as the use of proven and standardized company economic equations

  20. ALARA beyond dollars per person-rem

    International Nuclear Information System (INIS)

    Waite, D.; Harper, W.

    1983-01-01

    The trend in radiological assessments over the past decade is to extract more and more information from each bit of data. In the 1960's it was sufficient to calculate doses to the maximum individual and populations from exposure to critical nuclides in critical pathways. The 1970's brought the UNSCEAR and BEIR Reports and made the extension of calculated doses to predicted health effects fashionable. The 1980's may see data analysis extended still further to the use of an index of lost productivity. Advantages of these types of uses of dose calculations include the derivation of further insight into the system being analyzed and the attainment of a greater measure of comparability with impacts from agents other than radiological. The question is, where does the uncertainty in the analytical result overwhelm any possibility of its usefulness. This presentation addresses this question in the context of a performance analysis of a high-level nuclear waste repository. Estimates of uncertainty in dose calculations, health effects predictions and loss of productivity predictions are derived from examination of the open literature and the use of propagation of uncertainty techniques. The expected values and uncertainties are compounded as they would be in an ALARA analysis and the outcomes are analyzed. The advantages and disadvantages of truncating the analysis at each stage of extension are discussed. 21 references, 3 tables

  1. Hanford Waste Vitrification Plant technical manual

    Energy Technology Data Exchange (ETDEWEB)

    Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

  2. Hanford Waste Vitrification Plant technical manual

    International Nuclear Information System (INIS)

    Larson, D.E.; Watrous, R.A.; Kruger, O.L.

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

  3. The European ALARA network. Development, functioning and main activities

    International Nuclear Information System (INIS)

    Schmitt-Hannig, A.

    2009-01-01

    The new ICRP recommendations (ICRP 103), and in particular the detailed treatment of optimisation in the ICRP Publication 101, define optimisation of protection as a source-related process aimed at keeping the likelihood of incurred exposures, the number of people exposed and the magnitude of their individual doses as low as reasonably achievable, also below constraints, taking into account economic and societal factors. Practical implementation and further development of the ALARA principle has been achieved for many years now by the successful cooperation of experts from different European organisations; first as pioneers by establishing the European ALARA Network and then by enthusiastically supporting the activities of the network itself. This contribution presents the evolution, operation and key activities of the European ALARA Network (EAN) in the last years; the successful cooperation of experts from different professional backgrounds, advocating the ALARA principle in a range of radiation protection areas, and contributing to its further development by trading experience and networking. The interaction between the EAN and international organisations, which support the ALARA principle by including relevant activities in their work programmes, is described. (orig.)

  4. Using Weibull Distribution Analysis to Evaluate ALARA Performance

    International Nuclear Information System (INIS)

    Frome, E.L.; Watkins, J.P.; Hagemeyer, D.A.

    2009-01-01

    As Low as Reasonably Achievable (ALARA) is the underlying principle for protecting nuclear workers from potential health outcomes related to occupational radiation exposure. Radiation protection performance is currently evaluated by measures such as collective dose and average measurable dose, which do not indicate ALARA performance. The purpose of this work is to show how statistical modeling of individual doses using the Weibull distribution can provide objective supplemental performance indicators for comparing ALARA implementation among sites and for insights into ALARA practices within a site. Maximum likelihood methods were employed to estimate the Weibull shape and scale parameters used for performance indicators. The shape parameter reflects the effectiveness of maximizing the number of workers receiving lower doses and is represented as the slope of the fitted line on a Weibull probability plot. Additional performance indicators derived from the model parameters include the 99th percentile and the exceedance fraction. When grouping sites by collective total effective dose equivalent (TEDE) and ranking by 99th percentile with confidence intervals, differences in performance among sites can be readily identified. Applying this methodology will enable more efficient and complete evaluation of the effectiveness of ALARA implementation.

  5. Computer code for quantitative ALARA evaluations

    International Nuclear Information System (INIS)

    Voilleque, P.G.

    1984-01-01

    A FORTRAN computer code has been developed to simplify the determination of whether dose reduction actions meet the as low as is reasonably achievable (ALARA) criterion. The calculations are based on the methodology developed for the Atomic Industrial Forum. The code is used for analyses of eight types of dose reduction actions, characterized as follows: reduce dose rate, reduce job frequency, reduce productive working time, reduce crew size, increase administrative dose limit for the task, and increase the workers' time utilization and dose utilization through (a) improved working conditions, (b) basic skill training, or (c) refresher training for special skills. For each type of action, two analysis modes are available. The first is a generic analysis in which the program computes potential benefits (in dollars) for a range of possible improvements, e.g., for a range of lower dose rates. Generic analyses are most useful in the planning stage and for evaluating the general feasibility of alternative approaches. The second is a specific analysis in which the potential annual benefits of a specific level of improvement and the annual implementation cost are compared. The potential benefits reflect savings in operational and societal costs that can be realized if occupational radiation doses are reduced. Because the potential benefits depend upon many variables which characterize the job, the workplace, and the workers, there is no unique relationship between the potential dollar savings and the dose savings. The computer code permits rapid quantitative analyses of alternatives and is a tool that supplements the health physicist's professional judgment. The program output provides a rational basis for decision-making and a record of the assumptions employed

  6. Experiences in ALARA application: 7th parade of maintenance

    International Nuclear Information System (INIS)

    Armenta R, M.S.

    1991-01-01

    The achieved experience with these activities, and all the carried out during the seventh stop but that they are not included here, carried to take a serie of decisions in the ALARA group, of which can be mentioned the following: 1. Definition of goals of collective dose and singular for works, to complete the ALARA commitment toward the occupational exposure personnel of the CLV. 2. To analyze the obtained information, as quick as possible, for using it in similar situations of work (to normalize the obtained results, when this is possible. 3. To coordinate the activities in those that participate different work groups with the end of not hindering the development of the same ones. 4. To establish ALARA responsibles of the works to fulfill functions of: pursuit of the work and information to the workers for their safety

  7. ANI/MAELU engineering inspection criteria 8.3 ALARA

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, L. [American Nuclear Insurers, West Hardford, CT (United States)

    1995-03-01

    The purpose of this criteria section is to provide guidelines for programs whose intent is to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA). The success that has been achieved by applying ALARA concepts at nuclear power plants is clearly illustrated by the major reductions in the annual cumulative dose to workers at many sites over the last few years. This success is the combined result of the general maturity of the nuclear industry, the intensive study of dose reduction practices by industry groups, and the successful sharing of experience and practices among plants. Source term reduction should be used as a primary ALARA mechanism. Methods which should be considered include: satellite and cobalt reduction, chemistry control, decontamination, submicron filters, zinc addition, hot spot reduction and permanent or temporary shielding.

  8. Report on the PWR-radiation protection/ALARA Committee

    Energy Technology Data Exchange (ETDEWEB)

    Malone, D.J. [Consumers Power Co., Covert, MI (United States)

    1995-03-01

    In 1992, representatives from several utilities with operational Pressurized Water Reactors (PWR) formed the PWR-Radiation Protection/ALARA Committee. The mission of the Committee is to facilitate open communications between member utilities relative to radiation protection and ALARA issues such that cost effective dose reduction and radiation protection measures may be instituted. While industry deregulation appears inevitable and inter-utility competition is on the rise, Committee members are fully committed to sharing both positive and negative experiences for the benefit of the health and safety of the radiation worker. Committee meetings provide current operational experiences through members providing Plant status reports, and information relative to programmatic improvements through member presentations and topic specific workshops. The most recent Committee workshop was facilitated to provide members with defined experiences that provide cost effective ALARA performance.

  9. Pacific Northwest Laboratory ALARA Report for Calendar Year 1993

    International Nuclear Information System (INIS)

    Keller, S.L.

    1994-07-01

    This report provides summary results of the Calendar Year (CY) 1993 As Low As Reasonably Achievable (ALARA) Program at the Pacific Northwest Laboratory (PNL). This report includes information regarding whole-body exposures to radiation, and skin contaminations. The collective whole-body radiation dose to employees during 1993 was 0.58 person-sievert (58 person-rem). This dose was 11 percent lower than the projected dose of 0.65 person-sievert (65 person-rem). The Radiation Protection Section's Field Dosimetry Services group projected that no PNL employee's dose would exceed 0.02 sievert (2 rem) based on dosimeters processed during the year; no worker actually exceeded the limit by the end of CY 1993. There were 15 reported cases of skin contamination for PNL employees during 1993. This number of 60 percent of the projected total of 25 cases. There were an additional 21 cases of personal-effects contamination to PNL staff: Nine of these contamination events occurred at the 324 Building, nine occurred at the 325 Building, one occurred in the 327 Building, one occurred in the 3720 Building, and one occurred in the 326 Building. Line management set numerous challenging and production ALARA goals for their facilities. Appendix A describes the final status of the 1993 ALARA goals. Appendix B describes the radiological ALARA goals for 1994. The Radiation Protection Section of the Laboratory Safety Dept. routinely perform audits of radiological ALARA requirements for specific facilities with significant potential for exposure. These ALARA audits are part of a comprehensive safety audit of the facility, designed to evaluate and improve total safety performance

  10. Fluorescence of Alexa fluor dye tracks protein folding.

    Directory of Open Access Journals (Sweden)

    Simon Lindhoud

    Full Text Available Fluorescence spectroscopy is an important tool for the characterization of protein folding. Often, a protein is labeled with appropriate fluorescent donor and acceptor probes and folding-induced changes in Förster Resonance Energy Transfer (FRET are monitored. However, conformational changes of the protein potentially affect fluorescence properties of both probes, thereby profoundly complicating interpretation of FRET data. In this study, we assess the effects protein folding has on fluorescence properties of Alexa Fluor 488 (A488, which is commonly used as FRET donor. Here, A488 is covalently attached to Cys69 of apoflavodoxin from Azotobacter vinelandii. Although coupling of A488 slightly destabilizes apoflavodoxin, the three-state folding of this protein, which involves a molten globule intermediate, is unaffected. Upon folding of apoflavodoxin, fluorescence emission intensity of A488 changes significantly. To illuminate the molecular sources of this alteration, we applied steady state and time-resolved fluorescence techniques. The results obtained show that tryptophans cause folding-induced changes in quenching of Alexa dye. Compared to unfolded protein, static quenching of A488 is increased in the molten globule. Upon populating the native state both static and dynamic quenching of A488 decrease considerably. We show that fluorescence quenching of Alexa Fluor dyes is a sensitive reporter of conformational changes during protein folding.

  11. Elements for designing ALARA programmes for the maintenance and routine operations of nuclear facilities

    International Nuclear Information System (INIS)

    Lefaure, C.; Croft, J.R.

    1991-01-01

    This article briefly reviews the three fundamental elements for designing ALARA programmes for the maintenance and routine operations of nuclear facilities. These are the need for commitment of all parties involved, the need for specific ALARA organizational structures and the systematic use of ALARA tools. (UK)

  12. Experiences in ALARA application: 7th parade of maintenance; Experiencias en la aplicacion del criterio ALARA: septima parada de mantenimiento

    Energy Technology Data Exchange (ETDEWEB)

    Armenta R, M S [Comision Federal de Electricidad, Central Laguna Verde, Veracruz (Mexico)

    1991-07-01

    The achieved experience with these activities, and all the carried out during the seventh stop but that they are not included here, carried to take a serie of decisions in the ALARA group, of which can be mentioned the following: 1. Definition of goals of collective dose and singular for works, to complete the ALARA commitment toward the occupational exposure personnel of the CLV. 2. To analyze the obtained information, as quick as possible, for using it in similar situations of work (to normalize the obtained results, when this is possible. 3. To coordinate the activities in those that participate different work groups with the end of not hindering the development of the same ones. 4. To establish ALARA responsibles of the works to fulfill functions of: pursuit of the work and information to the workers for their safety.

  13. Hanford K basins spent nuclear fuel project update

    International Nuclear Information System (INIS)

    Williams, N.H.; Hudson, F.G.

    1997-07-01

    Twenty one hundred metric tons of spent nuclear fuel (SNF) are currently stored in the Hanford Site K Basins near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported to the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building

  14. ALARA review for the 202-S plutonium loadout hood stabilization

    International Nuclear Information System (INIS)

    Patch, R.F.

    2000-01-01

    This as low as reasonably achievable (ALARA) review provides a description of the engineering and administrative controls used to manage personnel exposures, control contamination levels, and control airborne radioactivity concentrations while conducting stabilization of the Reduction-Oxidation (REDOX) Facility plutonium loadout hood and associated piping, and the isolation of the ER-8 ventilation system

  15. ALARA and radiation protection optimization status of Cernavoda NPP

    International Nuclear Information System (INIS)

    Hau, D.I.

    2001-01-01

    ALARA (As Low As Reasonably Achievable) in Radiation Protection is specifically applied as a tool in lowering the risk of exposure when performing necessary activities, leading to a reduction of individual and collective doses of workers as much and as reasonable possible. (authors)

  16. VISIPLAN 3D ALARA planning and communication tool

    International Nuclear Information System (INIS)

    Vermeersch, F.

    2006-01-01

    Human operations are required in nuclear installation, during maintenance, outage, repair and decommissioning. This leads to the exposure of the worker to radiation. It is clear that these operations must be performed according to the ALARA principle (to reduce the dose As Low As Reasonably Achievable). The person responsible for planning the job needs to evaluate different scenarios based on the exposure of the worker. This involves the manipulation of a lot of information specific to the work place such as the geometry, materials, radiological and technical boundary conditions to assess the dose. A lot of communication between the ALARA stakeholders is needed during this pre-job study. A communication that can be cumbersome and tedious when based on written documents and paper plans. The use of 3D calculation and simulation tools provide a solution to this problem. They provide an excellent means to make the above mentioned process more efficient and effective by calculating and visualising the environment and the associated radiological risk. The VISIPLAN 3D ALARA planning tool is developed and designed by SCK-CEN as a dose assessment tool enabling the user to calculate the dose in a 3D environment for work scenarios. This software is very successful in the ALARA field. At present 22 companies in Europe use the VISIPLAN software in the field of dose assessment in maintenance and decommissioning. Recent developments and applications are discussed

  17. Review of ALARA plan for activities at the 105 K-East fuel storage basin

    International Nuclear Information System (INIS)

    Vargo, G.J.; Durham, J.S.; Hickey, E.E.; Stansbury, P.S.; Cicotte, G.R.

    1994-09-01

    As part of its ongoing efforts to reduce doses to workers to levels as low as reasonably achievable (ALARA), Westinghouse Hanford Company (WHC) tasked the Health Protection Department of the Pacific Northwest Laboratory (PNL) to review operations at the 105 K-East Fuel Storage Basin (105 K-East). This review included both routine operations and a proposed campaign to encapsulate N-Reactor fuel stored there. This report summarizes the results of PNL's reviews of policy, procedures, and practices for operations at 105 K-East as well as an evaluation of the major sources of occupational radiation exposures. Where possible, data previously collected by WHC and its predecessors were used. In addition, PNL staff developed a three-dimensional model of the radiological environment within 105 K-East to assess the relative contributions of different radiation sources to worker dose and to provide a decision tool for use in evaluating alternative methods of dose rate reduction. The model developed by PNL indicates that for most areas in the basin the primary source of occupational radiation exposure is the contaminated concrete surfaces of the basin near the waterline. Basin cooling water piping represents a significant source in a number of areas, particularly the Technical Viewing Pit. This report contains specific recommendations to reduce the impact of these sources of occupational radiation exposure in 105 K-East. Other recommendations to reduce doses to workers during activities such as filter changes and filter sampling are also included

  18. Adsorption of volatile organic compounds by polytetra-fluor ethylene

    International Nuclear Information System (INIS)

    Martinet, J.M.

    1958-01-01

    The sorption of organic vapours by microporous polytetra-fluor ethylene has been studied gravimetrically using a Mc Bain-Baker type sorption balance. The amount of sorption, the peculiarities observed on the isotherm curves, the small influence of temperature, and smallness of hysteresis suggests that mainly physical adsorption occurs when the temperature is around 25 deg. C. The values of the surface areas obtained from the adsorption isotherms using organic vapours differ greatly from those derived from N 2 adsorption measurements. This discrepancy cannot be completely attributed to differences in the structure and chemical function of the adsorbate molecules, or to the porous structure of the adsorbent. On the contrary, the surface area values obtained by sorbing high volatile freons conform with those measured by nitrogen adsorption, which seems to imply a connection between the area of sorbed monolayers and volatility of the adsorbate. (author) [fr

  19. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

    1993-05-01

    The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides an existing and future land use plan for the Hanford Site. The HSDP is updated annually in accordance with DOE Order 4320.1B, Site Development Planning, to reflect the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

  20. HANFORD PLUTONIUM FINISHG PLAN (PFP) COMPLETES PLUTONIUM STABILIZATION KEY SAFETY ISSUES CLOSED

    International Nuclear Information System (INIS)

    GERBER, M.S.

    2004-01-01

    A long and intense effort to stabilize and repackage nearly 18 metric tons (MT) of plutonium-bearing leftovers from defense production and nuclear experiments concluded successfully in February, bringing universal congratulations to the Department of Energy's Hanford Site in southeast Washington State. The victorious stabilization and packaging endeavor at the Plutonium Finishing Plant (PFP), managed and operated by prime contractor Fluor Hanford, Inc., finished ahead of all milestones in Hanford's cleanup agreement with regulators, and before deadlines set by the Defense Nuclear Facilities Safety Board (DNFSB), a part of the federal Executive Branch that oversees special nuclear materials. The PFP stabilization and packaging project also completed under budget for its four-year tenure, and has been nominated for a DOE Secretarial Award. It won the Project of the Year Award in the local chapter competition of the Project Management Institute, and is being considered for awards at the regional and national level

  1. Hanford External Dosimetry Program

    International Nuclear Information System (INIS)

    Fix, J.J.

    1990-10-01

    This document describes the Hanford External Dosimetry Program as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy (DOE) and its Hanford contractors. Program services include administrating the Hanford personnel dosimeter processing program and ensuring that the related dosimeter data accurately reflect occupational dose received by Hanford personnel or visitors. Specific chapters of this report deal with the following subjects: personnel dosimetry organizations at Hanford and the associated DOE and contractor exposure guidelines; types, characteristics, and procurement of personnel dosimeters used at Hanford; personnel dosimeter identification, acceptance testing, accountability, and exchange; dosimeter processing and data recording practices; standard sources, calibration factors, and calibration processes (including algorithms) used for calibrating Hanford personnel dosimeters; system operating parameters required for assurance of dosimeter processing quality control; special dose evaluation methods applied for individuals under abnormal circumstances (i.e., lost results, etc.); and methods for evaluating personnel doses from nuclear accidents. 1 ref., 14 figs., 5 tabs

  2. Virtual radiation fields for ALARA determination

    International Nuclear Information System (INIS)

    Knight, T.W.

    1995-01-01

    As computing power has increased, so too has the ability to model and simulate complex systems and processes. In addition, virtual reality technology has made it possible to visualize and understand many complex scientific and engineering problems. For this reason, a virtual dosimetry program called Virtual Radiation Fields (VRF) is developed to model radiation dose rate and cumulative dose to a receptor operating in a virtual radiation environment. With the design and testing of many facilities and products taking place in the virtual world, this program facilitates the concurrent consideration of radiological concerns during the design process. Three-dimensional (3D) graphical presentation of the radiation environment is made possible through the use of IGRIP, a graphical modeling program developed by Deneb Robotics, Inc. The VRF simulation program was designed to model and display a virtual dosimeter. As a demonstration of the program's capability, the Hanford tank, C-106, was modeled to predict radiation doses to robotic equipment used to remove radioactive waste from the tank. To validate VRF dose predictions, comparison was made with reported values for tank C-106, which showed agreement to within 0.5%. Graphical information is presented regarding the 3D dose rate variation inside the tank. Cumulative dose predictions were made for the cleanup operations of tank C-106. A four-dimensional dose rate map generated by VRF was used to model the dose rate not only in 3D space but also as a function of the amount of waste remaining in the tank. This allowed VRF to predict dose rate at any stage in the waste removal process for an accurate simulation of the radiological conditions throughout the tank cleanup procedure

  3. Virtual radiation fields for ALARA determination

    Energy Technology Data Exchange (ETDEWEB)

    Knight, T.W.

    1995-12-31

    As computing power has increased, so too has the ability to model and simulate complex systems and processes. In addition, virtual reality technology has made it possible to visualize and understand many complex scientific and engineering problems. For this reason, a virtual dosimetry program called Virtual Radiation Fields (VRF) is developed to model radiation dose rate and cumulative dose to a receptor operating in a virtual radiation environment. With the design and testing of many facilities and products taking place in the virtual world, this program facilitates the concurrent consideration of radiological concerns during the design process. Three-dimensional (3D) graphical presentation of the radiation environment is made possible through the use of IGRIP, a graphical modeling program developed by Deneb Robotics, Inc. The VRF simulation program was designed to model and display a virtual dosimeter. As a demonstration of the program`s capability, the Hanford tank, C-106, was modeled to predict radiation doses to robotic equipment used to remove radioactive waste from the tank. To validate VRF dose predictions, comparison was made with reported values for tank C-106, which showed agreement to within 0.5%. Graphical information is presented regarding the 3D dose rate variation inside the tank. Cumulative dose predictions were made for the cleanup operations of tank C-106. A four-dimensional dose rate map generated by VRF was used to model the dose rate not only in 3D space but also as a function of the amount of waste remaining in the tank. This allowed VRF to predict dose rate at any stage in the waste removal process for an accurate simulation of the radiological conditions throughout the tank cleanup procedure.

  4. Relationship between salivary fluor concentration and caries index in 12–15 years old children

    Directory of Open Access Journals (Sweden)

    Vidyana Pratiwi

    2012-03-01

    Full Text Available Background: Dental caries is a bacterial infection leading to dissolution and localized damage of hard tissues. The assessment of caries risk is based on several caries indicators including clinical conditions (DMF-T index, environment (fluor, and general health. Purpose: The objective of this study was to assess the relationship between salivary fluor concentration and caries index in children aging 12–15 years old at SMP Negeri 2 PTPN VIII Pangalengan. Methods: This study is an observational analytical study using crosssectional approach and is conducted in a field trial manner. The study sample consists of 80 students in the age of 12 to 15 years old at SMP Negeri 2 PTPN VIII selected through Probability Sampling manner using simple random sampling method. Results: The result of this study shows a DMF-T index of 4.32 and salivary fluor concentration mean of 0.018. Pearson Product Moment correlation test shows that there is a weak correlation between salivary fluor concentration and DMF-T index. Conclusion: It is concluded that the salivary fluor concentration has an insignificant correlation with the DMF-T index since the fluor concentration in saliva is very low.Latar belakang: Karies gigi adalah penyakit infeksi bakteri yang berakibat pada disolusi dan kerusakan terlokalisasi jaringan keras. Penilaian risiko karies berdasarkan atas beberapa indikator karies yaitu kondisi klinis (indeks DMF-T, lingkungan (fluor, dan kesehatan umum. Tujuan: Penelitian ini bertujuan untuk mengetahui hubungan konsentrasi fluor yang terdapat dalam saliva dengan indeks karies pada anak usia 12-15 tahun di SMP Negeri 2 PTPN VIII Pangalengan. Metode: Jenis penelitian ini adalah penelitian analitik observasional dengan pendekatan cross sectional yang dilakukan di lapangan. Sampel penelitian sebanyak 80 orang siswasiswi usia 12–15 tahun di SMP Negeri 2 PTPN VIII Pangalengan yang dipilih secara Probability Sampling dengan metode simple random sampling. Hasil

  5. Results from the nuclear microprobe PIXE analysis of selected rare earth fluor compounds

    International Nuclear Information System (INIS)

    Hollerman, William A.; Gates, Earl; Boudreaux, Philip; Glass, Gary A.

    2002-01-01

    Most previous research measures fluorescence properties over the macroscopic regime. Properties of individual microscopic grains could be significantly different than those measured over the macroscopic scale. Until recently, it was difficult to measure properties of individual fluor grains. Existing characterization techniques like scanning electron microscopy are not practical, since the resulting fluorescence masks the electron surface profile. Starting in September 2000, a research program was initiated at the Acadiana Research Laboratory to determine microscopic fluorescence properties for selected inorganic rare earth compounds. The initial phase of this program utilized microscopic proton induced X-ray emission (μPIXE) to characterize the elemental composition of individual fluor grains. Results show that both individual grains and small clusters of grains could be seen using μPIXE. Maps of this type can be used to estimate grain dimensions for the selected rare earth fluor. This technique is a new and innovative method to characterize a fluor material

  6. ALARA tools and performance indicators at Cernavoda NPP

    International Nuclear Information System (INIS)

    Chitu, C.; Popescu, V.; Simionov, V.

    2009-01-01

    Work efficiency is an area of high concern to nuclear power plant operators. Job planning has to be done so that there will be enough time for ALARA actions to be implemented. The control of the activities involving radiological risk is part of ALARA Process. An effective control supposes the implementation of a process to systematically identify the activities performed in radiological areas. Plant Performance Indicators related to ionizing radiation exposure have been established to improve station safe performance. They are assessed and reported periodically to reflect the safe operation objectives. If target values are exceeded 'abnormal condition reports' are generated. Corrective and preventive actions aim at work planning, technical aspects, and human performance. All the staff is informed about these events and corrective actions described through the training program are implemented. (authors)

  7. Designing plants for ALARA-revelation or evolution

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The author traces the Duke Nuclear program from the late 1960s to today. He then looks at the future. The primary goal, he says, should be to continue to reduce individual exposure in order to reduce total station, industry exposure. In order to accomplish this goal in the design process, he recommends continued training of design personnel to reinforce the ALARA concepts and to provide new industry techniques and actual examples

  8. ALARA approach on Qinshan unit I lower internals recovery project

    International Nuclear Information System (INIS)

    Wu Meijing; Xu Hongming; Jiang Jianqi; Chen Zhongyu

    2000-01-01

    Qinshan unit-1 is a 300 Mwe prototype PWR. It has been successfully operating for 4 fuel cycles about 10 years. Some loose parts by the failure of the guide tube of the reactor core neutron flux measurement thimble were observed on the lower structure of Core Barrel during periodical inspection after unloading all fuel assemblies. Qinshan Nuclear Power Company selected Westinghouse Electric Company as contractor to perform the reactor core barrel recovery service after negotiated with 4 world big company. QNPC and Westinghouse worked together to approach the ALARA by increasing water shielding, adding additional steel shielding, fuel pool cleaning and using the long hand tools, remote camera system. The training, mock-up exercise, good personal behavior was greatly contributed to the ALARA approaching. The collective dose and personal exposure of this job were successful controlled by implementing the preset ALARA program. The job was done by the cost of 70 man.mSv collective dose and 3.5 mSv maximum personal exposure despite of the high dose-rate which hot spot in some place is up to several hundred Sv per hour. (author)

  9. The uniform application of ALARA to all radiation workers

    International Nuclear Information System (INIS)

    Pomroy, C.

    1988-05-01

    New information on the dosimetry and epidemiology of atomic bomb survivors suggests that risk estimates may have to be revised upwards. This has focussed increased attention on the ALARA principle. The ICRP believes that ALARA principle is the driving force in keeping average radiation doses low. In practice, the optimization process required for ALARA varies between different sectors of the nuclear industry. For instance, the power utilities have developed procedures for comparing different dose reduction options. Similarly, uranium mine operators have applied optimization techniques to questions concerning ventilation and shielding of ore trucks. Missing from this list however, is the use of a formal optimizing technique in medical and research uses of radioactivity or radiation. Nonetheless, average annual doses to these workers are quite low. An alternative approach to optimization calculation has been suggested, entailing the identification of sub-groups of workers with substantially higher doses to discover the reasons for the higher doses, and to develop means to reduce them to the overall average. Thus maintenance mechanics in nuclear reactors, by the very nature of their jobs, have more potential for higher dose. The utilities are developing procedures to reduce the maintenance mechanics' doses. If the same analysis is applied to medical workers, it is seen that isotope technicians and therapeutic radiology technicians have average doses well above the overall average. The feasibility of some form of optimization process for these categories of workers is discussed

  10. Effective use of metrics in an ALARA program

    International Nuclear Information System (INIS)

    Bates, B.B. Jr.

    1996-01-01

    ALARA radiological protection programs require metrics to meet their objectives. Sources of metrics include; external dosimetry; internal dosimetry; radiological occurrences from the occurrence reporting and processing system (ORPS); and radiological incident reports (RIR). The sources themselves contain an abundance of specific ''indicators''. To choose the site-specific indicators that will be tracked and trended requires careful review. This required the end users to expend valuable time and effort to locate the data they needed. To address this problem, a central metrics database has been developed so that customers can have all their questions addressed quickly and correctly. The database was developed in the beginning to answer some of the customer's most frequently asked questions. It is now also a tool to communicate the status of the radiation protection program to facility managers. Finally it also addresses requirements contained in the Rad Con manual and the 10CFR835 implementation guides. The database uses currently available, ''user friendly'', software and contains information from RIR's, ORPS, and external dosimetry records specific to ALARA performance indicators. The database is expandable to allow new metrics input. Specific reports have been developed to assist customers in their tracking and trending of ALARA metrics

  11. Improvement of ALARA in Taiwan Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kao, H. M.; Chang, M.

    2006-01-01

    Full text: Full text: The ALARA(as low as reasonable achievable ) principle is a basic spirit of radiation safety culture and the most important element of a successful radiation safety program. In recent years, the ALARA principle and practices have been widely applied to the three operating nuclear power plants in Taiwan. Through the effective communication and fully cooperation between the authority and utility, the performance goals of improving radiation safety program have been set, and the implementation plans have been proposed and followed. Taking Chinshan nuclear power station as an example, in 2004, the occupational individual dose was 1.13mSv/ person in average,no one exceeded 20mSv ,and the collective dose was 1.03man-Sv/unit which achieved the best record of BWR plant in Taiwan. The radiation reduction approaches and tools adopted by the plants include removing radiation sources, setting radiation shieding, optimizing and controlling the schedule of radiation practices, considering the occupancy factors, and better administrative management to keep exposure ALARA will be discussed in this paper

  12. The application of the ALARA principle: a first assessment

    International Nuclear Information System (INIS)

    Lochard, J.; Webb, G.A.M.

    1984-01-01

    What can we learn from practical ALARA studies. On the methodological point of view the different works developed these last years rely upon the two basic ICRP assumptions, i.e.: the linearity of the dose-risk relationship and the optimal resource allocation principle. Furthermore, most authors seem now to assume the multidimensionality of radiological protection problems. This leads to envisage for decision-aiding techniques the enlargement of the cost-benefit method. As for the quantification process of ALARA principle, assessment techniques for both protection costs and levels of exposures of the various groups at risk are well established. Some differences can be however pointed out between authors concerning the monetary valuation of the detriment cost as well as the way to cope with time, probabilistic events and ''other factors'' not directly linked to protection costs and radiological detriment. Further consideration must be given to the exact role ALARA studies have to play in the decision-making process concerning conception and operation of installations. Particular efforts have to be put on the development of adequate data bases and also decision-aiding techniques able to take into account the multidimensionnality of factors involved in practical protection [fr

  13. LANL Environmental ALARA Program Status Report for CY 2016

    Energy Technology Data Exchange (ETDEWEB)

    Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mcnaughton, Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-02-24

    Los Alamos National Laboratory (LANL) ensures that radiation exposures to members of the public and the environment from LANL operations, past and present, are below regulatory thresholds and are as low as reasonably achievable (ALARA) through compliance with DOE Order 458.1 Radiation Protection for the Public and the Environment, and LANL Policy 412 Environmental Radiation Protection (LANL2016a). In 2007, a finding (RL.2-F-1) and observation (RL.2-0-1) in the NNSA/ LASO report, September 2007, Release of Property (Land) Containing Residual Radioactive Material Self-Assessment Report, indicated that LANL had no policy or documented process in place for the release of property containing residual radioactive material. In response, LANL developed PD410, Los Alamos National Laboratory Environmental ALARA Program. The most recent version of this document became effective in 2014 (LANL 2014a). The document provides program authorities, responsibilities, descriptions, processes, and thresholds for conducting qualitative and quantitative ALARA analyses for prospective and actual radiation exposures to the public and t o the environment resulting from DOE activities conducted on the LANL site.

  14. Thermal expansion behavior of fluor-chlorapatite crystalline solutions

    Science.gov (United States)

    Hovis, G.; Harlov, D.; Gottschalk, M.; Hudacek, W.; Wildermuth, S.

    2009-04-01

    the fluor-chlorapatite series is little affected by composition. This contrasts with relationships in alkali feldspars (Hovis and coworkers, 1997, 1999), which show that K-rich feldspars expand less than Na-rich feldspars. It contrasts also with the behavior of additional AlSi3 feldspars (Hovis and others, 2008), in which room-temperature chemical expansion limits the degree to which the structure can expand thermally. It also differs from expansion in kalsilite crystalline solutions (Hovis and coworkers, 2003, 2006), which depends on K:Na ratio. Among the minerals we have studied previously, only nepheline displays expansion behavior similar to that of fluor-chlorapatite crystalline solutions in that thermal expansion shows little sensitivity to composition. In AlSi3 feldspars and kalsilite one observes a single crystallographically distinct alkali site and a dominating SiO4 tetrahedral framework that limits the vibrational characteristics of the alkali-site occupant(s). Fluor-chlorapatite crystalline solutions have no such structural framework. Moreover, the anion site in the latter changes structural character in the transition from fluorapatite to chlorapatite. This flexibility apparently allows anion vibrational characteristics, coupled with those of Ca polyhedral components, to change continuously and in a compensating manner across the series. The thermal expansion data also imply that volumes of F-Cl mixing in fluor-chlorapatite are constant from room temperature to 1000 °C. References: Cherniak, D.J. (2000) Rare earth element diffusion in apatite. Geochimica et Cosmochimica Acta 64, 3871-3885. Harlov, D.E. and Förster, H-J. (2002) High grade fluid metasomatism on both a local and regional Scale: the Seward Peninsula, Alaska and the Ivrea-Verbano Zone, Northern Italy Part II: phosphate mineral chemistry. Journal of Petrology 43, 801-824. Holland, T.J.B. and Redfern, S.A.T. (1997) Unit-cell refinement: Changing the dependent variable, and use of regression

  15. Project Hanford management contract quality improvement project management plan; TOPICAL

    International Nuclear Information System (INIS)

    ADAMS, D.E.

    1999-01-01

    On July 13, 1998, the U.S. Department of Energy, Richland Operations Office (DOE-RL) Manager transmitted a letter to Fluor Daniel Hanford, Inc. (FDH) describing several DOE-RL identified failed opportunities for FDH to improve the Quality Assurance (QA) Program and its implementation. In addition, DOE-RL identified specific Quality Program performance deficiencies. FDH was requested to establish a periodic reporting mechanism for the corrective action program. In a July 17, 1998 response to DOE-RL, FDH agreed with the DOE concerns and committed to perform a comprehensive review of the Project Hanford Management Contract (PHMC) QA Program during July and August, 1998. As a result, the Project Hanford Management Contract Quality Improvement Plan (QIP) (FDH-3508) was issued on October 21, 1998. The plan identified corrective actions based upon the results of an in-depth Quality Program Assessment. Immediately following the scheduled October 22, 1998, DOE Office of Enforcement and Investigation (EH-10) Enforcement Conference, FDH initiated efforts to effectively implement the QIP corrective actions. A Quality Improvement Project (QI Project) leadership team was assembled to prepare a Project Management Plan for this project. The management plan was specifically designed to engage a core team and the support of representatives from FDH and the major subcontractors (MSCs) to implement the QIP initiatives; identify, correct, and provide feedback as to the root cause for deficiency; and close out the corrective actions. The QI Project will manage and communicate progress of the process

  16. FY 2001 Hanford Waste Management Strategic Plan

    International Nuclear Information System (INIS)

    COLLINS, M.S.

    2001-01-01

    We are pleased to present the 2001 Hanford Waste Management Program Strategic Plan. This plan supports the newly developed U. S. Department of Energy Site outcomes strategy. The 2001 Plan reflects current and projected needs for Waste Management Program services in support of Hanford Site cleanup, and updates the objectives and actions using new waste stream oriented logic for the strategic goals: (1) waste treatment/processing, storage, and disposal; (2) interfaces; and (3) program excellence. Overall direction for the Program is provided by the Waste Management Division, Office of the Assistant Manager for Environmental Restoration and Waste Management, U. S. Department of Energy, Richland Operations Office. Fluor Hanford, Inc. is the operating contractor for the program. This Plan documents proactive strategies for planning and budgeting, with a major focus on helping meet regulatory commitments in a timely and efficient manner and concurrently assisting us in completing programs cheaper, better and quicker. Newly developed waste stream oriented logic was incorporated to clarify Site outcomes. External drivers, technology inputs, treatment/processing, storage and disposal strategies, and stream specific strategies are included for the six major waste types addressed in this Plan (low-level waste, mixed low-level waste, contact-handled transuranic waste, remote-handled transuranic waste, liquid waste, and cesium/strontium capsules). The key elements of the strategy are identification and quantification of the needs for waste management services, assessment of capabilities, and development of cost-effective actions to meet the needs and to continuously improve performance. Accomplishment of specific actions as set forth in the Plan depends on continued availability of the required resources and funding. The primary objectives of Plan are: (1) enhance the Waste Management Program to improve flexibility, become more holistic especially by implementing new

  17. Hanford site environment

    International Nuclear Information System (INIS)

    Isaacson, R.E.

    1976-01-01

    A synopsis is given of the detailed characterization of the existing environment at Hanford. The following aspects are covered: demography, land use, meteorology, geology, hydrology, and seismology. It is concluded that Hanford is one of the most extensively characterized nuclear sites

  18. Hanford defense waste studies

    International Nuclear Information System (INIS)

    Napier, B.A.; Zimmerman, M.G.; Soldat, J.K.

    1981-01-01

    PNL is assisting Rockwell Hanford Operations to prepare a programmatic environmental impact statement for the management of Hanford defense nuclear waste. The Ecological Sciences Department is leading the task of calculation of public radiation doses from a large matrix of potential routine and accidental releases of radionuclides to the environment

  19. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

    1992-05-01

    The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides a land use plan for the Hanford Site and presents a picture of what is currently known and anticipated in accordance with DOE Order 4320.1B. Site Development Planning. The HSDP wig be updated annually as future decisions further shape the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

  20. PERBEDAAN PH SALIVA ANTARA PENGGUNA PASTA GIGI YANG MENGANDUNG BAKING SODA DAN PENGGUNA PASTA GIGI YANG MENGANDUNG FLUOR

    OpenAIRE

    LINARDI, ALICIA NADIA

    2014-01-01

    2014 Latar belakang : Baking soda dan fluor merupakan bahan yang biasa ditambahkan dalam pasta gigi. Baking soda dan fluor mempunyai kemampuan untuk meningkatkan sekresi saliva dan pH saliva. Tujuan penelitian ini adalah untuk mengetahui perbedaan pH saliva antara pengguna pasta gigi yang mengandung baking soda dan pengguna pasta gigi yang mengandun fluor. Bahan dan metode : Jenis penelitian ini adalah eksperimental dengan desai...

  1. Dehydration and Rehydration of Carbonated Fluor- and Hydroxylapatite

    Directory of Open Access Journals (Sweden)

    Claude Yoder

    2012-03-01

    Full Text Available The recent definitive deuterium solid state NMR spectroscopic evidence for structural water in fluor- and hydroxylapatites has prompted our study of the conditions necessary for the removal and reincorporation of this important structural feature of apatites. Thermal gravimetric analysis of 20 synthetic carbonated calcium hydroxylapatite (CCaApOH samples and nine carbonated calcium fluorapatite (CCaApF samples has been used to determine the amount of structural and adsorbed water in each sample. No correlation between the weight percent and number of moles of structural water and the weight percent carbonate in CCaApOH and CCaApF has been found. In contrast, there appears to be a relationship between the amount of adsorbed water and the carbonate concentration in the fluorapatites prepared with a two hour digestion time, as well as in the hydroxylapatites prepared with one hour digestion periods, presumably due to the effect of carbonate on crystallite size. Structural water can be removed from the apatite lattice, primarily above 200 °C, but heating to over 550 °C is required for complete removal. This water can be partly reincorporated through an apparently kinetically-controlled process that is enhanced by an increase in time and/or temperature. We speculate that the incorporation of structural water occurs at the beginning of the formation of the apatite structure, approximately coincident with the incorporation of carbonate. We also speculate that water is both removed and reincorporated by proton transfers from water molecules to hydroxide ions.

  2. Repowering analysis: Hanford Generating Project (HGP), Task Order Number 6

    International Nuclear Information System (INIS)

    1988-12-01

    The Hanford Generating Project (HGP), owned by the Washington Public Power Supply System, consists of two low pressure steam turbines, generators, and associated equipment located adjacent to the Department of Energy's (DOE) N-Reactor. HGP has been able to produce approximately 800 MWe with low pressure steam supplied by N-Reactor. DOE has placed N-Reactor in cold standby status for an undetermined length of time. This results in the idling of the HGP since no alternative source of steam is available. Bonneville Power Administration contracted with Fluor Daniel, Inc. to investigate the feasibility and cost of constructing a new source of steam for (repowering) one of the HGP turbines. The steam turbine is currently operated with 135 psia steam. The turbines can be rebuilt to operate with 500 psia steam pressure by adding additional stages, buckets, nozzles, and diaphragms. Because of the low pressure design, this turbine can never achieve the efficiencies possible in new high pressure turbines by the presences of existing equipment reduces the capital cost of a new generating resource. Five repowering options were investigated in this study. Three cases utilizing gas turbine combined cycle steam generation equipment, one case utilizing a gas fired boiler, and a case utilizing a coal fired boiler. This report presents Fluor Daniel's analysis of these repowering options

  3. Use of metrics in an effective ALARA program

    International Nuclear Information System (INIS)

    Bates, B.B. Jr.

    1996-01-01

    ALARA radiological protection programs require metrics to meet their objectives. Sources of metrics include external dosimetry; internal dosimetry; radiological occurrences from the occurrence reporting an processing system (ORPS); and radiological incident reports (RIR). The sources themselves contain an abundance of specific open-quotes indicators.close quotes To choose the site-specific indicators that will be tracked and trended requires careful review. Justification is needed to defend the indicators selected and maybe even stronger justification is needed for those indicators that are available, but not chosen as a metric. Historically, the many different sources of information resided in a plethora of locations. Even the same type of metric had data located in different areas and could not be easily totaled for the entire Site. This required the end user to expend valuable time and effort to locate the data they needed. To address this problem, a central metrics database has been developed so that a customer can have all their questions addressed quickly and correctly. The database was developed in the beginning to answer some of the customer's most frequently asked questions. IL is now also a tool to communicate the status of the radiation protection program to facility managers. Finally, it also addresses requirements contained in the Rad Con manual and the 10CFR835 implementation guides. The database uses currently available, open-quotes user friendly,close quotes software and contains information from RIR's, ORPS, and external dosimetry records specific to ALARA performance indicators. The database is expandable to allow new metrics input. Specific reports have been developed to assist customers in their tracking and trending of ALARA metrics. These include quarterly performance indicator reports, monthly radiological incident reports, monthly external dose history and goals tracking reports, and the future use of performance indexing

  4. ALARA radiation considerations for the AP600 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lau, F.L. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    1995-03-01

    The radiation design of the AP600 reactor plant is based on an average annual occupational radiation exposure (ORE) of 100 man-rem. As a design goal we have established a lower value of 70 man-rem per year. And, with our current design process, we expect to achieve annual exposures which are well below this goal. To accomplish our goal we have established a process that provides criteria, guidelines and customer involvement to achieve the desired result. The criteria and guidelines provide the shield designer, as well as the systems and plant layout designers with information that will lead to an integrated plant design that minimizes personnel exposure and yet is not burdened with complicated shielding or unnecessary component access limitations. Customer involvement is provided in the form of utility input, design reviews and information exchange. Cooperative programs with utilities in the development of specific systems or processes also provides for an ALARA design. The results are features which include ALARA radiation considerations as an integral part of the plant design and a lower plant ORE. It is anticipated that a further reduction in plant personnel exposures will result through good radiological practices by the plant operators. The information in place to support and direct the plant designers includes the Utility Requirements Document (URD), Federal Regulations, ALARA guidelines, radiation design information and radiation and shielding design criteria. This information, along with the utility input, design reviews and information feedback, will contribute to the reduction of plant radiation exposure levels such that they will be less than the stated goals.

  5. ALARA review for the deactivation of 105-N Lift Station

    International Nuclear Information System (INIS)

    Nellesen, A.L.

    1997-01-01

    This ALARA review provides a description of the engineering and administrative controls used to manage personnel exposure and to control contamination levels and airborne radioactivity concentrations, while removing water, sludge, stabilizing surfaces, and all other associated work involved in the deactivation of the 105-N Lift Station. The lift station was used as a sump and received contaminated water from the 105-N Fuel Storage Basin weirs and contaminated drains in the 105-N Building. During operation water from the lift station was pumped to the 1310-N and 1325-N cribs. Deactivation of the lift station is a critical step in completing the deactivation of N-Area

  6. An evaluation of high-dose jobs for ALARA improvement

    International Nuclear Information System (INIS)

    Mun, J. H.; Kim, H. S.

    1997-01-01

    It is well known that about 70 percent of occupational dose have incurred from maintenance jobs at outage period. To reduce occupational dose, first, the high-dose jobs at the outage period should be identified and evaluated. For this, the database program is used, which contains the ORE data of reference plants, Kori Units 3 and 4. As a result, it is found that the jobs related to steam generator are the highest dose jobs in terms of collective ORE dose. From the analysis of the job procedures of those jobs, the ALARA improvements are also derived

  7. Cost-effectiveness studies as part of an ALARA program

    International Nuclear Information System (INIS)

    Baum, J.W.

    1986-01-01

    Recent studies of cost effectiveness of engineering modifications for dose reduction at nuclear power plants conducted at BNL will be considered in this report. Since each of these items has the potential for a 50% to 60% reduction in collective dose, it appears there is large potential for dose reduction from engineering type modifications. The question that must be answered for each plant is ''which modifications or improvements are required for optimization (ALARA). The purpose of this paper is to illustrate that quantified optimization need not be costly and can often be highly beneficial

  8. As low as is reasonably achievable (ALARA) studies relative to the NWTS program

    International Nuclear Information System (INIS)

    Abrams, L.A.; Schlegel, R.L.; Sullivan, R.P.

    1977-10-01

    The history of development of the as-low-as-is-reasonably achievable (ALARA) concept and ALARA criteria for radiation exposures as applied to both off-site (environmental) and on-site (occupational) exposures at nuclear power plants are reviewed. The current status of activities within the various federal agencies directed toward developing ALARA criteria for other areas of the nuclear fuel cycle is presented. Based on the historical development, the present activities, and on discussions with numerous people involved in this area, the future development of ALARA criteria and implications for the National Waste Terminal Storage (NWTS) Program is forecast. Environmental ALARA criteria which relate to minimizing radiation to the surrounding populaltion are discussed along with current occupational ALARA criteria and quidelines for risk-benefit assessments that are under development and recommendations to assure that evolving ALARA concepts are periodically brought up to date and that such concepts be made available to those subcontractors who have responsibility for design and operation of a repository. An annotated bibliography of some 83 sources giving information on ALARA criteria and its application is included

  9. Pacific Northwest Laboratory plan to maintain radiation exposure as low as reasonably achievable (ALARA)

    International Nuclear Information System (INIS)

    Higby, D.P.; Denovan, J.T.

    1982-12-01

    This document describes the radiation safety program at the Pacific Northwest Laboratory (PNL). The practices and administrative policies of this program support the principles of ALARA (to maintain radiation exposure as low as reasonably achievable). This document also describes a program to establish safety goals at PNL to help ensure that operations are conducted according to ALARA principles

  10. As low as is reasonably achievable (ALARA) studies relative to the NWTS program

    Energy Technology Data Exchange (ETDEWEB)

    Abrams, L.A.; Schlegel, R.L.; Sullivan, R.P.

    1977-10-01

    The history of development of the as-low-as-is-reasonably achievable (ALARA) concept and ALARA criteria for radiation exposures as applied to both off-site (environmental) and on-site (occupational) exposures at nuclear power plants are reviewed. The current status of activities within the various federal agencies directed toward developing ALARA criteria for other areas of the nuclear fuel cycle is presented. Based on the historical development, the present activities, and on discussions with numerous people involved in this area, the future development of ALARA criteria and implications for the National Waste Terminal Storage (NWTS) Program is forecast. Environmental ALARA criteria which relate to minimizing radiation to the surrounding populaltion are discussed along with current occupational ALARA criteria and quidelines for risk-benefit assessments that are under development and recommendations to assure that evolving ALARA concepts are periodically brought up to date and that such concepts be made available to those subcontractors who have responsibility for design and operation of a repository. An annotated bibliography of some 83 sources giving information on ALARA criteria and its application is included. (JRD)

  11. Best Available Technology (economically achievable) guidance document for the Hanford Site

    International Nuclear Information System (INIS)

    1988-07-01

    This document provides Westinghouse Hanford Company (Westinghouse Hanford) and the US Department of Energy (DOE) with a step-by-step procedure for the identification and documentation of the Best Available Technology (BAT) economically achievable for treating liquid effluents on the Hanford Site. The BAT determination is a key element in the DOE strategy to eliminate use of the soil column for contaminated effluents disposal. Following application of BAT, a liquid effluent is considered suitable for discharge to the environment, including the soil column. Liquid effluents on the Hanford Site are currently disposed of in accordance with DOE orders that require protection of public health and safety, and to the extent possible, minimize adverse impacts on the environment. The determination of BAT on a liquid effluent will only occur after the effluent meets all applicable release limits. As a result, the application of BAT may involve an additional level of control, as well as contribute to the overall Hanford Site as low as reasonably achievable (ALARA) program. 27 refs., 7 figs., 1 tab

  12. Hanford Site Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J. (Westinghouse Hanford Co., Richland, WA (USA)); Yancey, E.F. (Pacific Northwest Lab., Richland, WA (USA))

    1990-01-01

    The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs.

  13. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J.; Yancey, E.F.

    1990-01-01

    The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs

  14. Hanford K Basins spent nuclear fuels project update

    International Nuclear Information System (INIS)

    Hudson, F.G.

    1997-01-01

    Twenty one hundred metric tons of spent nuclear fuel are stored in two concrete pools on the Hanford Site, known as the K Basins, near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current wet pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in the K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported into the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building (CSB) in the 200 Area for staging prior to hot conditioning. The conditioning step to remove chemically bound water is performed by holding the MCO at 300 C under vacuum. This step is necessary to prevent excessive pressure buildup during interim storage that could be caused by corrosion. After conditioning, MCOs will remain in the CSB for interim storage until a national repository is completed

  15. Hanford K Basins spent nuclear fuels project update

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, F.G.

    1997-10-17

    Twenty one hundred metric tons of spent nuclear fuel are stored in two concrete pools on the Hanford Site, known as the K Basins, near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current wet pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in the K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported into the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building (CSB) in the 200 Area for staging prior to hot conditioning. The conditioning step to remove chemically bound water is performed by holding the MCO at 300 C under vacuum. This step is necessary to prevent excessive pressure buildup during interim storage that could be caused by corrosion. After conditioning, MCOs will remain in the CSB for interim storage until a national repository is completed.

  16. Just in Time DSA the Hanford Nuclear Safety Basis Strategy

    Energy Technology Data Exchange (ETDEWEB)

    JACKSON, M.W.

    2002-06-01

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford, Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safely Basis Requirements (the Rule) in January 2001 requires that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSAs that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long-term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: Compliance with the Rule; A ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and Consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

  17. Just in Time DSA the Hanford Nuclear Safety Basis Strategy

    International Nuclear Information System (INIS)

    JACKSON, M.W.

    2002-01-01

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford, Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safely Basis Requirements (the Rule) in January 2001 requires that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSAs that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long-term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: Compliance with the Rule; A ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and Consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD and D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD and D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex

  18. ALARA issues arising for safety and security of radiation sources and security screening devices - Summary and recommendations of the 12. European ALARA network workshop

    International Nuclear Information System (INIS)

    Shaw, P.; Crouail, P.; Drouet, F.

    2010-01-01

    The 12. European ALARA Network (EAN) workshop on 'ALARA issues arising for safety and security of radiation sources and security screening devices' took place in Vienna (Austria) in October 2009. The aim of that workshop was to consider how the implementation of ALARA3, in terms of planned and emergency situations, involving worker and public doses, is affected by the introduction of security-related measures. In the case of new equipment and procedures, there was also the question of whether exposures arising from security screening devices can be justified and optimised. This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. During their discussions, the working groups identified recommendations dealing with the following topics: the implementation of the Code of Conduct and HASS4 - ensuring ALARA; balancing security and safety - how to achieve an optimum solution; the management of an emergency exposure situation from an ALARA perspective; the justification and optimisation of the use of security devices. The objective of this paper is to present the main conclusions and recommendations produced during the workshop. Individual presentations (papers and slides) as well as the reports from the working groups are available to download on the EAN web site (http://www.eu-alara.net). (authors)

  19. LESSONS LEARNED IN OPERATING THE HOSE-IN-HOSE SYSTEM FOR TRANSFSERRING SLUDGE AT HANFORD'S K BASINS

    International Nuclear Information System (INIS)

    PERES MW

    2008-01-01

    In May 2007, the Department of Energy and the Fluor Hanford K Basin Closure Project completed transferring sludge from the K East Basin to new containers in the K West Basin using a Hose-in-Hose system. This project presented a number of complex and unique technical, operational, and management challenges that had to be resolved to complete the required transfers and satisfy project milestones. The project team (including DOE; regulators; and Fluor management, operations, maintenance, engineering and all other support organizations) found innovative solutions to each challenge. This paper records lessons learned during the operational phase of the sludge transfer via the Hose-In-Hose system. The subject is limited to the operational phase and does not cover design, development, testing or turnover. A discussion of the situation or problem encountered is provided, along with the lesson learned as applicable to a future program or project

  20. The program of the ALARA Center at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Khan, T.A.; Baum, J.W.

    1993-01-01

    In 1984 the Brookhaven National Laboratory was asked by the Nuclear Regulatory Commission to set up a Center to monitor dose-reduction efforts in the US and abroad and to focus the industry's attention on ALARA. The paper summarizes the main work of the ALARA Center between 1984 and 1992. The Center maintains nine data bases for the NRC and the Nuclear Power Industry. These databases are constantly updated and access to them is provided through a personal computer and a modem and by periodic publications in the form of a newsletter and NUREG reports. Also described briefly are eight other projects related to dose-reduction at nuclear power plants that the Center has carried out for the NRC. Among these are projects that analyze the cost-effectiveness of engineering modifications, look at worldwide activities at dose reduction and compare US and foreign dose experience, examine high-dose worker groups and high-dose jobs, develop optimum techniques to control contamination at nuclear plants, and look at the doses being received by men and women in all sectors of the nuclear industry

  1. Hanford Site Infrastructure Plan

    International Nuclear Information System (INIS)

    1990-01-01

    The Hanford Site Infrastructure Plan (HIP) has been prepared as an overview of the facilities, utilities, systems, and services that support all activities on the Hanford Site. Its purpose is three-fold: to examine in detail the existing condition of the Hanford Site's aging utility systems, transportation systems, Site services and general-purpose facilities; to evaluate the ability of these systems to meet present and forecasted Site missions; to identify maintenance and upgrade projects necessary to ensure continued safe and cost-effective support to Hanford Site programs well into the twenty-first century. The HIP is intended to be a dynamic document that will be updated accordingly as Site activities, conditions, and requirements change. 35 figs., 25 tabs

  2. Hanford Emergency Response Plan

    International Nuclear Information System (INIS)

    Wagoner, J.D.

    1994-04-01

    The Hanford Emergency Response Plan for the US Department of Energy (DOE), Richland Operations Office (RL), incorporates into one document an overview of the emergency management program for the Hanford Site. The program has been developed in accordance with DOE orders, and state and federal regulations to protect worker and public health and safety and the environment in the event of an emergency at or affecting the Hanford Site. This plan provides a description of how the Hanford Site will implement the provisions of DOE 5500 series and other applicable Orders in terms of overall policies and concept of operations. It should be used as the basis, along with DOE Orders, for the development of specific contractor and RL implementing procedures

  3. Hanford Emergency Response Plan

    Energy Technology Data Exchange (ETDEWEB)

    Wagoner, J.D.

    1994-04-01

    The Hanford Emergency Response Plan for the US Department of Energy (DOE), Richland Operations Office (RL), incorporates into one document an overview of the emergency management program for the Hanford Site. The program has been developed in accordance with DOE orders, and state and federal regulations to protect worker and public health and safety and the environment in the event of an emergency at or affecting the Hanford Site. This plan provides a description of how the Hanford Site will implement the provisions of DOE 5500 series and other applicable Orders in terms of overall policies and concept of operations. It should be used as the basis, along with DOE Orders, for the development of specific contractor and RL implementing procedures.

  4. Hanford cultural resources laboratory

    International Nuclear Information System (INIS)

    Wright, M.K.

    1995-01-01

    This section of the 1994 Hanford Site Environmental Report describes activities of the Hanford Cultural Resources Laboratory (HCRL) which was established by the Richland Operations Office in 1987 as part of PNL.The HCRL provides support for the management of the archaeological, historical, and traditional cultural resources of the site in a manner consistent with the National Historic Preservation Act, the Native American Graves Protection and Repatriation Act, and the American Indian Religious Freedom Act

  5. Hanford cultural resources laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Wright, M.K.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report describes activities of the Hanford Cultural Resources Laboratory (HCRL) which was established by the Richland Operations Office in 1987 as part of PNL.The HCRL provides support for the management of the archaeological, historical, and traditional cultural resources of the site in a manner consistent with the National Historic Preservation Act, the Native American Graves Protection and Repatriation Act, and the American Indian Religious Freedom Act.

  6. Hanford Facility contingency plan

    International Nuclear Information System (INIS)

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

    1993-10-01

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

  7. Hanford work faces change

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This article is a discussion of DOE efforts in the awarding of a large engineering-construction contract at the Hanford Reservation. Though the announced winner was a group lead by J. A. Jones Construction/Duke Engineering Services, the incumbent (ICF-Kaiser Engineers) protested the announced award. The protest was dismissed by the GAO, but DOE officials still reopened the bidding. There was also a short note regarding the award of the ERMC at Hanford

  8. CLOSING IN ON CLOSURE PERSPECTIVES FROM HANFORD and FERNALD AN UPDATE

    International Nuclear Information System (INIS)

    CONNELL, J.D.

    2004-01-01

    In World War II, the arms dramatically changed from machine guns and incendiary bombs to nuclear weapons. Hanford and Fernald, two government-run sites, were part of the infrastructure established for producing the fissile material for making these weapons, as well as building a nuclear arsenal to deter future aggression by other nations. This paper compares and contrasts, from a communications point of view, these two Department of Energy (DOE) closure sites, each with Fluor as a prime contractor. The major differences between the two sites--Hanford in Washington state and Fernald in Ohio--includes the following: size of the site and the workforce, timing of closure, definition of end state, DOE oversight, proximity to population centers, readiness of local population for closure, and dependence of the local economy on the site's budget. All of these elements affect how the sites' communication professionals provide information even though the objectives are the same: build public acceptance and support for DOE's mission to accelerate cleanup, interface with stakeholders to help ensure that issues are addressed and goals are met, help workers literally work themselves out of jobs--faster, and prepare the ''host'' communities to deal with the void left when the sites are closed and the government contractors are gone. The 12-months between January 04 and January 05 have seen dramatic transformations at both sites, as Fernald is now just about a year away from closure and FLuor's work at Hanford has made the transition from operations to deactivation and demolition. While Fernald continues to clean out silos of waste and ship it off site, Hanford is dealing with recent state legislation that has the potential to significantly impact the progress of cleanup. These changes have even further accentuated the differences in the content, distribution, and impact of communications

  9. Managing risk at Hanford

    International Nuclear Information System (INIS)

    Hesser, W.A.; Stillwell, W.G.; Rutherford, W.A.

    1994-01-01

    Clearly, there is sufficient motivation from Washington for the Hanford community to pay particular attention to the risks associated with the substantial volumes of radiological, hazardous, and mixed waste at Hanford. But there is also another reason for emphasizing risk: Hanford leaders have come to realize that their decisions must consider risk and risk reduction if those decisions are to be technically sound, financially affordable, and publicly acceptable. The 560-square miles of desert land is worth only a few thousand dollars an acre (if that) -- hardly enough to justify the almost two billion dollars that will be spent at Hanford this year. The benefit of cleaning up the Hanford Site is not the land but the reduction of potential risk to the public and the environment for future generations. If risk reduction is our ultimate goal, decisions about priority of effort and resource allocation must consider those risks, now and in the future. The purpose of this paper is to describe how Hanford is addressing the issues of risk assessment, risk management, and risk-based decision making and to share some of our experiences in these areas

  10. HANFORD GROUNDWATER REMEDIATION

    Energy Technology Data Exchange (ETDEWEB)

    CHARBONEAU, B; THOMPSON, M; WILDE, R.; FORD, B.; GERBER, M.S.

    2006-02-01

    By 1990 nearly 50 years of producing plutonium put approximately 1.70E + 12 liters (450 billion gallons) of liquid wastes into the soil of the 1,518-square kilometer (586-square mile) Hanford Site in southeast Washington State. The liquid releases consisted of chemicals used in laboratory experiments, manufacturing and rinsing uranium fuel, dissolving that fuel after irradiation in Hanford's nuclear reactors, and in liquefying plutonium scraps needed to feed other plutonium-processing operations. Chemicals were also added to the water used to cool Hanford's reactors to prevent corrosion in the reactor tubes. In addition, water and acid rinses were used to clean plutonium deposits from piping in Hanford's large radiochemical facilities. All of these chemicals became contaminated with radionuclides. As Hanford raced to help win World War II, and then raced to produce materials for the Cold War, these radioactive liquid wastes were released to the Site's sandy soils. Early scientific experiments seemed to show that the most highly radioactive components of these liquids would bind to the soil just below the surface of the land, thus posing no threat to groundwater. Other experiments predicted that the water containing most radionuclides would take hundreds of years to seep into groundwater, decaying (or losing) most of its radioactivity before reaching the groundwater or subsequently flowing into the Columbia River, although it was known that some contaminants like tritium would move quickly. Evidence today, however, shows that many contaminants have reached the Site's groundwater and the Columbia River, with more on its way. Over 259 square kilometers (100 square miles) of groundwater at Hanford have contaminant levels above drinking-water standards. Also key to successfully cleaning up the Site is providing information resources and public-involvement opportunities to Hanford's stakeholders. This large, passionate, diverse, and

  11. Design of a System to Retrieve Sludge from the K East Spent Fuel Basin at Hanford

    International Nuclear Information System (INIS)

    TWITCHELL, A.L.

    2003-01-01

    This paper describes the Sludge Retrieval System (SRS), which was designed to safely remove radioactive sludge from the K East spent fuel basin at the 100 K Area of the Hanford Site. Basin water and sludge have the potential to leak to the environment due to the age and condition of the basins. Since the 100 K Area spent fuel basins are located next to the Columbia River, the Spent Nuclear Fuel Project mission includes the safe removal, containment, and transportation of sludge from the basins to a secure storage location. The scope of the SRS includes: (1) a system capable of retrieving sludge from the K East basin floor, pits, and fuel canisters; (2) separation of debris from sludge, where debris is defined as any material greater than 0.64 cm (0.25 in.) in diameter; (3) collection of sludge particles in a container that can be transported away from the basin; and (4) modifications to the K East basin to allow installation of the SRS. The SRS was designed by Fluor Federal Services. Changes to the designed system were made by Fluor Hanford as a result of full-scale testing performed after design. This paper discusses this testing, as well as operation and control of the system. Construction and startup testing was initially scheduled to be complete by the end of December 2002. Startup of the system is now expected in April 2003

  12. DESIGN OF A SYSTEM TO RETRIEVE SLUDGE FROM THE K EAST SPENT FUEL BASIN AT HANFORD

    International Nuclear Information System (INIS)

    Twitchell, A.L.; MacLean, G.T.; Ho, Q.T.; Fort, D.L.

    2003-01-01

    This paper describes the Sludge Retrieval System (SRS), which was designed to safely remove radioactive sludge from the K East spent fuel basin at the 100 K Area of the Hanford Site. Basin water and sludge have the potential to leak to the environment due to the age and condition of the basins. Since the 100 K Area spent fuel basins are located next to the Columbia River, the Spent Nuclear Fuel Project mission includes the safe removal, containment, and transportation of sludge from the basins to a secure storage location. The scope of the SRS includes: A system capable of retrieving sludge from the K East basin floor, pits, and fuel canisters; Separation of debris from sludge, where debris is defined as any material greater than 0.64 cm (0.25 in.) in diameter; Collection of sludge particles in a container that can be transported away from the basin; Modifications to the K East basin to allow installation of the SRS. The SRS was designed by Fluor Federal Services. Changes to the designed system were made by Fluor Hanford as a result of full-scale testing performed after design. This paper discusses this testing, as well as operation and control of the system. Construction and startup testing was initially scheduled to be complete by the end of December 2002. Startup of the system is now expected in April 2003

  13. Hanford high-level waste melter system evaluation data packages

    International Nuclear Information System (INIS)

    Elliott, M.L.; Shafer, P.J.; Lamar, D.A.; Merrill, R.A.; Grunewald, W.; Roth, G.; Tobie, W.

    1996-03-01

    The Tank Waste Remediation System is selecting a reference melter system for the Hanford High-Level Waste vitrification plant. A melter evaluation was conducted in FY 1994 to narrow down the long list of potential melter technologies to a few for testing. A formal evaluation was performed by a Melter Selection Working Group (MSWG), which met in June and August 1994. At the June meeting, MSWG evaluated 15 technologies and selected six for more thorough evaluation at the Aug. meeting. All 6 were variations of joule-heated or induction-heated melters. Between the June and August meetings, Hanford site staff and consultants compiled data packages for each of the six melter technologies as well as variants of the baseline technologies. Information was solicited from melter candidate vendors to supplement existing information. This document contains the data packages compiled to provide background information to MSWG in support of the evaluation of the six technologies. (A separate evaluation was performed by Fluor Daniel, Inc. to identify balance of plant impacts if a given melter system was selected.)

  14. Vadose Zone Hydrogeology Data Package for Hanford Assessments

    Energy Technology Data Exchange (ETDEWEB)

    Last, George V.; Freeman, Eugene J.; Cantrell, Kirk J.; Fayer, Michael J.; Gee, Glendon W.; Nichols, William E.; Bjornstad, Bruce N.; Horton, Duane G.

    2006-06-01

    This data package documents the technical basis for selecting physical and geochemical parameters and input values that will be used in vadose zone modeling for Hanford assessments. This work was originally conducted as part of the Characterization of Systems Task of the Groundwater Remediation Project managed by Fluor Hanford, Inc., Richland, Washington, and revised as part of the Characterization of Systems Project managed by the Pacific Northwest National Laboratory (PNNL) for the U.S. Department of Energy, Richland Operations Office (DOE-RL). This data package describes the geologic framework, the physical, hydrologic, and contaminant transport properties of the geologic materials, and deep drainage (i.e., recharge) estimates, and builds on the general framework developed for the initial assessment conducted using the System Assessment Capability (SAC) (Bryce et al. 2002). The general approach for this work was to update and provide incremental improvements over the previous SAC data package completed in 2001. As with the previous SAC data package, much of the data and interpreted information were extracted from existing documents and databases. Every attempt was made to provide traceability to the original source(s) of the data or interpretations.

  15. Application of the ALARA process in the regulation of nuclear activities

    International Nuclear Information System (INIS)

    1991-05-01

    In this report the historical and conceptual basis of the ALARA process has been reviewed. The application solely of a prescriptive approach, particularly a rigorous quantitative approach to the decision-making process, has been questioned. While the Committees recognize the value of quantitative techniques they strongly emphasize that application of the ALARA concept is a much broader process for the determination of acceptable levels of protection. An ALARA process should take into account social and economic factors that are not quantifiable and involve representation of all those having a legitimate interest in the results of the process

  16. The ALARA project of the EDF nuclear park exploitation

    International Nuclear Information System (INIS)

    Potoczek, J.

    1998-01-01

    To bring the exploitation of the nuclear park of EDF at the level of the best exploiters in the world in matter of collective and individual dosimetry, the ALARA principle coordinates numerous actions: to associate the temporary societies, to define common language, methods and tools for the whole park to organize a level effect in this area, to optimize the maintenance that is expansive in radiation doses, to make the different levels of management responsible on dosimetric stakes, to reduce the singular sources of exposure, to assure the organisation and exploitation of the experience back in this field and adapt consequently the system of information. The results are cheerful and the objectives for 2000 are: less than 1.2 h.Sv by year and by reactor, no intervener whom annual radiation dose is upper than 20 mSv (out of exceptional case). (N.C.)

  17. Application of ALARA principles to shipment of spent nuclear fuel

    International Nuclear Information System (INIS)

    Greenborg, J.; Brackenbush, L.W.; Murphy, D.W.; Burnett, R.A.; Lewis, J.R.

    1980-05-01

    The public exposure from spent fuel shipment is very low. In view of this low exposure and the perfect safety record for spent fuel shipment, existing systems can be considered satisfactory. On the other hand, occupational exposure reduction merits consideration and technology improvement to decrease dose should concentrate on this exposure. Practices that affect the age of spent fuel in shipment and the number of times the fuel must be shipped prior to disposal have the largest impact. A policy to encourage a 5-year spent fuel cooling period prior to shipment coupled with appropriate cask redesign to accommodate larger loads would be consistent with ALARA and economic principles. And finally, bypassing high population density areas will not in general reduce shipment dose

  18. Cobalt reduction of NSSS valve hardfacings for ALARA

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Joo Hak; Lee, Sang Sub [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-07-01

    This report informs NSSS designer that replacement of materials is one of the major means of ALARA implementation, and describes that NSSS valves with high-cobalt hardfacing are significant contributors to post-shutdown radiation fields caused by activation of cobalt-59 to cobalt-60. Generic procedures for implementing cobalt reduction programs for valves are presented. Discussions are presented of the general and specific design requirements for valve hardfacing in nuclear service. The nuclear safety issues involved with changing valve hardfacing materials are discussed. The common methods used to deposit hardfacing materials are described together with an explanation of the wear measurements. Wear resistance, corrosion resistance, friction coefficient, and mechanical properties of candidate hardfacing alloys are given. World-wide nuclear utility experience with cobalt-free hardfacing alloys is described. The use of low-cobalt or cobalt-free alloys in other nuclear plant components is described. 17 figs., 38 tabs., 18 refs. (Author).

  19. Application of the ALARA principle to individual occupational radiation monitoring

    International Nuclear Information System (INIS)

    Aleinikov, V.E.

    1998-01-01

    Routine individual occupational radiation monitoring is necessary to ensure that exposure are kept as low as reasonably achievable (ALARA) and that the authorized dose limits are not exceeded. The type and extend of the monitoring depend on the nature and magnitude of occupational radiation exposure. Optimal choice of the wearing time for individual dosimeters, T, has important consequences for achievement of the individual monitoring objects. The choice of T depends on individual dose distribution, the lower detection limit for the detector used, the lost of an information during period of monitoring, the cost of the measurements and the benefits associated with the results. The paper describes the application of quantitative optimization techniques to optimize the wearing time for individual dosimeters. It was shown how optimal wearing time for individual dosimeters depends on dose distribution, the lower detection limit, dose limit, fading and cost of the measurements. (author)

  20. Cobalt reduction of NSSS valve hardfacings for ALARA

    International Nuclear Information System (INIS)

    Kim, Joo Hak; Lee, Sang Sub

    1994-07-01

    This report informs NSSS designer that replacement of materials is one of the major means of ALARA implementation, and describes that NSSS valves with high-cobalt hardfacing are significant contributors to post-shutdown radiation fields caused by activation of cobalt-59 to cobalt-60. Generic procedures for implementing cobalt reduction programs for valves are presented. Discussions are presented of the general and specific design requirements for valve hardfacing in nuclear service. The nuclear safety issues involved with changing valve hardfacing materials are discussed. The common methods used to deposit hardfacing materials are described together with an explanation of the wear measurements. Wear resistance, corrosion resistance, friction coefficient, and mechanical properties of candidate hardfacing alloys are given. World-wide nuclear utility experience with cobalt-free hardfacing alloys is described. The use of low-cobalt or cobalt-free alloys in other nuclear plant components is described. 17 figs., 38 tabs., 18 refs. (Author)

  1. Review of Hanford international activities

    International Nuclear Information System (INIS)

    Panther, D.G.

    1993-01-01

    Hanford initiated a review of international activities to collect, review, and summarize information on international environmental restoration and waste management initiatives considered for use at Hanford. This effort focused on Hanford activities and accomplishments, especially international technical exchanges and/or the implementation of foreign-developed technologies

  2. The preliminary success of ALARA implementation in Daya Bay NPP

    International Nuclear Information System (INIS)

    Yang Maochun; Chen Degan

    2000-01-01

    Based on the practical condition of the plant and in reference to advanced management experiences worldwide, Daya Bay Nuclear Power Plant has established its own peculiar management system for radiation protection management and ALARA implementation. The characteristics of the system are: radiation protection training to all workers, active involvement of all managers and staffs, and whole process safety control to maintenance activities. The management philosophy of 'workers are responsible for their own radiation safety' is adopted in the plant. A strict, formalized and systematic whole staff radiation protection training, evaluation, authorization and periodically refreshing mechanism had been established and executed in the plant. In the organizational point of view, the responsibilities of line managers were specified in plant procedures, ALARA coordination organization on plant level and for specific activities were established. Meanwhile, the plant highlighted the defining, following up, controlling and advertising of radiation protection targets. All these measures made radiation protection management be the responsibilities of a safety network in which whole staffs are involved. In the practical radiation protection activities, the plant focuses on works of high radiation risk and performs whole process control. In addition, professional radiation protection staff played an important and active role in technical advisory and control of radiation protection. Satisfactory results have been achieved in Daya Bay NPP in radiation protection in the past years. The collective dose including that of contractors per unit and year have been declining from 0.99 man·Sv/Unit·Year in 1995 to 0.667 man·Sv/Unit·Year in 1998, which were consistently lower than the best quartile result of PWR plants in WANO reports each year. Individual dose was also controlled at a very low level, no one was overexposed in the past years

  3. Culture of safety. Indicators of culture of safety. Stage of culture of safety. Optimization of radiating protection. Principle of precaution. Principle ALARA. Procedure ALARA

    International Nuclear Information System (INIS)

    Mursa, E.

    2006-01-01

    Object of research: is the theory and practice of optimization of radiating protection according to recommendations of the international organizations, realization of principle ALARA and maintenance of culture of safety (SC) on the nuclear power plant. The purpose of work - to consider the general aspects of realization of principle ALARA, conceptual bases of culture of safety, as principle of management, and practice of their introduction on the nuclear power plant. The work has the experts' report character in which the following questions are presented: The recommendations materials of the IAEA and other international organizations have been assembled, systematized and analyzed. The definitions, characteristics and universal SC features, and also indicators as a problem of parameters and quantitative SC measurements are described in details advanced. The ALARA principles - principle of precaution; not acceptance of zero risk; choice of a principle ALARA; model of acceptable radiation risk are described. The methodology of an estimation of culture of safety level and practical realization of the ALARA principle in separate organization is shown on a practical example. The SC general estimation at a national level in Republic of Moldova have been done. Taking into consideration that now Safety Culture politics are introduced only in relation to APS, in this paper the attempt of application of Safety Culture methodology to Radiological Objects have been made (Oncological Institute of the Republic of Moldova and Special Objects No.5101 and 5102 for a long time Storage of the Radioactive Waste). (authors)

  4. Strategy for Meeting the Secretary of Energy and Hanford Site FY 2001 Pollution Prevention Goals

    International Nuclear Information System (INIS)

    CLARK, D.E.

    2000-01-01

    The purpose of this strategy is to identify the Fiscal Year (FY) 2001 Hanford Site waste reduction, sanitary recycling and affirmative procurement goals and identify the action required to ensure that the Secretary of Energy's FY 2005 pollution prevention and the FY 2001 Hanford Site goals are met. The strategy and plan to ensure that the Secretary of Energy's routine waste reduction, recycling, cleanup/stabilization waste and affirmative procurement goals are met consists of four phases. The first phase is to ensure that the infrastructure is in place to support planning and organization. This phase involves ensuring that roles and responsibilities are identified; requirement documents are current; goals and successes are communicated; and accurate and current waste information is available. Roles and responsibilities are identified and the RL requirement documents (i.e., the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan and Hanford Site Guide for Preparing and Maintaining Generator Group Pollution Prevention Program Documentation) will specify the Secretary of Energy's goals. Goals will be communicated formally and informally via the Hanford Reach, training sessions, meetings and correspondence. Sharing of pollution prevention successes and goal progress are encouraged at the Pollution Prevention/Waste Minimization (PZ/WMin) quarterly meetings. Existing site waste generation databases will be utilized to provide current waste generation data. The second phase of the strategy and plan is to establish and allocate goals by prime contractor (i.e. Fluor Hanford, Inc. (FH), Pacific Northwest National Laboratory (PNNL), Bechtel Hanford Inc. (BHI), and CH2MHill Hanford Group (CHG)). This requires determining current status toward meeting the Secretary of Energy's goals; establishing the Hanford Site FY goals, and allocating waste reduction goals by prime contractor. The third phase of the strategy and plan is goal implementation. This

  5. Hanford groundwater scenario studies

    International Nuclear Information System (INIS)

    Arnett, R.C.; Gephart, R.E.; Deju, R.A.; Cole, C.R.; Ahlstrom, S.W.

    1977-05-01

    This report documents the results of two Hanford groundwater scenario studies. The first study examines the hydrologic impact of increased groundwater recharge resulting from agricultural development in the Cold Creek Valley located west of the Hanford Reservation. The second study involves recovering liquid radioactive waste which has leaked into the groundwater flow system from a hypothetical buried tank containing high-level radioactive waste. The predictive and control capacity of the onsite Hanford modeling technology is used to evaluate both scenarios. The results of the first study indicate that Cold Creek Valley irrigationis unlikely to cause significant changes in the water table underlying the high-level waste areas or in the movement of radionuclides already in the groundwater. The hypothetical tank leak study showed that an active response (in this case waste recovery) can be modeled and is a possible alternative to passive monitoring of radionuclide movement in the unlikely event that high-level waste is introduced into the groundwater

  6. Hanford Area 2000 Population

    International Nuclear Information System (INIS)

    Elliott, Douglas B.; Scott, Michael J.; Antonio, Ernest J.; Rhoads, Kathleen

    2004-01-01

    This report was prepared for the U.S. Department of Energy (DOE) Richland Operations Office, Surface Environmental Surveillance Project, to provide demographic data required for ongoing environmental assessments and safety analyses at the DOE Hanford Site near Richland, Washington. This document includes 2000 Census estimates for the resident population within an 80-kilometer (50-mile) radius of the Hanford Site. Population distributions are reported relative to five reference points centered on meteorological stations within major operating areas of the Hanford Site - the 100 F, 100 K, 200, 300, and 400 Areas. These data are presented in both graphical and tabular format, and are provided for total populations residing within 80 km (50 mi) of the reference points, as well as for Native American, Hispanic and Latino, total minority, and low-income populations

  7. Hanford Waste Vitrification Plant

    International Nuclear Information System (INIS)

    Larson, D.E.; Allen, C.R.; Kruger, O.L.; Weber, E.T.

    1991-10-01

    The Hanford Waste Vitrification Plant (HWVP) is being designed to immobilize pretreated Hanford high-level waste and transuranic waste in borosilicate glass contained in stainless steel canisters. Testing is being conducted in the HWVP Technology Development Project to ensure that adapted technologies are applicable to the candidate Hanford wastes and to generate information for waste form qualification. Empirical modeling is being conducted to define a glass composition range consistent with process and waste form qualification requirements. Laboratory studies are conducted to determine process stream properties, characterize the redox chemistry of the melter feed as a basis for controlling melt foaming and evaluate zeolite sorption materials for process waste treatment. Pilot-scale tests have been performed with simulated melter feed to access filtration for solids removal from process wastes, evaluate vitrification process performance and assess offgas equipment performance. Process equipment construction materials are being selected based on literature review, corrosion testing, and performance in pilot-scale testing. 3 figs., 6 tabs

  8. ALARA Council: Sharing our resources and experiences to reduce doses at Commonwealth Edison Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Rescek, F. [Commonwealth Edison Co., Downers Grove, IL (United States)

    1995-03-01

    Commonwealth Edison Company is an investor-owned utility company supplying electricity to over three million customers (eight million people) in Chicago and northern Illinois, USA. The company operates 16 generating stations which have the capacity to produce 22,522 megawatts of electricity. Six of these generating stations, containing 12 nuclear units, supply 51% of this capacity. The 12 nuclear units are comprised of four General Electric boiling water (BWR-3) reactors, two General Electric BWR-5 reactors, and six Westinghouse four-loop pressurized water reactors (PWR). In August 1993, Commonwealth Edison created an ALARA Council with the responsibility to provide leadership and guidance that results in an effective ALARA Culture within the Nuclear Operations Division. Unlike its predecessor, the Corporate ALARA Committee, the ALARA Council is designed to bring together senior managers from the six nuclear stations and corporate to create a collaborative effort to reduce occupational doses at Commonwealth Edison`s stations.

  9. Proposal of organisation and ALARA procedures for maintenance site: application to replacement of steam generator

    International Nuclear Information System (INIS)

    Lochard, J.; Lefaure, C.

    1989-08-01

    This report proposes generic organization and ALARA procedures for preparing a maintenance site at a NPP. After a short description of the ALARA principle, it describes the proposition for French sites. They are grouped according to the following: motivation, organisation, means. They are illustrated by the example of steam generator replacement. Three special points concerning preparation of the site are developed: education; training of operators; review of the project

  10. ALARA Review for the Sediment Relocation and Removal from the 105-N Fuel Storage Basin

    International Nuclear Information System (INIS)

    Demers, J.W.

    1998-01-01

    This as low as reasonable achievable (ALARA) review revision provides a description of the engineering and administrative controls used to manage personnel exposure, control contamination levels, and airborne radioactivity concentrations during sediment relocation and removal in the 105-N Fuel Storage Basin. This document updates and supercedes the ALARA review of the sediment-related activities contained in 100-N Basin Stabilization Project As Low As Reasonably Achievable Plan (BHI 1995)

  11. An operating nuclear utility's experience with the ALARA design of a new nuclear unit

    International Nuclear Information System (INIS)

    Rodgers, R.C.

    1985-01-01

    This talk presents a review of how operating experience at Northeast Utilities has been factored into the design of a new nuclear unit and the development and management of the radiation protection program. Their operational experience has indicated that there are two facets to keeping radiation exposures ALARA. The first is the proper ALARA design of the unit. The other facet is the design of a comprehensive radiation protection program. The author discusses these facets in some detail

  12. DOE wants Hanford change

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Nine months ago, Energy Secretary Hazel O'Leary promised local officials running the agency's huge Hanford, Washington, weapon complex more control in directing its projected $57-billion waste cleanup. Earlier this month, she returned to the site for a follow-on open-quotes summit,close quotes this time ordering teamwork with contractors, regulators and local activities

  13. Ten years of ALARA experience in commercial nuclear pharmacy

    International Nuclear Information System (INIS)

    Coffey, J.L.; Seifert, K.L.; Green, R.L.; McAnany, P.J.

    2002-01-01

    The objective of this study was to review ten years of extremity exposure in a growing nuclear pharmacy company and determine those practices that have been most effective in keeping exposures ALARA. The focus of this study was specifically on extremity exposure since whole body exposures have not been as significant. Methods: More than 400 dispensing employees are monitored weekly for extremity exposure. Currently, these employees handle and dispense more than 9,000 Curies (333,000 GBq) of activity ready for use in nuclear medicine procedures each week. The quarterly and annual extremity exposure histories were examined and compared with the introduction of different initiatives to limit these exposures. Changes in the total activity per unit dose were considered as well as the introduction of different compounding practices during this time. An attempt was made to also determine specifically which activities contribute most to the extremity exposure of a dispenser. Procedural changes were reviewed as well as engineering controls such as new shielding materials and designs. Results: A significant conversion of cardiac doses occurred during the time period evaluated. Tc-99m heart agents became the preferred radiopharmaceutical replacing a significant portion of Tl-201 that had been used previously. Tl-201 is still used often in conjunction with a Tc-99m agent. The significance of the switch is the high percentage of dispensed doses for cardiac studies and the higher activities of the Tc-99m agents. A combination of procedural changes and engineering controls (primarily tungsten shielding devices) have been effective in preventing the extremity exposure increase one might expect based on higher activities dispensed per unit dose and the higher energy of Tc-99m compared to Tl-201. One procedural change, the mandatory use of tongs for handling unshielded syringes of radiopharmaceuticals, resulted in a 17% reduction in the average exposure to the extremities

  14. Alexa Fluor-labeled Fluorescent Cellulose Nanocrystals for Bioimaging Solid Cellulose in Spatially Structured Microenvironments

    Energy Technology Data Exchange (ETDEWEB)

    Grate, Jay W.; Mo, Kai-For; Shin, Yongsoon; Vasdekis, Andreas; Warner, Marvin G.; Kelly, Ryan T.; Orr, Galya; Hu, Dehong; Dehoff, Karl J.; Brockman, Fred J.; Wilkins, Michael J.

    2015-03-18

    Cellulose nanocrystal materials have been labeled with modern Alexa Fluor dyes in a process that first links the dye to a cyanuric chloride molecule. Subsequent reaction with cellulose nanocrystals provides dyed solid microcrystalline cellulose material that can be used for bioimaging and suitable for deposition in films and spatially structured microenvironments. It is demonstrated with single molecular fluorescence microscopy that these films are subject to hydrolysis by cellulose enzymes.

  15. ALARA and de minimis concepts in regulation of personnel exposure

    International Nuclear Information System (INIS)

    Baum, J.W.

    1987-01-01

    The ALARA process should not be limited by a de minimis level on either collective or individual dose, but should be limited or defined by an acceptable discount-rate on future costs and effects, and a monetary value for detriment, to be used in cost-effectiveness or cost-benefit calculations at dose levels well below the regulatory limits. This approach would provide the desired benefit of simplifying the decision process, it makes it more cost effective, and would avoid the inconsistencies of limits on only one of the four parameters of importance in the optimization process. These are average individual effective dose equivalent rate, number of individuals to be included in the summation, years of exposure, and costs, which include costs of analysis to reduce the exposure. This approach emphasizes that these doses to an individual may not be considered trivial by society when given to a very large population, especially if they could easily be avoided. 32 refs., 2 tabs

  16. Interpretation of ALARA in the Canadian regulatory framework

    Energy Technology Data Exchange (ETDEWEB)

    Utting, R. [Atomic Energy Control Board, Ottawa, Ontario (Canada)

    1995-03-01

    The Atomic Energy Control Board (AECB) is responsible for the regulation of all aspects of atomic energy in Canada. This includes the complete nuclear fuel cycle from uranium mining to long-term disposal of nuclear fuel, as well as the medical and industrial utilization of radioisotopes. Clearly, the regulatory approach will differ from practice to practice but, as far as possible, the AECB has attempted to minimize the degree of prescription of regulatory requirements. The traditional modus operandi of the AECB has been to have broad general principles enshrined in regulations with the requirement that licensees submit specific operating policies and procedures to the AECB for approval. In the large nuclear facilities with their sophisticated technical infrastructures, this policy has been largely successful although in a changing legal and political milieu the AECB is finding that a greater degree of proactive regulation is becoming necessary. With the smaller users, the AECB has for a long time found it necessary to have a greater degree of prescription in its regulatory function. Forthcoming General Amendments to the Atomic Energy Control Regulations will, amongst other things, formally incorporate the concept of ALARA into the Canadian regulatory framework. Within the broad range of practices licensed by the AECB it is not practical to provide detailed guidance on optimization that will be relevant and appropriate to all licensees, however the following general principles are proposed.

  17. Gambaran Histopatologik Lesi Karies pada Email dengan Aplikasi Fluor In Vitro

    Directory of Open Access Journals (Sweden)

    Agoeng Tjahjani

    2015-11-01

    Full Text Available Tahap dini karies telah lama dikenal dengan istilah bercak putih. Untuk mengetahui terjadinya lesi karies di bawah permukaan email in vivo, maka dilakukan penelitian secara in vitro dengan merendam gigi Premolar dengan dan tanpa aplikasi fluor dalam perbenihan kuman Streptococcus mutans FA-1 (ATCC 16495. Enam puluh empat gigi Preolar tanpa karies dibagi dalam 2 kelompok. Pada kelompok perlakuan, gigi diaplikasi dengan fluor sedang pada kelompok kontrol gigi tanpa aplikasi fluor. Semua gigi dimasukkan dalam perbenihan tioglikolat air yang ke dalamnya telah ditanam Streptococcus mutans FA-4 (ATCC 16495 selama 4 dan 8 minggu. Pembentukan bercah putih diamati dengan mikroskop 'zoom-stereo'. Sedang besarnya porusitas di bawah permukaan email diaamti dengan mikroskop polarisasi. Pada akhir minggu ke-4 dan ke-8 pada kedua kelompok ditemukan peningkatan jumlah gigi dengan pembentukan bercak putih dan peningkatan nilai rata-rata kedalaman lapisan badan lesi. Uji statistik dengan chi-square test menunjukkan perbedaan bermakna pada p<0.05. Berdasarkan penelitian tersebut di atas disimpulkan bahwa (1 aplikasi NaF hanya menghambat sebagian pembentukan lesi karies dan (2 sistem perbenihan kuman yang digunakan tidak dapat mencerminkan keadaan mulut yang sebenarnya.

  18. Application of the ALARA principle to the bleed condenser relief valve replacement project

    International Nuclear Information System (INIS)

    Wong, T.; Kraft, J.

    1997-01-01

    Darlington Nuclear Generating Division's achievements in radiation dose performance can be attributed, in part, to adherence to the ALARA principle. The station's ALARA program, which is an integral part of the safety culture, derives its strength from a strong and unwavering commitment by the site Vice President. This commitment is supported by performance standards and an accountability system which holds managers and supervisors responsible for dose performance. A LAN-based hazard and dose information system with site-wide accessibility was established to facilitate work planning and exposure control. The principle of dose optimization is fully integrated into the work management process and includes work planning, progress monitoring and post-job review. An integrated performance assessment and reporting system also provides timely feedback to management on dose performance. An example of the ALARA program was the bleed condenser relieve valve replacement project. Pre-job ALARA review meetings for the project were held with supervisory staff and technicians to discuss job details and dose reduction measures. All work groups were required to prepare a detailed step be step task safety analysis (TSA). The trades and engineering staff were requested to critique the TSA and suggest ways of reducing dose. Over 30 practical ALARA suggestions were received and adopted for implementation. Daily meetings were held to review job progress and the effectiveness exposure control. A post-job ALARA review was held at the conclusion of each project to obtain feedback and lessons learned. All improvement suggestions were reviewed for implementation during subsequent installations. As a result of the ALARA initiatives, significant dose savings were achieved. The normalized dose expenditure has been reduced from 9.6 rem for the first installation to 6.9 rem for the fourth and last installation. (author)

  19. Hanford spent fuel inventory baseline

    International Nuclear Information System (INIS)

    Bergsman, K.H.

    1994-01-01

    This document compiles technical data on irradiated fuel stored at the Hanford Site in support of the Hanford SNF Management Environmental Impact Statement. Fuel included is from the Defense Production Reactors (N Reactor and the single-pass reactors; B, C, D, DR, F, H, KE and KW), the Hanford Fast Flux Test Facility Reactor, the Shipping port Pressurized Water Reactor, and small amounts of miscellaneous fuel from several commercial, research, and experimental reactors

  20. Lithium-bearing fluor-arfvedsonite from Hurricane Mountain, New Hampshire: A crystal-chemical study

    Science.gov (United States)

    Hawthorne, F.C.; Oberti, R.; Ottolini, L.; Foord, E.E.

    1996-01-01

    The structures of two crystals of Li-bearing fluor-arfvedsonite (1) (K0.32Na0.68)Na2(Li0.48Fe 2+2.83Mn2+0.10Zn 0.06Fe3+1.46Ti0.07) (Si7.88Al0.12)O22[Fu1.15(OH) 0.85] and (2) (K0.25Na0.75)Na2(Li0.48Fe 2+2.84Mn2+0.11Zn 0.05Fe3+1.45Ti0.07)(Si 7.89Al0.11)O22[F1.35(OH) 0.65] from a granitic pegmatite, Hurricane Mountain, New Hampshire, have been refined to R indices of 1.5(1.6)% based on 1380(1387) reflections measured with MoK?? X-radiation. The unit cell parameters are (1) a 9.838(4), b 17.991(6), c 5.315(2) A??, 103.78(3)??, V 913.7 A??3 and (2) a 9.832(3), b 17.990(7), c 5.316(3) A??, ?? 103.79(3)??, V 913.2 A??3. Site-scattering refinement shows Li to be completely ordered at the M(3) site in these crystals. The amphibole composition is intermediate between fluor-arfvedsonite and fluor-ferro-leakeite with a small component (???10%) of fluor-ferro-ferri-nybo??ite. These amphibole crystals project into miarolitic cavities in a pegmatitic phase of a riebeckite granite. The early-crystallizing amphibole is close to fluor-ferro-leakeite in composition, but becomes progressively depleted in Li and F as crystals project out into miarolitic cavities; the final amphibole to crystallize is a fibrous Li-poor riebeckite. Li plays a significant role in late-stage fractionation involving the crystallization of alkali amphibole in peralkaline granitic environments.

  1. Hanford well custodians. Revision 1

    International Nuclear Information System (INIS)

    Schatz, A.L.; Underwood, D.J.

    1995-01-01

    The Hanford Site Groundwater Protection Management Program recognized the need to integrate monitoring well activities in a centralized manner. A key factor to Hanford Site well integration was the need to clearly identify a responsible party for each of the wells. WHC was asked to identify all wells on site, the program(s) using each well, and the program ultimately responsible for the well. This report lists the custodian and user(s) for each Hanford well and supplies a comprehensive list of all decommissioned and orphaned wells on the Hanford Site. This is the first update to the original report released in December 1993

  2. Reinventing government: Reinventing Hanford

    International Nuclear Information System (INIS)

    Mayeda, J.T.

    1994-05-01

    The Hanford Site was established in 1943 as one of the three original Manhattan Project locations involved in the development of atomic weapons. It continued as a defense production center until 1988, when its mission changed to environmental restoration and remediation. The Hanford Site is changing its business strategy and in doing so, is reinventing government. This new development has been significantly influenced by a number of external sources. These include: the change in mission, reduced security requirements, new found partnerships, fiscal budgets, the Tri-Party agreement and stakeholder involvement. Tight budgets and the high cost of cleanup require that the site develop and implement innovative cost saving approaches to its mission. Costeffective progress is necessary to help assure continued funding by Congress

  3. Hanford process review

    International Nuclear Information System (INIS)

    1991-12-01

    This report is a summary of past incidents at the US Department of Energy's (DOE) Hanford Site. The purpose of the report is to provide the major, significant, nuclear-safety-related incidents which incurred at the Hanford Site in a single document for ease of historical research. It should be noted that the last major accident occurred in 1980. This document is a summary of reports released and available to the public in the DOE Headquarters and Richland public reading rooms. This document provides no new information that has not previously been reported. This report is not intended to cover all instances of radioactivity release or contamination, which are already the subject of other major reviews, several of which are referenced in Section 1.3

  4. Hanford Tank Cleanup Update

    International Nuclear Information System (INIS)

    Berriochoa, M.V.

    2011-01-01

    Access to Hanford's single-shell radioactive waste storage tank C-107 was significantly improved when workers completed the cut of a 55-inch diameter hole in the top of the tank. The core and its associated cutting equipment were removed from the tank and encased in a plastic sleeve to prevent any potential spread of contamination. The larger tank opening allows use of a new more efficient robotic arm to complete tank retrieval.

  5. Man-rem audit - a tool for exposure ALARA at Madras Atomic Power Station

    International Nuclear Information System (INIS)

    Shivaramakrishnan, N.R.; Eswaran, G.; Gangamohan, M.; Sathish, A.V.; Ramasubramanian, K.V.; Gandhimathinathan, S.; Selvam, S.; Moolya, L.L.

    2012-01-01

    ALARA - acronym for As Low As Reasonably Achievable, which means making every reasonable effort to maintain exposures to radiation as far below the dose limits as is practical. ICRP has recommended ALARA to be implemented as a formal practice into the System of Dose Limitation, which contains three parts, 1) Justification of practice 2) Optimization 3) Dose Limits. As with the human endeavor, there is always room for improvement. Keeping this in mind, ALARA program is being practiced in our Nuclear Power Plants over the years. There has been a gradual reduction of collective dose in our Nuclear Power Plants due to successful implementation of the ALARA programs. This was possible due to the rigorous application of O and M experience, feedback and active participation of workforce towards ALARA. Furthermore, ALARA is an ongoing continual improvement programme towards collective dose reduction and has enough scope for improvement at any point of time. In order to substantiate the gains of ALARA programme and to improve it further, first time Mam-rem Audit was conducted at MAPS during the month of Sep-Oct 2010. This paper gives the brief outline about the method man-rem audit, its findings, corrective action implementation and the benefits derived from it. Man-rem audit similar to financial audit, serves as a tool for finding out grey areas where improvements is required so that station collective dose can be further optimized. It is one of the identified missions to achieve excellence in area of reducing station collective dose, unplanned exposures and RPP deviation. The scope of this audit is to bring further improvements in the reduction in station collective dose, create more awareness among the employees about ALARA principles and seek valuable suggestions for improvements. Audit team consisting of senior HP persons had one to one interaction with the individuals of the respective section in the field and tried to gather the information from the individual and

  6. Department of Energy ALARA implementation guide. Response to the Health Physics Society

    Energy Technology Data Exchange (ETDEWEB)

    Connelly, J.M. [Dept. of Energy, Washington, DC (United States)

    1995-03-01

    In the August 1993 Health Physics Society (HPS) newsletter, the HPS Scientific and Public Issues Committee published a Position Statement entitled {open_quotes}Radiation Protection of the Public and the Environment.{close_quotes}. In this article, this HPS committee made the statement that they were deeply concerned by the trend for agencies to incorporate the ALARA concept as a regulatory requirements, without providing specific guidance as to what it means and how to implement it consistently. The HPS position paper was in response to the DOE notice on proposed rulemaking for Title 10 Code of Federal Regulations Part 834, {open_quotes}Radiation Protection of the Public and the Environment{close_quotes} (10 CFR 834). In the notice of proposed rulemaking for 10 CFR 834, the Department of Energy (DOE) defined ALARA as follows: {open_quotes}As used in this part, ALARA is not a dose limit, but rather a process which has the objective of attaining doses as far below the applicable limit of this part as is reasonably achievable{close_quotes} (10 CFR 834.2, p. 16283 of the Federal Register). The HPS position paper continues, {open_quotes}The section goes on to elaborate on what is meant by a process without providing sufficient guidance to assure uniform applicability of the process.{close_quotes}. Although this concern is directed towards the ALARA process as it relates to the environment, the Office of Health, which is responsible for occupational workers, shares the same definition for ALARA.

  7. PROGRESS WITH K BASINS SLUDGE RETRIEVAL STABILIZATION & PACKAGING AT THE HANFORD NUCLEAR SITE

    Energy Technology Data Exchange (ETDEWEB)

    KNOLLMEYER, P.M.; PHILLIPS, C; TOWNSON, P.S.

    2006-01-30

    This paper shows how Fluor Hanford and BNG America have combined nuclear plant skills from the U.S. and the U.K. to devise methods to retrieve and treat the sludge that has accumulated in K Basins at the Hanford Site over many years. Retrieving the sludge is the final stage in removing fuel and sludge from the basins to allow them to be decontaminated and decommissioned, so as to remove the threat of contamination of the Columbia River. A description is given of sludge retrieval using vacuum lances and specially developed nozzles and pumps into Consolidation Containers within the basins. The special attention that had to be paid to the heat generation and potential criticality issues with the irradiated uranium-containing sludge is described. The processes developed to re-mobilize the sludge from the Consolidation Containers and pump it through flexible and transportable hose-in-hose piping to the treatment facility are explained with particular note made of dealing with the abrasive nature of the sludge. The treatment facility, housed in an existing Hanford building, is described, and the uranium-corrosion and grout packaging processes explained. The uranium corrosion process is a robust, tempered process very suitable for dealing with a range of differing sludge compositions. Optimization and simplification of the original sludge corrosion process design is described and the use of transportable and reusable equipment is indicated. The processes and techniques described in the paper are shown to have wide applicability to nuclear cleanup.

  8. Pacific Northwest Laboratory ALARA report for Calendar Year 1994

    International Nuclear Information System (INIS)

    Keller, S.L.

    1995-08-01

    This report provides summary results of the Calendar Year (CY) 1994 As Low As Reasonably Achievable (ALARA) Program performance at the Pacific Northwest Laboratory (PNL). This report includes data regarding performance in the area of personnel exposures to radiation, skin contaminations, control of contaminated areas, minimization of radioactive waste, and control of radioactive releases. In CY 1994: (1) The collective total effective dose equivalent to PNL employees during 1994 was 55 person-rem. The Field Dosimetry Services of the Radiological Control Department, Technical Support Section, projected that no PNL employee's dose would exceed 2 rem based on dosimeters processed during the year; no worker actually exceeded the projection-by the end of CY 1994. The maximum dose to any individual was 1.11 rem. (2) There were 34 instances of skin and personal-clothing contamination events for PNL employees during 1994. Eighteen of these contamination events occurred at the 324 Building; eleven occurred at the 325 Building; two occurred in the 327 Building; one occurred in the 326 Building; one occurred in the 3708 Building; and one occurred in the RTL Building. (3) PNL facilities contained 12 Airborne Radioactivity Areas, and 60 Contamination Areas and High Contamination Areas. The area of the Airborne Radioactivity Areas was 383 m 2 (4125 ft 2 ). The area of the Contamination Areas was 5290 m 2 (56,947 ft 2 ). The area of the High Contamination Areas was 266 m 2 (2863 ft 2 ). (4) PNL disposed of 10.5 m 3 (371 ft 3 ) of compacted low level waste. Also disposed was 423 m 3 (14,949 ft 3 ) of noncompacted low level and mixed waste that was not subject to volume reduction. The total radioactivity of the disposed waste was 1217 Ci. (5) PNL facilities released 165.2 Ci of noble gas, 3.0E-5 Ci of airborne particulate radioactive material, and 12.2 Ci of tritium to the environment

  9. ALARA and decommissioning: The Fort St. Vrain experience

    Energy Technology Data Exchange (ETDEWEB)

    Borst, T.; Niehoff, M. [Public Service Co. of Colorado, Platteville, CO (United States); Zachary, M. [Scientific Ecology Group, Platteville, CO (United States)

    1995-03-01

    The Fort St. Vrain Nuclear Generating Station, the first and only commercial High Temperature Gas Cooled Reactor to operate in the United States, completed initial fuel loading in late 1973 and initial startup in early 1974. Due to a series of non-nuclear technical problems, Fort St. Vrain never operated consistently, attaining a lifetime capacity factor of slightly less than 15%. In August of 1989, the decision was made to permanently shut down the plant due to control rod drive and steam generator ring header failures. Public Service Company of Colorado elected to proceed with early dismantlement (DECON) as opposed to SAFSTOR on the bases of perceived societal benefits, rad waste, and exposure considerations, regulatory uncertainties associated with SAFSTOR, and cost. The decommissioning of Fort St. Vrain began in August of 1992, and is scheduled to be completed in early 1996. Decommissioning is being conducted by a team consisting of Westinghouse, MK-Ferguson, and Scientific Ecology Group. Public Service Company of Colorado as the licensee provides contract management and oversight of contractor functions. An aggressive program to maintain project radiation exposures As Low As Reasonably Achievable (ALARA) has been established, with the following program elements: temporary and permanent shielding contamination control; mockup training; engineering controls; worker awareness; integrated work package reviews communication; special instrumentation; video camera usage; robotics application; and project committees. To date, worker exposures have been less than project estimates. from the start of the project through Februrary of 1994, total exposure has been 98.666 person-rem, compared to the project estimate of 433 person-rem and goal of 347 person-rem. The presentation will discuss the site characterization efforts, the radiological performance indicator program, and the final site release survey plans.

  10. Mortality studies of Hanford workers

    International Nuclear Information System (INIS)

    Gilbert, E.S.

    1986-04-01

    Radiation exposures at Hanford have been deliberately limited as a protection to the worker. This means that if current estimates of radiation risks, which have been determined by national and international groups, are correct, it's highly unlikely that noticeable radiation-induced health effects will be identified among Hanford workers. 1 fig., 4 tabs

  11. ALARA radiation protection applications at NPP A1 decommissioning using VISPLAN planning tool

    International Nuclear Information System (INIS)

    Slavik, O.; Kucharova, D.; Listjak, M.

    2005-01-01

    The SCK.CEN developed during the BR3 reactor decommissioning a graphical interfaced 3D dose assessment tool aimed at the above mentioned dose optimization problems. The tool was improved further and commercialized under the name VISIPLAN 3D ALARA planning tool. The use of VISIPLAN tool at NPP A1 decommissioning was advised by EDF within the IAEA TCP SLR/4008 project missions as a component of a 3D technological chain ensuring acquisition and evaluation of digitized information leading to ALARA optimisation of the developed decommissioning working procedures (see Fig. 1). VISIPLAN license was purchased by IAEA and granted to VUJE and NPP A1 within the IAEA TCP project SLR/4008, covering also the necessary basic and advanced training (at NPP A1 real decommissioning environment), and is currently used by VUJE analysts at NPP A1 decommissioning as an ALARA tool for intervention planning and optimisation. The VISIPLAN allows a fast dose assessment for work planned in a radioactive environment. The calculations are based on a 3D model of the work place. This PC-based tool is user friendly and calculates a detailed dose account for different work scenarios defined by the ALARA analyst, taking into account worker position, work duration and subsequent geometry and source distribution changes. The VISIPLAN methodology is described. The VISIPLAN tool was applied to several ALARA studies carried out by the VUJE within development and analysis of various Work Programs for NPP Al decommissioning tasks. The applications ranged from simpler to complex ALARA planning tasks covering simple shielding applications to selection of the most suitable order of complex working procedures. Removal of inner liners from underground reservoirs 6/1 and 6/2 as well as Dismantling of pipes and components from a (hostile) 60 m corridor are described. (authors)

  12. Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants

    International Nuclear Information System (INIS)

    Khan, T.A.; Roecklein, A.K.

    1995-03-01

    This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately

  13. ALARA Review for the Deactivation of the 107-N Pump Well

    International Nuclear Information System (INIS)

    Edwards, T.A.

    1998-01-01

    This as low as reasonably achievable (ALARA) review provides a description of the engineering and administrative controls used during the completion of deactivation work at the 107-N Building. This ALARA assessment focuses on the 107-N Building pump well. The level of contamination found in the pump well has been estimated to be approximately 830 mRad/hr beta and 680,000 disintegrations per minute (dpm) alpha per large area wipe. As part of the characterization of the water and sediment, samples were taken to determine the isotopic distribution

  14. Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A. [comp.] [Brookhaven National Lab., Upton, NY (United States); Roecklein, A.K. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications

    1995-03-01

    This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately.

  15. Hanford tanks initiative plan

    International Nuclear Information System (INIS)

    McKinney, K.E.

    1997-01-01

    Abstract: The Hanford Tanks Initiative (HTI) is a five-year project resulting from the technical and financial partnership of the U.S. Department of Energy's Office of Waste Management (EM-30) and Office of Science and Technology Development (EM-50). The HTI project accelerates activities to gain key technical, cost performance, and regulatory information on two high-level waste tanks. The HTI will provide a basis for design and regulatory decisions affecting the remainder of the Tank Waste Remediation System's tank waste retrieval Program

  16. Westinghouse Hanford Company health and safety performance report

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, L.

    1996-05-15

    Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% from the CY 1995 rate of 1.03 (page 2-8). The

  17. Westinghouse Hanford Company health and safety performance report

    International Nuclear Information System (INIS)

    Rogers, L.

    1996-01-01

    Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% from the CY 1995 rate of 1.03 (page 2-8). The

  18. Hanford inventory program user's manual

    International Nuclear Information System (INIS)

    Hinkelman, K.C.

    1994-01-01

    Provides users with instructions and information about accessing and operating the Hanford Inventory Program (HIP) system. The Hanford Inventory Program is an integrated control system that provides a single source for the management and control of equipment, parts, and material warehoused by Westinghouse Hanford Company in various site-wide locations. The inventory is comprised of spare parts and equipment, shop stock, special tools, essential materials, and convenience storage items. The HIP replaced the following systems; ACA, ASP, PICS, FSP, WSR, STP, and RBO. In addition, HIP manages the catalog maintenance function for the General Supplies inventory stocked in the 1164 building and managed by WIMS

  19. Occupational dose reduction at Department of Energy contractor facilities: Study of ALARA programs

    International Nuclear Information System (INIS)

    Dionne, B.J.; Meinhold, C.B.; Khan, T.A.; Baum, J.W.

    1992-03-01

    This report provides the US Department of Energy (DOE) and its contractors with information that will be useful for reducing occupational radiation doses at DOE's nuclear facilities. In 1989 and 1990, health physicists from the Brookhaven National Laboratory's (BNL) ALARA Center visited twelve DOE contractor facilities with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). The health physicists interviewed radiological safety staff, engineers, and training personnel who were responsible for dose control. The status of ALARA practices at the major contractor facilities was compared with the requirements and recommendation in DOE Order 5480.11 ''Radiation Protection for Occupational Workers'' and PNL-6577 ''Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are as Low as Reasonably Achievable.'' The information and data collected are described and examples of successful practices are presented. The findings on the status of the DOE Contractor ALARA Programs are summarized and evaluated. In addition, the supplement to this report contains examples of good-practice documents associated with implementing the major elements of a formally documented ALARA program for a major DOE contractor facility

  20. Radiation protection-culture. Culture improvement in radiation protection and ALARA behaviour

    International Nuclear Information System (INIS)

    Boehler, M.C.

    1994-12-01

    In order to that the optimization principle become an actual professional liable dynamical critter in the radiological protection topics, the hierarchic impulse and the personnel sensitiveness are determining. The ALARA (As Low As Reasonably Achievable) in the firm cultivation modify the behaviour and act philosophy. 7 refs., 2 figs

  1. ALARA cost/benefit analysis at Union Electric company using the ARP/AI methodology

    International Nuclear Information System (INIS)

    Williams, M.C.

    1987-01-01

    This paper describes the development of a specific method for justification of expenditures associated with reducing occupational radiation exposure to as low as reasonably achievable (ALARA). This methodology is based on the concepts of the Apparebt Reduction Potential (ARP) and Achievability index (AI) as described in NUREG/CR-0446, Union Eletric's corporate planning model and the EPRI Model for dose rate buildup with reactor operating life. The ARP provides a screening test to determine if there is a need for ALARA expenditures based on actual or predicted exposure rates and/or dose experience. The AI is a means of assessing all costs and all benefits, even though they are expressed in different units of measurement such as person-rem and dollars, to determine if ALARA expenditures are justified and their value. This method of cost/benefit analysis can be applied by any company or organization utilizing site-specific exposure and dose rate data, and incorporating consideration of administrative exposure controls which may vary from organization to organization. Specific example cases are presented and compared to other methodologies for ALARA cost/benefit analysis

  2. The Evaluation of personnel radiation dose and society radiation on RSG-GAS around as proposal determination of ALARA value

    International Nuclear Information System (INIS)

    Pande Made Udiyani; Puradwi IW

    2007-01-01

    Each nuclear installation to achieve radiation safety has to meet the ALARA concepts. The ALARA value of a nuclear installation should be enacted by regulator body. ALARA value can be determined by evaluation radiation exposure and dose acceptance of nuclear installation operation. As case study in Indonesia, ALARA assessment in nuclear installation is done at RSG-GAS reactor. Intention of this research is to determine gyration reference assess ALARA by evaluate radiation dose acceptance by RSG-GAS radiation personnel and the influence of RSG-GAS operation to presentation of radiation accepted by society which living around its. ALARA of RSG-GAS determined based on evaluation of measurement data of the radiation doses which is accepted by personnel radiation. While evaluation of radiation doses which is accepted by society in the radius 5 km of the RSG-GAS conducted to data result of calculation using program package of CAP-88 and measurement result with method of carborne survey. Result of radiation dose evaluation obtained which not pass dose definition for the radiation worker that is 50 mSv/year, and for society around RSG-GAS that is 5 mSv/year. Based on the result of evaluation hence obtained value of ALARA for RSG-GAS in value of gyration 17 - 50 mSv/year. (author)

  3. Just in Time DSA-The Hanford Nuclear Safety Basis Strategy

    International Nuclear Information System (INIS)

    Olinger, S. J.; Buhl, A. R.

    2002-01-01

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD and D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD and D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex

  4. Just in Time DSA-The Hanford Nuclear Safety Basis Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Olinger, S. J.; Buhl, A. R.

    2002-02-26

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

  5. Health physics manual of good practices for reducing radiation exposure to levels that are as low as reasonably achievable (ALARA)

    International Nuclear Information System (INIS)

    Herrington, W.N.; Higby, D.P.; Kathren, R.L.; Merwin, S.E.; Stoetzel, G.A.

    1988-06-01

    A primary objective of the US Department of Energy (DOE) health physics and radiation protection program has been to limit radiation exposures to those levels that are as low as reasonably achievable (ALARA). As a result, the ALARA concept developed into a program and a set of operational principles to ensure that the objective was consistently met. Implementation of these principles required that a guide be produced. The original ALARA guide was issued by DOE in 1980 to promote improved understanding of ALARA concepts within the DOE community and to assist those responsible for operational ALARA activities in attaining their goals. Since 1980, additional guidance has been published by national and international organizations to provide further definition and clarification to ALARA concepts. As basic ALARA experience increased, the value and role of the original guide prompted the DOE Office of Nuclear Safety (ONS) to support a current revision. The revised manual of good practices includes six sections: 1.0 Introduction, 2.0 Administration, 3.0 Optimization, 4.0 Setting and Evaluating ALARA Goals, 5.0 Radiological Design, and 6.0 Conduct of Operations. The manual is directed primarily to contractor and DOE staff who are responsible for conduct and overview of radiation protection and ALARA programs at DOE facilities. The intent is to provide sufficient guidance such that the manual, if followed, will ensure that radiation exposures are maintained as low as reasonably achievable and will establish the basis for a formally structured and auditable program. 118 refs., 16 figs., 3 tabs

  6. Hanford Site Environmental Report 1993

    Energy Technology Data Exchange (ETDEWEB)

    Dirkes, R.L.; Hanf, R.W.; Woodruff, R.K. [eds.

    1994-06-01

    The Hanford Site Environmental Report is prepared annually to summarize environmental data and information, describe environmental management performance, and demonstrate the status of compliance with environmental regulations. The report also highlights major environmental programs and efforts. The report is written to meet reporting requirements and Guidelines of the U.S. Department of Energy (DOE) an to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to (a) describe the Hanford Site and its mission, (b) summarize the status in 1993 of compliance with environmental regulations, (c) describe the environmental programs at the Hanford Site, (d) discuss estimated radionuclide exposure to the public from 1993 Hanford activities, (e) present information on effluent monitoring and environmental surveillance, including ground-water protection and monitoring, (f) discuss activities to ensure quality. More detailed information can be found in the body of the report, the appendixes, and the cited references.

  7. Introduction to the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report discusses the Site mission and provides general information about the site. The U.S. DOE has established a new mission for Hanford including: Management of stored wastes, environmental restoration, research and development, and development of new technologies. The Hanford Reservation is located in south central Washington State just north of the confluence of the Snake and Yakima Rivers with the Columbia River. The approximately 1,450 square kilometers which comprises the Hanford Site, with restricted public access, provides a buffer for the smaller areas within the site which have historically been used for the production of nuclear materials, radioactive waste storage, and radioactive waste disposal.

  8. Hanford Site Environmental Report 1993

    International Nuclear Information System (INIS)

    Dirkes, R.L.; Hanf, R.W.; Woodruff, R.K.

    1994-06-01

    The Hanford Site Environmental Report is prepared annually to summarize environmental data and information, describe environmental management performance, and demonstrate the status of compliance with environmental regulations. The report also highlights major environmental programs and efforts. The report is written to meet reporting requirements and Guidelines of the U.S. Department of Energy (DOE) an to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to (a) describe the Hanford Site and its mission, (b) summarize the status in 1993 of compliance with environmental regulations, (c) describe the environmental programs at the Hanford Site, (d) discuss estimated radionuclide exposure to the public from 1993 Hanford activities, (e) present information on effluent monitoring and environmental surveillance, including ground-water protection and monitoring, (f) discuss activities to ensure quality. More detailed information can be found in the body of the report, the appendixes, and the cited references

  9. Hanford Site Environmental Report 1999

    International Nuclear Information System (INIS)

    Poston, TM; Hanf, RW; Dirkes, RL

    2000-01-01

    This Hanford Site environmental report is prepared annually to summarize environmental data and information, to describe environmental management performance, to demonstrate the status of compliance with environmental regulations, and to highlight major environmental programs and efforts. The report is written to meet requirements and guidelines of the U.S. Department of Energy (DOE) and to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to: (1) describe the Hanford Site and its mission; (2) summarize the status of compliance with environmental regulations; (3) describe the environmental programs at the Hanford Site; (4) discuss the estimated radionuclide exposure to the public from 1999 Hanford Site activities; (5) present the effluent monitoring, environmental surveillance, groundwater protection and monitoring information; and (6) discuss the activities to ensure quality

  10. Introduction to the Hanford Site

    International Nuclear Information System (INIS)

    Cushing, C.E.

    1995-01-01

    This section of the 1994 Hanford Site Environmental Report discusses the Site mission and provides general information about the site. The U.S. DOE has established a new mission for Hanford including: Management of stored wastes, environmental restoration, research and development, and development of new technologies. The Hanford Reservation is located in south central Washington State just north of the confluence of the Snake and Yakima Rivers with the Columbia River. The approximately 1,450 square kilometers which comprises the Hanford Site, with restricted public access, provides a buffer for the smaller areas within the site which have historically been used for the production of nuclear materials, radioactive waste storage, and radioactive waste disposal

  11. Hanford Facility RCRA permit handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    Purpose of this Hanford Facility (HF) RCRA Permit Handbook is to provide, in one document, information to be used for clarification of permit conditions and guidance for implementing the HF RCRA Permit.

  12. Hanford Surplus Facilities Program plan

    International Nuclear Information System (INIS)

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

    1989-09-01

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

  13. Mortality studies of Hanford workers

    International Nuclear Information System (INIS)

    Gilbert, E.S.

    1986-03-01

    The relationships of cancer mortality with radiation exposure as influenced by age, sex, follow-up time length of employment, and job category are discussed in relation to workers at the Hanford facilities

  14. Hanford Waste Management Plan, 1987

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of the Hanford Waste Management Plan (HWMP) is to provide an integrated plan for the safe storage, interim management, and disposal of existing waste sites and current and future waste streams at the Hanford Site. The emphasis of this plan is, however, on the disposal of Hanford Site waste. The plans presented in the HWMP are consistent with the preferred alternative which is based on consideration of comments received from the public and agencies on the draft Hanford Defense Waste Environmental Impact Statement (HDW-EIS). Low-level waste was not included in the draft HDW-EIS whereas it is included in this plan. The preferred alternative includes disposal of double-shell tank waste, retrievably stored and newly generated TRU waste, one pre-1970 TRU solid waste site near the Columbia River and encapsulated cesium and strontium waste

  15. Hanford site waste tank characterization

    International Nuclear Information System (INIS)

    De Lorenzo, D.S.; Simpson, B.C.

    1994-08-01

    This paper describes the on-going work in the characterization of the Hanford-Site high-level waste tanks. The waste in these tanks was produced as part of the nuclear weapons materials processing mission that occupied the Hanford Site for the first 40 years of its existence. Detailed and defensible characterization of the tank wastes is required to guide retrieval, pretreatment, and disposal technology development, to address waste stability and reactivity concerns, and to satisfy the compliance criteria for the various regulatory agencies overseeing activities at the Hanford Site. The resulting Tank Characterization Reports fulfill these needs, as well as satisfy the tank waste characterization milestones in the Hanford Federal Facility Agreement and Consent Order

  16. Hanford Site 1998 Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    RL Dirkes; RW Hanf; TM Poston

    1999-09-21

    This Hanford Site environmental report is prepared annually to summarize environmental data and information, to describe environmental management performance, to demonstrate the status of compliance with environmental regulations, and to highlight major environmental programs and efforts. The report is written to meet requirements and guidelines of the U.S. Department of Energy (DOE) and to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to: describe the Hanford Site and its mission; summarize the status of compliance with environmental regulations; describe the environmental programs at the Hanford Site; discuss the estimated radionuclide exposure to the public from 1998 Hanford Site activities; present the effluent monitoring, environmental surveillance, and groundwater protection and monitoring information; and discuss the activities to ensure quality.

  17. Hanford Site Environmental Report 1999

    Energy Technology Data Exchange (ETDEWEB)

    TM Poston; RW Hanf; RL Dirkes

    2000-09-28

    This Hanford Site environmental report is prepared annually to summarize environmental data and information, to describe environmental management performance, to demonstrate the status of compliance with environmental regulations, and to highlight major environmental programs and efforts. The report is written to meet requirements and guidelines of the U.S. Department of Energy (DOE) and to meet the needs of the public. This summary has been written with a minimum of technical terminology. Individual sections of the report are designed to: (1) describe the Hanford Site and its mission; (2) summarize the status of compliance with environmental regulations; (3) describe the environmental programs at the Hanford Site; (4) discuss the estimated radionuclide exposure to the public from 1999 Hanford Site activities; (5) present the effluent monitoring, environmental surveillance, groundwater protection and monitoring information; and (6) discuss the activities to ensure quality.

  18. The isotope-dilution method of fluorine microestimation; Microdosage du fluor pur dilution isotopique; Mikroopredelenie ftora no metodu razbavleniya izotopov; Microvaloracion del fluor por dilucion isotopica

    Energy Technology Data Exchange (ETDEWEB)

    Kudahl, J N; Fremlin, J H; Hardwick, J L [Department of Physics, University of Birmingham (United Kingdom)

    1962-01-15

    Fluoride ions are adsorbed on glass from acid solution and, for solutions containing less than 100 ppm of fluorine, the amount adsorbed varies very regularly with concentration. A certain volume of a carrier-free solution of the unstable isotope F{sup 18} is added to each of a set of acid fluoride solutions which may be a few milligrams, or less, in size. If the solutions are applied to a defined area of glass, some of the F{sup 18} is adsorbed and this can be fixed by raising the pH when equilibrium has been reached. The radioactivity of the glass is a measure of the total amount of fluoride on the glass and can be used to draw an adsorption isotherm from which the fluorine content of an unknown solution in the set can be found. The effects of pH, and the presence of calcium and phosphate ions have been studied, and it has been shown that organic materials may be ashed safely if calcium or magnesium ions are present. The accuracy of the method is independent of the fluoride concentration down to concentrations of a fraction of a ppm. (author) [French] L'ion de fluorure d'une solution acide est adsorbe sur du verre; pour des solutions contenant moins de 100 ppm de fluor, la quantite adsorbee varie tres regulierement en fonction de la concentration. Un certain volume d'une solution, sans entraineur-, de l'isotope instable {sup 18}F est ajoute a une serie de solutions acides de fluorure; il peut s'agir de quantites de l'ordre de quelques milligrammes, ou meme moins. Si l'on applique les solutions sur une surface bien definie de verre, une partie du {sup 18}F est adsorbee; on peut la fixer en augmentant le pH des que l'equilibre a ete realise. La radioactivite du verre donne la mesure de la quantite totale de fluorure fixe sur le verre; elle peut servir a etablir l'isotherme d'adsorption, dont en peut deduire la teneur en fluor de toute solution de la serie. Les auteurs ont etudie les effets du pH et la presence d'ions de calcium et de magnesium; ils ont montre que

  19. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Cannon, S.D.; Finch, S.M.

    1992-10-01

    The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The independent Technical Steering Panel (TSP) provides technical direction. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed from release to impact on humans (dose estimates):Source Terms, Environmental Transport, Environmental Monitoring Data, Demography, Food Consumption, and Agriculture, and Environmental Pathways and Dose Estimates

  20. HANFORD WASTE MINEROLOGY REFERENCE REPORT

    International Nuclear Information System (INIS)

    Disselkamp, R.S.

    2010-01-01

    This report lists the observed mineral phases present in the Hanford tanks. This task was accomplished by performing a review of numerous reports using experimental techniques including, but not limited to: x-ray diffraction, polarized light microscopy, scanning electron microscopy, transmission electron microscopy, energy dispersive spectroscopy, electron energy loss spectroscopy, and particle size distribution analyses. This report contains tables that can be used as a quick reference to identify the crystal phases present observed in Hanford waste.

  1. HANFORD WASTE MINERALOGY REFERENCE REPORT

    Energy Technology Data Exchange (ETDEWEB)

    DISSELKAMP RS

    2010-06-29

    This report lists the observed mineral phases present in the Hanford tanks. This task was accomplished by performing a review of numerous reports that used experimental techniques including, but not limited to: x-ray diffraction, polarized light microscopy, scanning electron microscopy, transmission electron microscopy, energy dispersive spectroscopy, electron energy loss spectroscopy, and particle size distribution analyses. This report contains tables that can be used as a quick reference to identify the crystal phases observed in Hanford waste.

  2. HANFORD WASTE MINEROLOGY REFERENCE REPORT

    Energy Technology Data Exchange (ETDEWEB)

    DISSELKAMP RS

    2010-06-18

    This report lists the observed mineral phase phases present in the Hanford tanks. This task was accomplished by performing a review of numerous reports using experimental techniques including, but not limited to: x-ray diffraction, polarized light microscopy, scanning electron microscopy, transmission electron microscopy, energy dispersive spectroscopy, electron energy loss spectroscopy, and particle size distribution analyses. This report contains tables that can be used as a quick reference to identify the crystal phases present observed in Hanford waste.

  3. Hanford Waste Mineralogy Reference Report

    International Nuclear Information System (INIS)

    Disselkamp, R.S.

    2010-01-01

    This report lists the observed mineral phases present in the Hanford tanks. This task was accomplished by performing a review of numerous reports that used experimental techniques including, but not limited to: x-ray diffraction, polarized light microscopy, scanning electron microscopy, transmission electron microscopy, energy dispersive spectroscopy, electron energy loss spectroscopy, and particle size distribution analyses. This report contains tables that can be used as a quick reference to identify the crystal phases observed in Hanford waste.

  4. Hanford internal dosimetry program manual

    International Nuclear Information System (INIS)

    Carbaugh, E.H.; Sula, M.J.; Bihl, D.E.; Aldridge, T.L.

    1989-10-01

    This document describes the Hanford Internal Dosimetry program. Program Services include administrating the bioassay monitoring program, evaluating and documenting assessments of internal exposure and dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating internal radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. 13 refs., 16 figs., 42 tabs

  5. Proposal of organisation and ALARA procedures for maintenance site: application to replacement of steam generator; Propositions d'organisation et procedures ALARA pour la preparation des chantiers de maintenance: application au RGV

    Energy Technology Data Exchange (ETDEWEB)

    Lochard, J; Lefaure, C

    1989-08-01

    This report proposes generic organization and ALARA procedures for preparing a maintenance site at a NPP. After a short description of the ALARA principle, it describes the proposition for French sites. They are grouped according to the following: motivation, organisation, means. They are illustrated by the example of steam generator replacement. Three special points concerning preparation of the site are developed: education; training of operators; review of the project.

  6. Managing the process for storage and disposal of immobilized high- and low-level tank waste at the Hanford Site

    International Nuclear Information System (INIS)

    Murkowski, R.J.

    1998-01-01

    Lockheed Martin Hanford Corporation (LMHC) is one of six subcontractors under Fluor Daniel Hanford, Inc., the Management and Integration contractor for the Project Hanford Management Contract working for the US Department of Energy. One of LMHC's responsibilities is to prepare storage and disposal facilities to receive immobilized high and low-level tank waste by June of 2002. The immobilized materials are to be produced by one or more vendors working under a privatization contract. The immobilized low-activity waste is to be permanently disposed of at the Hanford Site while the immobilized high-level waste is to be stored at the Hanford Site while awaiting shipment to the offsite repository. Figure 1 is an overview of the entire cleanup mission with the disposal portion of the mission. Figure 2 is a representation of major activities required to complete the storage and disposal mission. The challenge for the LNIHC team is to understand and plan for accepting materials that are described in the Request for Proposal. Private companies will submit bids based on the Request for Proposal and other Department of Energy requirements. LMHC, however, must maintain sufficient flexibility to accept modifications that may occur during the privatization bid/award process that is expected to be completed by May 1998. Fundamental to this planning is to minimize the risks of stand-by costs if storage and disposal facilities are not available to receive the immobilized waste. LMHC has followed a rigorous process for the identification of the functions and requirements of the storage/disposal facilities. A set of alternatives to meet these functions and requirements were identified and evaluated. The alternatives selected were (1) to modify four vaults for disposal of immobilized low-activity waste, and (2) to retrofit a portion of the Canister Storage Building for storage of immobilized high-level waste

  7. Women and the Hanford Site

    Science.gov (United States)

    Gerber, Michele

    2014-03-01

    When we study the technical and scientific history of the Manhattan Project, women's history is sometimes left out. At Hanford, a Site whose past is rich with hard science and heavy construction, it is doubly easy to leave out women's history. After all, at the World War II Hanford Engineer Works - the earliest name for the Hanford Site - only nine percent of the employees were women. None of them were involved in construction, and only one woman was actually involved in the physics and operations of a major facility - Dr. Leona Woods Marshall. She was a physicist present at the startup of B-Reactor, the world's first full-scale nuclear reactor - now a National Historic Landmark. Because her presence was so unique, a special bathroom had to be built for her in B-Reactor. At World War II Hanford, only two women were listed among the nearly 200 members of the top supervisory staff of the prime contractor, and only one regularly attended the staff meetings of the Site commander, Colonel Franklin Matthias. Overall, women comprised less than one percent of the managerial and supervisory staff of the Hanford Engineer Works, most of them were in nursing or on the Recreation Office staff. Almost all of the professional women at Hanford were nurses, and most of the other women of the Hanford Engineer Works were secretaries, clerks, food-service workers, laboratory technicians, messengers, barracks workers, and other support service employees. The one World War II recruiting film made to attract women workers to the Site, that has survived in Site archives, is entitled ``A Day in the Life of a Typical Hanford Girl.'' These historical facts are not mentioned to criticize the past - for it is never wise to apply the standards of one era to another. The Hanford Engineer Works was a 1940s organization, and it functioned by the standards of the 1940s. Just as we cannot criticize the use of asbestos in constructing Hanford (although we may wish they hadn't used so much of it), we

  8. Hanford Site Transuranic (TRU) Waste Certification Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP

  9. Hanford Site Transuranic (TRU) Waste Certification Plan

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    1999-09-09

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

  10. Hanford Site peak gust wind speeds

    International Nuclear Information System (INIS)

    Ramsdell, J.V.

    1998-01-01

    Peak gust wind data collected at the Hanford Site since 1945 are analyzed to estimate maximum wind speeds for use in structural design. The results are compared with design wind speeds proposed for the Hanford Site. These comparisons indicate that design wind speeds contained in a January 1998 advisory changing DOE-STD-1020-94 are excessive for the Hanford Site and that the design wind speeds in effect prior to the changes are still appropriate for the Hanford Site

  11. Hanford Sitewide Groundwater Remediation Strategy

    International Nuclear Information System (INIS)

    Knepp, A.J.; Isaacs, J.D.

    1997-09-01

    This document fulfills the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-13-81, to develop a concise statement of strategy that describe show the Hanford Site groundwater remediation will be accomplished. The strategy addresses objectives and goals, prioritization of activities, and technical approaches for groundwater cleanup. The strategy establishes that the overall goal of groundwater remediation on the Hanford Site is to restore groundwater to its beneficial uses in terms of protecting human health and the environment, and its use as a natural resource. The Hanford Future Site Uses Working Group established two categories for groundwater commensurate with various proposed landuses: (1) restricted use or access to groundwater in the Central Plateau and in a buffer zone surrounding it and (2) unrestricted use or access to groundwater for all other areas. In recognition of the Hanford Future Site Uses Working Group and public values, the strategy establishes that the sitewide approach to groundwater cleanup is to remediate the major plumes found in the reactor areas that enter the Columbia River and to contain the spread and reduce the mass of the major plumes found in the Central Plateau

  12. The Hanford Site focus, 1994

    International Nuclear Information System (INIS)

    Peterson, J.M.

    1994-03-01

    This report describes what the Hanford Site will look like in the next two years. We offer thumbnail sketches of Hanford Site programs and the needs we are meeting through our efforts. We describe our goals, some recent accomplishments, the work we will do in fiscal year (FY) 1994, the major activities the FY 1995 budget request covers, and the economic picture in the next few years. The Hanford Site budget shows the type of work being planned. US Department of Energy (DOE) sites like the Hanford Site use documents called Activity Data Sheets to meet this need. These are building blocks that are included in the budget. Each Activity Data Sheet is a concise (usually 4 or 5 pages) summary of a piece of work funded by the DOE's Environmental Restoration and Waste Management budget. Each sheet describes a waste management or environmental restoration need over a 5-year period; related regulatory requirements and agreements; and the cost, milestones, and steps proposed to meet the need. The Hanford Site is complex and has a huge budget, and its Activity Data Sheets run to literally thousands of pages. This report summarizes the Activity Data Sheets in a less detailed and much more reader-friendly fashion

  13. Interim Hanford Waste Management Plan

    International Nuclear Information System (INIS)

    1985-09-01

    The September 1985 Interim Hanford Waste Management Plan (HWMP) is the third revision of this document. In the future, the HWMP will be updated on an annual basis or as major changes in disposal planning at Hanford Site require. The most significant changes in the program since the last release of this document in December 1984 include: (1) Based on studies done in support of the Hanford Defense Waste Environmental Impact Statement (HDW-EIS), the size of the protective barriers covering contaminated soil sites, solid waste burial sites, and single-shell tanks has been increased to provide a barrier that extends 30 m beyond the waste zone. (2) As a result of extensive laboratory development and plant testing, removal of transuranic (TRU) elements from PUREX cladding removal waste (CRW) has been initiated in PUREX. (3) The level of capital support in years beyond those for which specific budget projections have been prepared (i.e., fiscal year 1992 and later) has been increased to maintain Hanford Site capability to support potential future missions, such as the extension of N Reactor/PUREX operations. The costs for disposal of Hanford Site defense wastes are identified in four major areas in the HWMP: waste storage and surveillance, technology development, disposal operations, and capital expenditures

  14. Lessons learned in planning ALARA/health physics support for major nuclear power plant outages

    International Nuclear Information System (INIS)

    Gilman, T.R.; Lesinski, M.L.

    1987-01-01

    Although as low as reasonably achievable (ALARA)/health physics is viewed as necessary support for nuclear power plant outage work, it can be the last area to which attention is given in preparing for a large-scope outage. Inadequate lead times cause last-minute preparations resulting in delays in planned work. The Dresden Unit 3 Recirculation Piping Replacement Project is examined from a planning viewpoint. The attention that was given the various areas of a comprehensive ALARA/health physics program is examined, and approximate recommended lead times are discussed. The discussion will follow a chronological path from project inception to the beginning stages of outage work. Initially, the scope of work needs to be assessed by individuals familiar with similar projects of equivalent magnitude. Those individuals need to be health physics professionals who understand the particular utility and/or the site's way of doing business. They should also possess a good understanding of preferred industry practices

  15. Experience of ALARA in controlling radiocaesium discharges to the Irish Sea

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1984-01-01

    Radiocaesium discharges to the Irish Sea, which primarily originate from corrosion of magnox fuel in the Sellafield storage ponds, are a source of public radiation exposure mainly through the fish and shellfish consumption pathway. Experience of ALARA in the context of reducing these discharges is described. The operators, British Nuclear Fuels Limited (BNFL), in consultation with Government Departments, decided to install an ion exchange plant to remove radioactivity from pond effluents. This plant is scheduled for commissioning in 1984 and optimisation will play a major part in determining its operating regime. Meanwhile, measures have been taken to reduce discharges using skips of zeolite installed in the ponds. Experience of ALARA in determining the optimum replacement rate of skips is described. A major consideration was differential cost-benefit analysis. Following installation of skips at the rate thereby indicated, discharges are being reduced by about half. A further major reduction is expected when the ion exchange plant becomes available. (author)

  16. ALARA database value in future outage work planning and dose management

    International Nuclear Information System (INIS)

    Miller, D.W.; Green, W.H.

    1995-01-01

    ALARA database encompassing job-specific duration and man-rem plant specific information over three refueling outages represents an invaluable tool for the outage work planner and ALARA engineer. This paper describes dose-management trends emerging based on analysis of three refueling outages at Clinton Power Station. Conclusions reached based on hard data available from a relational database dose-tracking system is a valuable tool for planning of future outage work. The system's ability to identify key problem areas during a refueling outage is improving as more outage comparative data becomes available. Trends over a three outage period are identified in this paper in the categories of number and type of radiation work permits implemented, duration of jobs, projected vs. actual dose rates in work areas, and accuracy of outage person-rem projection. The value of the database in projecting 1 and 5 year station person-rem estimates is discussed

  17. Preoperational ALARA walk-down at the Shearon Harris Nuclear Power Plant

    International Nuclear Information System (INIS)

    Greene, D.W.

    1987-01-01

    Carolina Power and Light Company's Shearon Harris Nuclear Power Plant will enter commercial operation in 19987. During its design and construction a number of reviews were performed to ensure that personnel exposures in the completed plant would be ALARA. The final review in this process consisted of a comprehensive walk-down of plant radiation controlled areas by health physics, operations, maintenance, and engineering personnel. The walk-down project was conducted over a 12-month period using detailed criteria and checklists. This article describes the project, presents examples of the criteria that were used, and list the problems that were identified for resolution as well as the good ALARA design features that were incorporated into the plant

  18. ALARA database value in future outage work planning and dose management

    Energy Technology Data Exchange (ETDEWEB)

    Miller, D.W.; Green, W.H. [Clinton Power Station Illinois Power Co., IL (United States)

    1995-03-01

    ALARA database encompassing job-specific duration and man-rem plant specific information over three refueling outages represents an invaluable tool for the outage work planner and ALARA engineer. This paper describes dose-management trends emerging based on analysis of three refueling outages at Clinton Power Station. Conclusions reached based on hard data available from a relational database dose-tracking system is a valuable tool for planning of future outage work. The system`s ability to identify key problem areas during a refueling outage is improving as more outage comparative data becomes available. Trends over a three outage period are identified in this paper in the categories of number and type of radiation work permits implemented, duration of jobs, projected vs. actual dose rates in work areas, and accuracy of outage person-rem projection. The value of the database in projecting 1 and 5 year station person-rem estimates is discussed.

  19. Differential turbidity at Hanford

    International Nuclear Information System (INIS)

    Laulainen, N.S.; Kleckner, E.W.; Michalsky, J.J.; Stokes, G.M.

    1980-01-01

    Experiments continued in FY 1979 to examine differential turbidity effects on insolation as measured at the earth's surface. These experiments are primarily intended to provide means for interpreting insolation-data assessment studies. These data are also valuable for inferring aerosol radiative or optical effects, which is an important consideration in evaluating inadvertent climate modification and visibility degradation as a result of aerosols. The experiments are characterized by frequent, nearly simultaneous observations at the Rattlesnake Mountain Observatory (RMO) and the Hanford Meteorological Station (HMS) and take advantage of the nearly 1-km altitude difference between these two observing sites. This study indicated that nearly simultaneous measurements of the direct solar beam from stationary sites that are separated in altitude can be used to monitor the incremental optical depth arising from aerosols in the intervening layer. Once appropriate calbiration procedures have been established for the MASP unit, the direct solar data can be used to document on a routine basis aerosol variations in the first kilometer between HMS and RMO

  20. Hanford gas dispersion analysis

    International Nuclear Information System (INIS)

    Fujita, R.K.; Travis, J.R.

    1994-01-01

    An analysis was performed to verify the design of a waste gas exhauster for use in support of rotary core sampling activities at the Westinghouse Hanford Waste Tank Farm. The exhauster was designed to remove waste gases from waste storage tanks during the rotary core drilling process of the solid materials in the tank. Some of the waste gases potentially are very hazardous and must be monitored during the exhauster's operation. If the toxic gas concentrations in specific areas near the exhauster exceed minimum Threshold Limit Values (TLVs), personnel must be excluded from the area. The exhauster stack height is of interest because an increase in stack height will alter the gas concentrations at the critical locations. The exhaust stack is currently ∼4.6 m (15 ft) high. An equipment operator will be located within a 6.1 m (20 ft) radius of the exhaust stack, and his/her head will be at an elevation 3.7 m (12 ft) above ground level (AGL). Therefore, the maximum exhaust gas concentrations at this location must be below the TLV for the toxic gases. Also, the gas concentrations must be within the TLV at a 61 m (200 ft) radius from the stack. If the calculated gas concentrations are above the TLV, where the operator is working below the stack at the 61 m (200 ft) radius location, the stack height may need to be increased

  1. 1976 Hanford americium accident

    International Nuclear Information System (INIS)

    Heid, K.R.; Breitenstein, B.D.; Palmer, H.E.; McMurray, B.J.; Wald, N.

    1979-01-01

    This report presents the 2.5-year medical course of a 64-year-old Hanford nuclear chemical operator who was involved in an accident in an americium recovery facility in August 1976. He was heavily externally contaminated with americium, sustained a substantial internal deposition of this isotope, and was burned with concentrated nitric acid and injured by flying debris about the face and neck. The medical care given the patient, including the decontamination efforts and clinical laboratory studies, are discussed. In-vivo measurements were used to estimate the dose rates and the accumulated doses to body organs. Urinary and fecal excreta were collected and analyzed for americium content. Interpretation of these data was complicated by the fact that the intake resulted both from inhalation and from solubilization of the americium embedded in facial tissues. A total of 1100 μCi was excreted in urine and feces during the first 2 years following the accident. The long-term use of diethylenetriaminepentate (DTPA), used principally as the zinc salt, is discussed including the method, route of administration, and effectiveness. To date, the patient has apparently experienced no complications attributable to this extensive course of therapy, even though he has been given approximately 560 grams of DTPA. 4 figures, 1 table

  2. Radiation exposure usage accountability and impact with respect to ALAP (ALARA) analysis

    International Nuclear Information System (INIS)

    Williams, M.C.

    1978-01-01

    A unique method has been developed for radiation exposure usage accounting at the N Reactor. This method accounts for exposure usage by specific job and working crafts. The accounting system provides information for use in job planning, exposure resource management, and ALAP (ALARA) analysis. It provides justification for ALAP expenditures, documentation of the effectiveness of exposure reduction efforts, and can be used to establish priorities for ALAP efforts

  3. CSER 95-002: ALARA shielding for IAEA SNM container movement

    International Nuclear Information System (INIS)

    Miller, E.M.

    1995-01-01

    This CSER qualifies use of a 5% borated, lead foil lined polyethylene 1 inch annulus as a bucket and in a small carrier to move sealed containers of plutonium. The containers are Oversize Cans or smaller containing plutonium limited in mass and H/Pu ratio by PFP storage and transportation CPS's. These ALARA shielding units reduce personnel exposure to the radiation from the containers as they are moved for assay and other required activities

  4. Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

    International Nuclear Information System (INIS)

    Chen Xiaoqiu

    2009-01-01

    Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

  5. Current practices for maintaining occupational exposures ALARA at low-level waste disposal sites

    International Nuclear Information System (INIS)

    Hadlock, D.E.; Herrington, W.N.; Hooker, C.D.; Murphy, D.W.; Gilchrist, R.L.

    1983-12-01

    The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in establishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) disposal sites. The PNL, through site visits, evaluated operations at LLW disposal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control, internal exposure control, respiratory protection, surveillance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of occupationally exposed individuals

  6. Application of the Alara principle to the occupationally exposed workers in nuclear power plants

    International Nuclear Information System (INIS)

    Mueller, W.; Haider, G.

    1988-01-01

    This report sets down how the Alara (as low as reasonably achievable) principle is applied in radiation protection of the occupationally exposed personnel at light-water reactors in EC countries. In some instances the practices, experiences and results from EC countries are supplemented by the practice in other States (e.g. USA, Sweden). Commencing with a short summary of the legal situation in the Member States of the European Community with regard to Alara, the report describes the framework in which the optimization practice has been developed. The main chapters elaborate in detail how the Alara principle has been put into practice in design and operation in LWRs. The importance of qualification and training of power-plant personnel in relation to optimization of radiation protection is considered and some comparisons are drawn with the US practice. Recommendations are made where reason for modification or harmonization of practices is seen in the conclusions of the different chapters and the overall conclusions and summary of the report

  7. ALARA Review of the Spallation Neutron Source Accumulator Ring and Transfer Lines

    Energy Technology Data Exchange (ETDEWEB)

    Haire, M.J.

    2003-06-30

    The Spallation Neutron Source (SNS) is designed to meet the growing need for new tools that will deepen our understanding in materials science, life science, chemistry, fundamental and nuclear physics, earth and environmental sciences, and engineering sciences. The SNS is an accelerator-based neutron-scattering facility that when operational will produce an average beam power of 2 MW at a repetition rate of 60 Hz. The accelerator complex consists of the front-end systems, which will include an ion source; a 1-GeV full-energy linear accelerator; a single accumulator ring and its transfer lines; and a liquid mercury target. This report documents an as-low-as-reasonably-achievable (ALARA) review of the accumulator ring and transfer lines at their early design stage. An ALARA working group was formed and conducted a review of the SNS ring and transfer lines at the {approx}25% complete design stage to help ensure that ALARA principles are being incorporated into the design. The radiological aspects of the SNS design criteria were reviewed against regulatory requirements and ALARA principles. Proposed features and measures were then reviewed against the SNS design criteria. As part of the overall review, the working group reviewed the design manual; design drawings and process and instrumentation diagrams; the environment, safety, and health manual; and other related reports and literature. The group also talked with SNS design engineers to obtain explanations of pertinent subject matter. The ALARA group found that ALARA principles are indeed being incorporated into the early design stage. Radiation fields have been characterized, and shielding calculations have been performed. Radiological issues are being adequately addressed with regard to equipment selection, access control, confinement structure and ventilation, and contamination control. Radiation monitoring instrumentation for worker and environment protection are also being considered--a good practice at this

  8. Guide to reducing radiation exposure to as low as reasonably achievable (ALARA)

    Energy Technology Data Exchange (ETDEWEB)

    Kathren, R.L.

    1980-04-01

    This document is designed to provide DOE contractor personnel with general guidance regarding programs and techniques to reduce radiation exposures to as low as reasonably achievable (ALARA). Thus it is directed towards a broad audience, and should have special relevance and interest for operating management as well as radiation protection personnel. It is well recognized that each contractor has needs specific and critical to its radiation protection program. Hence no single set of specific and detailed criteria can be set down as a prescription for achieving the ALARA goal. Rather, general guidance in the form of broad principles is given in order to acquaint management with ALARA needs and concepts. The purpose is to encourage maximum management support of the technical personnel responsible for carrying out day-to-day radiation protection activities. Although primarily written for management, this document also contains technical guidance of potential value to those directly involved in radiation protection activities. Again it should be stressed that what is provided is guidance, and is therefore not mandatory.

  9. Current practices for maintaining occupational exposures ALARA at low-level waste disposal sites

    Energy Technology Data Exchange (ETDEWEB)

    Hadlock, D.E.; Herrington, W.N.; Hooker, C.D.; Murphy, D.W.; Gilchrist, R.L.

    1983-12-01

    The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in establishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) disposal sites. The PNL, through site visits, evaluated operations at LLW disposal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control, internal exposure control, respiratory protection, surveillance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of occupationally exposed individuals.

  10. ALARA review for the decontamination and decommissioning of the 233-S pipe trench

    International Nuclear Information System (INIS)

    Kornish, M.J.

    1998-01-01

    The 233-S Facility was completed in 1955 to expand plutonium production by further concentrating the plutonium nitrate product solution from the Reduction Oxidation (REDOX) Plant. The facility is radiologically contaminated because of operations and accidents. Isolation from REDOX and removal of the product transfer lines from the pipe trench is the second step in the decontamination and decommissioning of the entire 233-S Facility. The work scope is to isolate all piping from REDOX and then to remove all the piping/equipment from the pipe trench. The building is presently a Hazard Category 2 Nuclear Facility. A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure No. 1.22, Planning Radiological Work, when radiological conditions exceed trigger levels. The level of contamination inside the pipe trench and the process fluid piping is unknown. The potential exists to exceed the level of loose surface contamination, which requires a formal ALARA review when opening the pipe trench and cutting of piping commences. This ALARA review is for task instruction 1997-03-18-009 Revision 1, 233-S Pipe Trench Decon and Pipe Removal

  11. Guide to reducing radiation exposure to as low as reasonably achievable (ALARA)

    International Nuclear Information System (INIS)

    Kathren, R.L.

    1980-04-01

    This document is designed to provide DOE contractor personnel with general guidance regarding programs and techniques to reduce radiation exposures to as low as reasonably achievable (ALARA). Thus it is directed towards a broad audience, and should have special relevance and interest for operating management as well as radiation protection personnel. It is well recognized that each contractor has needs specific and critical to its radiation protection program. Hence no single set of specific and detailed criteria can be set down as a prescription for achieving the ALARA goal. Rather, general guidance in the form of broad principles is given in order to acquaint management with ALARA needs and concepts. The purpose is to encourage maximum management support of the technical personnel responsible for carrying out day-to-day radiation protection activities. Although primarily written for management, this document also contains technical guidance of potential value to those directly involved in radiation protection activities. Again it should be stressed that what is provided is guidance, and is therefore not mandatory

  12. Hanford Site sustainable development initiatives

    International Nuclear Information System (INIS)

    Sullivan, C.T.

    1994-05-01

    Since the days of the Manhattan Project of World War II, the economic well being of the Tri-Cities (Pasco, Kennewick, and Richland) of Washington State has been tied to the US Department of Energy missions at the nearby Hanford Site. As missions at the Site changed, so did the economic vitality of the region. The Hanford Site is now poised to complete its final mission, that of environmental restoration. When restoration is completed, the Site may be closed and the effect on the local economy will be devastating if action is not taken now. To that end, economic diversification and transition are being planned. To facilitate the process, the Hanford Site will become a sustainable development demonstration project

  13. HANFORD SITE RIVER CORRIDOR CLEANUP

    International Nuclear Information System (INIS)

    BAZZELL, K.D.

    2006-01-01

    In 2005, the US Department of Energy (DOE) launched the third generation of closure contracts, including the River Corridor Closure (RCC) Contract at Hanford. Over the past decade, significant progress has been made on cleaning up the river shore that bordes Hanford. However, the most important cleanup challenges lie ahead. In March 2005, DOE awarded the Hanford River Corridor Closure Contract to Washington Closure Hanford (WCH), a limited liability company owned by Washington Group International, Bechtel National and CH2M HILL. It is a single-purpose company whose goal is to safely and efficiently accelerate cleanup in the 544 km 2 Hanford river corridor and reduce or eliminate future obligations to DOE for maintaining long-term stewardship over the site. The RCC Contract is a cost-plus-incentive-fee closure contract, which incentivizes the contractor to reduce cost and accelerate the schedule. At $1.9 billion and seven years, WCH has accelerated cleaning up Hanford's river corridor significantly compared to the $3.2 billion and 10 years originally estimated by the US Army Corps of Engineers. Predictable funding is one of the key features of the new contract, with funding set by contract at $183 million in fiscal year (FY) 2006 and peaking at $387 million in FY2012. Another feature of the contract allows for Washington Closure to perform up to 40% of the value of the contract and subcontract the balance. One of the major challenges in the next few years will be to identify and qualify sufficient subcontractors to meet the goal

  14. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Finch, S.M.; McMakin, A.H.

    1991-04-01

    The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doses that populations could have received from nuclear operations at Hanford since 1944. The project is being managed and conducted by the Pacific Northwest Laboratory (PNL) under the direction of an independent Technical Steering Panel (TSP). The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed, from released to impact on humans (dose estimates): source terms; environmental transport; environmental monitoring data; demographics, agriculture, food habits; and, environmental pathways and dose estimates

  15. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Finch, S.M.; McMakin, A.H.

    1992-06-01

    The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The project is being managed and conducted by the Battelle Pacific Northwest Laboratories under contract with the Centers for Disease Control. The independent Technical Steering Panel (TSP) provides technical direction. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed, from release to impact on humans (dose estimates): source terms; environmental transport; environmental monitoring data; demography, food consumption, and agriculture; environmental pathways and dose estimates

  16. Disposal of Hanford defense waste

    International Nuclear Information System (INIS)

    Holten, R.A.; Burnham, J.B.; Nelson, I.C.

    1986-01-01

    An Environmental Impact Statement (EIS) on the disposal of Hanford Defense Waste is scheduled to be released near the end of March, 1986. This EIS will evaluate the impacts of alternatives for disposal of high-level, tank, and transuranic wastes which are now stored at the Department of Energy's Hanford Site or will be produced there in the future. In addition to releasing the EIS, the Department of Energy is conducting an extensive public participation process aimed at providing information to the public and receiving comments on the EIS

  17. Hanford Site technical baseline database. Revision 1

    International Nuclear Information System (INIS)

    Porter, P.E.

    1995-01-01

    This report lists the Hanford specific files (Table 1) that make up the Hanford Site Technical Baseline Database. Table 2 includes the delta files that delineate the differences between this revision and revision 0 of the Hanford Site Technical Baseline Database. This information is being managed and maintained on the Hanford RDD-100 System, which uses the capabilities of RDD-100, a systems engineering software system of Ascent Logic Corporation (ALC). This revision of the Hanford Site Technical Baseline Database uses RDD-100 version 3.0.2.2 (see Table 3). Directories reflect those controlled by the Hanford RDD-100 System Administrator. Table 4 provides information regarding the platform. A cassette tape containing the Hanford Site Technical Baseline Database is available

  18. In situ activation of benzyl alcohols with XtalFluor-E: formation of 1,1-diarylmethanes and 1,1,1-triarylmethanes through Friedel-Crafts benzylation.

    Science.gov (United States)

    Desroches, Justine; Champagne, Pier Alexandre; Benhassine, Yasmine; Paquin, Jean-François

    2015-02-28

    The Friedel-Crafts benzylation of arenes using benzyl alcohols activated in situ with XtalFluor-E is described. A wide range of 1,1-diarylmethanes and 1,1,1-triarylmethanes were prepared under experimentally simple and mild conditions, without the need for a transition metal or a strong Lewis acid. Notably, the reactivity observed demonstrates the potential of XtalFluor-E to induce C-OH bond ionization and SN1 reactivity of benzylic alcohols.

  19. Hanford tank initiative vehicle/based waste retrieval demonstration report phase II, track 2

    International Nuclear Information System (INIS)

    Berglin, E.J.

    1997-01-01

    Using the versatile TracPUMpTm, Environmental Specialties Group, LLC (ES) performed a successful Phase 11 demonstration of a Vehicle- Based Waste Retrieval System (VWRS) for removal of waste material and residual liquid found in the Hanford Underground Storage Tanks (ousts). The purpose of this demonstration was to address issues pertaining to the use of a VWRS in OUSTS. The demonstration also revealed the waste removal capabilities of the TracPumpTm and the most effective techniques and equipment to safely and effectively remove waste simulants. ES successfully addressed the following primary issues: I . Dislodge and convey the waste forms present in the Hanford OUSTS; 2. Access the UST through tank openings as small as twenty-four inches in diameter; 3. Traverse a variety of terrains including slopes, sludges, rocks and hard, slippery surfaces without becoming mired; 4. Dislodge and convey waste within the confinement of the Decontamination Containment Capture Vessel (DCCV) and with minimal personnel exposure; 5. Decontaminate equipment to acceptable limits during retrieval from the UST; 6. Perform any required maintenance within the confinement of the DCCV; and 7. Maintain contaminate levels ''as low as reasonably achievable'' (ALARA) within the DCCV due to its crevice and comer-free design. The following materials were used to simulate the physical characteristics of wastes found in Hanford's OUSTS: (1) Hardpan: a clay-type material that has high shear strength; (2) Saltcake: a fertilizer-based material that has high compressive strength; and (3) Wet Sludge.- a sticky, peanut- butter- like material with low shear strength. Four test beds were constructed of plywood and filled with a different simulant to a depth of eight to ten inches. Three of the test beds were of homogenous simulant material, while the fourth bed consisted of a mixture of all three simulant types

  20. Hanford Site environmental management specification

    International Nuclear Information System (INIS)

    Grygiel, M.L.

    1998-01-01

    The US Department of Energy, Richland Operations Office (RL) uses this Hanford Site Environmental Management Specification (Specification) to document top-level mission requirements and planning assumptions for the prime contractors involved in Hanford Site cleanup and infrastructure activities under the responsibility of the US Department of Energy, Office of Environmental Management. This Specification describes at a top level the activities, facilities, and infrastructure necessary to accomplish the cleanup of the Hanford Site and assigns this scope to Site contractors and their respective projects. This Specification also references the key National Environmental Policy Act of 1969 (NEPA), Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), and safety documentation necessary to accurately describe the cleanup at a summary level. The information contained in this document reflects RL's application of values, priorities, and critical success factors expressed by those involved with and affected by the Hanford Site project. The prime contractors and their projects develop complete baselines and work plans to implement this Specification. These lower-level documents and the data that support them, together with this Specification, represent the full set of requirements applicable to the contractors and their projects. Figure 1-1 shows the relationship of this Specification to the other basic Site documents. Similarly, the documents, orders, and laws referenced in this specification represent only the most salient sources of requirements. Current and contractual reference data contain a complete set of source documents

  1. Hanford Site Waste Management Plan

    International Nuclear Information System (INIS)

    1988-12-01

    The Hanford Site Waste Management Plan (HWMP) was prepared in accordance with the outline and format described in the US Department of Energy Orders. The HWMP presents the actions, schedules, and projected costs associated with the management and disposal of Hanford defense wastes, both radioactive and hazardous. The HWMP addresses the Waste Management Program. It does not include the Environmental Restoration Program, itself divided into the Environmental Restoration Remedial Action Program and the Decontamination and Decommissioning Program. The executive summary provides the basis for the plans, schedules, and costs within the scope of the Waste Management Program at Hanford. It summarizes fiscal year (FY) 1988 including the principal issues and the degree to which planned activities were accomplished. It further provides a forecast of FY 1989 including significant milestones. Section 1 provides general information for the Hanford Site including the organization and administration associated with the Waste Management Program and a description of the Site focusing on waste management operations. Section 2 and Section 3 describe radioactive and mixed waste management operations and hazardous waste management, respectively. Each section includes descriptions of the waste management systems and facilities, the characteristics of the wastes managed, and a discussion of the future direction of operations

  2. Differential turbidity measurements at Hanford

    International Nuclear Information System (INIS)

    Laulainen, N.S.; Bates, J.A.; Kleckner, E.W.; Michalsky, J.J.; Schrotke, P.M.; Thorp, J.M.

    1978-01-01

    An experiment to exmine differential turbidity effects on measured insolation between the Rattlesnake Observatory and the Hanford Meteorological Station was conducted during summer 1977. Several types of solar radiation instruments were used, including pyranometers, multiwavelength sunphotometers, and an active cavity radiometer. Preliminary results show dramatic temporal variability of aerosol loading at HMS and significant insolation and turbidity differences between the Observatory and HMS

  3. Hanford Site environmental management specification

    Energy Technology Data Exchange (ETDEWEB)

    Grygiel, M.L.

    1998-06-10

    The US Department of Energy, Richland Operations Office (RL) uses this Hanford Site Environmental Management Specification (Specification) to document top-level mission requirements and planning assumptions for the prime contractors involved in Hanford Site cleanup and infrastructure activities under the responsibility of the US Department of Energy, Office of Environmental Management. This Specification describes at a top level the activities, facilities, and infrastructure necessary to accomplish the cleanup of the Hanford Site and assigns this scope to Site contractors and their respective projects. This Specification also references the key National Environmental Policy Act of 1969 (NEPA), Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), and safety documentation necessary to accurately describe the cleanup at a summary level. The information contained in this document reflects RL`s application of values, priorities, and critical success factors expressed by those involved with and affected by the Hanford Site project. The prime contractors and their projects develop complete baselines and work plans to implement this Specification. These lower-level documents and the data that support them, together with this Specification, represent the full set of requirements applicable to the contractors and their projects. Figure 1-1 shows the relationship of this Specification to the other basic Site documents. Similarly, the documents, orders, and laws referenced in this specification represent only the most salient sources of requirements. Current and contractual reference data contain a complete set of source documents.

  4. Mortality of Hanford radiation workers

    International Nuclear Information System (INIS)

    Gilbert, E.S.

    1979-01-01

    The effects of occupational exposure to low level ionizing radiation at the Hanford plant in southeastern Washington were investigated. Death rates were related to exposure status. To provide perspective, the rates were also compared with the death rates of the US population

  5. Hanford site operator changes management

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    This article is a brief discussion of management changes at the Westinghouse Hanford Corporation. A. LeMar Trego has relieved Thomas Anderson as president of WHC. This was in response to recent shortcomings in Westinghouse's management of the environmental restoration and their failure to receive a $10M performance bonus

  6. Tri-State Synfuels Project Review: Volume 12. Fluor project status. [Proposed Henderson, Kentucky coal to gasoline plant; engineering

    Energy Technology Data Exchange (ETDEWEB)

    1982-06-01

    The purpose of this report is to document and summarize activities associated with Fluor's efforts on the Tri-State Synfuels Project. The proposed facility was to be coal-to-transport fuels facility located in Henderson, Kentucky. Tri-State Synfuels Company was participating in the project as a partner of the US Department of Energy per terms of a Cooperative Agreement resulting from DOE's synfuel's program solicitation. Fluor's initial work plan called for preliminary engineering and procurement services to the point of commitment for construction for a Sasol Fischer-Tropsch plant. Work proceeded as planned until October 1981 when results of alternative coal-to-methanol studies revealed the economic disadvantage of the Synthol design for US markets. A number of alternative process studies followed to determine the best process configuration. In January 1982 Tri-State officially announced a change from Synthol to a Methanol to Gasoline (MTG) design basis. Further evaluation and cost estimates for the MTG facility eventually led to the conclusion that, given the depressed economic outlook for alternative fuels development, the project should be terminated. Official announcement of cancellation was made on April 13, 1982. At the time of project cancellation, Fluor had completed significant portions of the preliminary engineering effort. Included in this report are descriptions and summaries of Fluor's work during this project. In addition location of key project data and materials is identified and status reports for each operation are presented.

  7. TRACKING CLEAN UP AT HANFORD

    International Nuclear Information System (INIS)

    CONNELL, C.W.

    2005-01-01

    The Hanford Federal Facility Agreement and Consent Order, known as the ''Tri-Party Agreement'' (TPA), is a legally binding agreement among the US Department of Energy (DOE), The Washington State Department of Ecology, and the US Environmental Protection Agency (EPA) for cleaning up the Hanford Site. Established in the 1940s to produce material for nuclear weapons as part of the Manhattan Project, Hanford is often referred to as the world's large environmental cleanup project. The Site covers more than 580 square miles in a relatively remote region of southeastern Washington state in the US. The production of nuclear materials at Hanford has left a legacy of tremendous proportions in terms of hazardous and radioactive waste. From a waste-management point of view, the task is enormous: 1700 waste sites; 450 billion gallons of liquid waste; 70 billion gallons of contaminated groundwater; 53 million gallons of tank waste; 9 reactors; 5 million cubic yards of contaminated soil; 22 thousand drums of mixed waste; 2.3 tons of spent nuclear fuel; and 17.8 metric tons of plutonium-bearing material and this is just a partial listing. The agreement requires that DOE provide the results of analytical laboratory and non-laboratory tests/readings to the lead regulatory agency to help guide then in making decisions. The agreement also calls for each signatory to preserve--for at least ten years after the Agreement has ended--all of the records in it, or its contractors, possession related to sampling, analysis, investigations, and monitoring conducted. The Action Plan that supports the TPA requires that Ecology and EPA have access to all data that is relevant to work performed, or to be performed, under the Agreement. Further, the Action Plan specifies two additional requirements: (1) that EPA, Ecology and their respective contractor staffs have access to all the information electronically, and (2) that the databases are accessible to, and used by, all personnel doing TPA

  8. ALARA [as low as reasonably achievable] engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

    International Nuclear Information System (INIS)

    Daniel, S.W.; Kaplan, E.; Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

    1989-09-01

    This report is the first in the series of bibliographies supporting the efforts at the Brookhaven National Laboratory ALARA Center on dose reduction at DOE facilities. Abstracts for this bibliography were selected from proceedings of technical meetings, journals, research reports, and searches of the DOE Energy Data Base. The abstracts included in this report relate to operational health physics as well as other subjects which have a bearing on dose reduction. Facilities covered include: radioactive waste, uranium enrichment, fabrication, unirradiated fissile materials storage, irradiated fissile material storage, reprocessing, decommissioning, recovery, hot laboratories, tritium production, reactors (research, test and production but not power reactors), and accelerators. We have also included material in improved design, materials selection, planning, and other topics which are related to dose-reduction efforts. The report contains 68 abstracts as well as subject and author indices

  9. Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA

    International Nuclear Information System (INIS)

    Dionne, B.J.; Lane, S.G.; Baum, J.W.

    1991-11-01

    Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report, prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health, contains the third in a series of bibliographies on dose reduction at DOE facilities. This report also contains abstracts from the two previous volumes. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE's Office of Environment, Safety and Health to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy Data Base, and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, storage, and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, and accelerators. Material on improved shielding design, decontamination, containments, robotics, job planning, improved operational techniques, and other topics are also included

  10. Report on the BWR owners group radiation protection/ALARA Committee

    Energy Technology Data Exchange (ETDEWEB)

    Aldrich, L.R. [Commonwealth Edison Co., Downers Grove, IL (United States)

    1995-03-01

    Radiation protection programs at U.S. boiling water reactor (BWR) stations have evolved during the 1980s and early 1990s from a regulatory adherence-based endeavor to a proactive, risk-based radiation protection and prevention mission. The objectives are no longer to merely monitor and document exposure to radiation and radioactive materials. The focus of the current programs is the optimization of radiation protection of occupational workers consistent with the purpose of producing cost-effective electric power. The newly revised 10 CFR 20 defines the term ALARA (as low as reasonably achievable) to take into account the state of technology, the economics of improvements in relation to the state of the technology, and the benefits to the public health and safety. The BWR Owners Group (BWROG) initially formed the Radiation Protection/ALARA Committee in January 1990 to evaluate methods of reducing occupational radiation exposure during refueling outages. Currently, twenty U.S. BWR owner/operators (representing 36 of the operational 37 domestic BWR units), as well as three foreign BWR operators (associate members), have broadened the scope to promote information exchange between BWR radiation protection professionals and develop good practices which will affect optimization of their radiation protection programs. In search of excellence and the challenge of becoming {open_quotes}World Class{close_quotes} performers in radiation protection, the BWROG Radiation Protection/ALARA Committee has recently accepted a role in assisting the member utilities in improving radiation protection performance in a cost-effective manner. This paper will summarize the recent activities of this Committee undertaken to execute their role of exchanging information in pursuit of optimizing the improvement of their collective radiation protection performance.

  11. Report on the BWR owners group radiation protection/ALARA Committee

    International Nuclear Information System (INIS)

    Aldrich, L.R.

    1995-01-01

    Radiation protection programs at U.S. boiling water reactor (BWR) stations have evolved during the 1980s and early 1990s from a regulatory adherence-based endeavor to a proactive, risk-based radiation protection and prevention mission. The objectives are no longer to merely monitor and document exposure to radiation and radioactive materials. The focus of the current programs is the optimization of radiation protection of occupational workers consistent with the purpose of producing cost-effective electric power. The newly revised 10 CFR 20 defines the term ALARA (as low as reasonably achievable) to take into account the state of technology, the economics of improvements in relation to the state of the technology, and the benefits to the public health and safety. The BWR Owners Group (BWROG) initially formed the Radiation Protection/ALARA Committee in January 1990 to evaluate methods of reducing occupational radiation exposure during refueling outages. Currently, twenty U.S. BWR owner/operators (representing 36 of the operational 37 domestic BWR units), as well as three foreign BWR operators (associate members), have broadened the scope to promote information exchange between BWR radiation protection professionals and develop good practices which will affect optimization of their radiation protection programs. In search of excellence and the challenge of becoming open-quotes World Classclose quotes performers in radiation protection, the BWROG Radiation Protection/ALARA Committee has recently accepted a role in assisting the member utilities in improving radiation protection performance in a cost-effective manner. This paper will summarize the recent activities of this Committee undertaken to execute their role of exchanging information in pursuit of optimizing the improvement of their collective radiation protection performance

  12. History of Hanford Site Defense Production (Brief)

    International Nuclear Information System (INIS)

    GERBER, M.S.

    2001-01-01

    This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

  13. Backfitting of the nuclear power plant Borssele. A practical application of the ALARA-principle

    International Nuclear Information System (INIS)

    Leurs, C.J.

    1998-01-01

    In two articles an overview is given of the adjustments for the title plant and how the radiation load of employees is kept as low as possible according to the newest insights of the ALARA-principle. In this article attention is paid to the results of the project 'Modifications' which comprises 16 system engineering modifications. The maximum attention for radiation protection resulted in a collective dose of circa 2500 millisievert, which is a factor 4 lower than the first estimation of the radiation load. 7 refs

  14. Cone-beam computed tomography: Time to move from ALARA to ALADA

    Energy Technology Data Exchange (ETDEWEB)

    Jaju, Prashant P.; Jaju, Sushma P. [Rishiraj College of Dental Sciences and Research Centre, Bhopa(Indonesia)

    2015-12-15

    Cone-beam computed tomography (CBCT) is routinely recommended for dental diagnosis and treatment planning. CBCT exposes patients to less radiation than does conventional CT. Still, lack of proper education among dentists and specialists is resulting in improper referral for CBCT. In addition, aiming to generate high-quality images, operators may increase the radiation dose, which can expose the patient to unnecessary risk. This letter advocates appropriate radiation dosing during CBCT to the benefit of both patients and dentists, and supports moving from the concept of 'as low as reasonably achievable' (ALARA) to 'as low as diagnostically acceptable' (ALADA.

  15. Fluor Hanford Integrated Safety Management System Phase 1 Verification 04/12/2000 Thru 04/28/2000 Volume 1 and 2

    International Nuclear Information System (INIS)

    PARSONS, J.E.

    2000-01-01

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78)

  16. Fluor Hanford Integrated Safety Management System Phase 1 Verification 04/12/2000 Thru 04/28/2000 Volume 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    PARSONS, J.E.

    2000-03-01

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78).

  17. Fluor Hanford Integrated Safety Management System Phase 1 Verification 04/12/2000 Thru 04/28/2000 Volume 1 and 2

    CERN Document Server

    Parsons, J E

    2000-01-01

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78).

  18. Historical genesis of Hanford Site wastes

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1991-01-01

    This paper acquaints the audience with historical waste practices and policies as they changed over the years at the Hanford Site, and with the generation of the major waste streams of concern in Hanford Site clean-up today. The paper also describes the founding and basic operating history of the Hanford Site, including World War 11 construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), and some past suggestions and efforts to chemically treat, open-quotes fractionate,close quotes and/or immobilize Hanford's wastes. Recent events, including the designation of the Hanford Site as the open-quotes flagshipclose quotes of Department of Energy (DOE) waste remediation efforts and the signing of the landmark Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), have generated new interest in Hanford's history. Clean-up milestones dictated in this agreement demand information about how, when, in what quantities and mixtures, and under what conditions, Hanford Site wastes were generated and released. This paper presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

  19. Potential radiation doses from 1994 Hanford Operations

    Energy Technology Data Exchange (ETDEWEB)

    Soldat, J.K.; Antonio, E.J.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the potential radiation doses to the public from releases originating at the Hanford Site. Members of the public are potentially exposed to low-levels of radiation from these effluents through a variety of pathways. The potential radiation doses to the public were calculated for the hypothetical MEI and for the general public residing within 80 km (50 mi) of the Hanford Site.

  20. Potential radiation doses from 1994 Hanford Operations

    International Nuclear Information System (INIS)

    Soldat, J.K.; Antonio, E.J.

    1995-01-01

    This section of the 1994 Hanford Site Environmental Report summarizes the potential radiation doses to the public from releases originating at the Hanford Site. Members of the public are potentially exposed to low-levels of radiation from these effluents through a variety of pathways. The potential radiation doses to the public were calculated for the hypothetical MEI and for the general public residing within 80 km (50 mi) of the Hanford Site

  1. Hanford Site Solid Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  2. Pollution prevention opportunity assessments at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Betsch, M.D., Westinghouse Hanford

    1996-06-26

    The Pollution Prevention Opportunity Assessment (PPOA) is a pro- active way to look at a waste generating activity and identify opportunities to minimize wastes through a cost benefit analysis. Hanford`s PPOA process is based upon the graded approach developed by the Kansas City Plant. Hanford further streamlined the process while building in more flexibility for the individual users. One of the most challenging aspects for implementing the PPOA process at Hanford is one overall mission which is environmental restoration, Now that the facilities are no longer in production, each has a different non- routine activity making it difficult to quantify the inputs and outputs of the activity under consideration.

  3. HANFORD SCIENCE & TECHNOLOGY NEEDS STATEMENTS 2002

    Energy Technology Data Exchange (ETDEWEB)

    WIBLE, R.A.

    2002-04-01

    This document: (a) provides a comprehensive listing of the Hanford sites science and technology needs for fiscal year (FY) 2002; and (b) identifies partnering and commercialization opportunities within industry, other federal and state agencies, and the academic community. These needs were prepared by the Hanford projects (within the Project Hanford Management Contract, the Environmental Restoration Contract and the River Protection Project) and subsequently reviewed and endorsed by the Hanford Site Technology Coordination Group (STCG). The STCG reviews included participation of DOE-RL and DOE-ORP Management, site stakeholders, state and federal regulators, and Tribal Nations. These needs are reviewed and updated on an annual basis and given a broad distribution.

  4. Field trip guide to the Hanford Site

    International Nuclear Information System (INIS)

    Reidel, S.P.; Lindsey, K.A.; Fecht, K.R.

    1992-11-01

    This report is designed to provide a guide to the key geologic and hydrologic features of the US Department of Energy's Hanford Site located in south-central Washington. The guide is divided into two parts. The first part is a general introduction to the geology of the Hanford Site and its relation to the regional framework of south-central Washington. The second part is a road log that provides directions to important geologic features on the Hanford Site and descriptions of the locality. The exposures described were chosen for their accessibility and importance to the geologic history of the Hanford Site and to understanding the geohydrology of the Site

  5. Hanford Site Solid Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    1993-01-01

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

  6. Mortality of Hanford radiation workers

    International Nuclear Information System (INIS)

    Gilbert, E.S.

    1980-01-01

    Mortality from all causes for white males employed at Hanford for at least two years is 75 percent of that expected on the basis of US vital statistics. Mortality from cancer is 85 percent of that expected. These results are typical of a working population. Neither death from all causes nor death from all cancer types shows a positive correlation with external radiation exposures. Myeloid leukemia, the disease that several studies have found to be associated most strongly with radiation exposure, is not correlated with external radiation exposure of Hanford workers. Two specific cancers, multiple myeloma and to a lesser extent cancer of the pancreas, were found to be positively correlated with radiation exposure. The correlations identified result entirely from a small number of deaths (3 each for multiple myeloma and cancer of the pancreas) with cumulative exposure greater than 15 rem

  7. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    McMakin, A.H.; Cannon, S.D.; Finch, S.M.

    1992-07-01

    The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The TSP consists of experts in environmental pathways, epidemiology, surface-water transport, ground-water transport, statistics, demography, agriculture, meteorology, nuclear engineering, radiation dosimetry, and cultural anthropology. Included are appointed technical members representing the states of Oregon, Washington, and Idaho, a representative of Native American tribes, and an individual representing the public. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed from release to impact on humans (dose estimates): Source terms, environmental transport, environmental monitoring data, demography, food consumption, and agriculture, and environmental pathways and dose estimates. Progress is discussed

  8. Hanford whole body counting manual

    International Nuclear Information System (INIS)

    Palmer, H.E.; Brim, C.P.; Rieksts, G.A.; Rhoads, M.C.

    1987-05-01

    This document, a reprint of the Whole Body Counting Manual, was compiled to train personnel, document operation procedures, and outline quality assurance procedures. The current manual contains information on: the location, availability, and scope of services of Hanford's whole body counting facilities; the administrative aspect of the whole body counting operation; Hanford's whole body counting facilities; the step-by-step procedure involved in the different types of in vivo measurements; the detectors, preamplifiers and amplifiers, and spectroscopy equipment; the quality assurance aspect of equipment calibration and recordkeeping; data processing, record storage, results verification, report preparation, count summaries, and unit cost accounting; and the topics of minimum detectable amount and measurement accuracy and precision. 12 refs., 13 tabs

  9. Hanford Environmental Information System (HEIS)

    International Nuclear Information System (INIS)

    1994-01-01

    The Well subject area of the Hanford Environmental Information System (HEIS) manages data relevant to wells, boreholes and test pits constructed at the Hanford Site for soil sampling, geologic analysis and/or ground-water monitoring, and sampling for hydrochemical and radiological analysis. Data stored in the Well subject area include information relevant to the construction of the wells and boreholes, structural modifications to existing wells and boreholes, the location of wells, boreholes and test pits, and the association of wells, boreholes and test pits with organization entities such as waste sites. Data resulting from ground-water sampling performed at wells are stored in tables in the Ground-Water subject area. Geologic data collected during drilling, including particle sizing and interpretative geologic summaries, are stored in tables in the Geologic subject area. Data from soil samples taken during the drilling or excavation and sent for chemical and/or radiological analysis are stored in the Soil subject area

  10. Hanford waste tank cone penetrometer

    International Nuclear Information System (INIS)

    Seda, R.Y.

    1995-12-01

    A new tool is being developed to characterize tank waste at the Hanford Reservation. This tool, known as the cone penetrometer, is capable of obtaining chemical and physical properties in situ. For the past 50 years, this tool has been used extensively in soil applications and now has been modified for usage in Hanford Underground Storage tanks. These modifications include development of new ''waste'' data models as well as hardware design changes to accommodate the hazardous and radioactive environment of the tanks. The modified cone penetrometer is scheduled to be deployed at Hanford by Fall 1996. At Hanford, the cone penetrometer will be used as an instrumented pipe which measures chemical and physical properties as it pushes through tank waste. Physical data, such as tank waste stratification and mechanical properties, is obtained through three sensors measuring tip pressure, sleeve friction and pore pressure. Chemical data, such as chemical speciation, is measured using a Raman spectroscopy sensor. The sensor package contains other instrumentation as well, including a tip and side temperature sensor, tank bottom detection and an inclinometer. Once the cone penetrometer has reached the bottom of the tank, a moisture probe will be inserted into the pipe. This probe is used to measure waste moisture content, water level, waste surface moisture and tank temperature. This paper discusses the development of this new measurement system. Data from the cone penetrometer will aid in the selection of sampling tools, waste tank retrieval process, and addressing various tank safety issues. This paper will explore various waste models as well as the challenges associated with tank environment

  11. Hanford Environmental Information System (HEIS)

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of the Biota subject area of the Hanford Environmental Information System (HEIS) is to manage the data collected from samples of plants and animals. This includes both samples taken from the plant or animal or samples related to the plant or animal. Related samples include animal feces and animal habitat. Data stored in the Biota subject area include data about the biota samples taken, analysis results counts from population studies, and species distribution maps

  12. Hanford Environmental Information System (HEIS)

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of the Soil subject area of the Hanford Environmental Information System (HEIS) is to manage the data acquired from soil samples, both geologic and surface, and sediment samples. Stored in the Soil subject area are data relevant to the soil samples, laboratory analytical results, and field measurements. The two major types of data make up the Soil subject area are data concerning the samples and data about the chemical and/or radiologic analyses of soil samples

  13. Hanford Generic Interim Safety Basis

    Energy Technology Data Exchange (ETDEWEB)

    Lavender, J.C.

    1994-09-09

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  14. Hanford Generic Interim Safety Basis

    International Nuclear Information System (INIS)

    Lavender, J.C.

    1994-01-01

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports

  15. Hanford Environmental Information System (HEIS)

    International Nuclear Information System (INIS)

    1994-01-01

    The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. HEIS is an information system with an inclusive database. Although the database is the nucleus of the system, HEIS also provides user access software: query-by-form data entry, extraction, and browsing facilities; menu-driven reporting facilities; an ad hoc query facility; and a geographic information system (GIS). These features, with the exception of the GIS, are described in this manual set. Because HEIS contains data from the entire Hanford Site, many varieties of data are included and have.been divided into subject areas. Related subject areas comprise several volumes of the manual set. The manual set includes a data dictionary that lists all of the fields in the HEIS database, with their definitions and a cross reference of their locations in the database; definitions of data qualifiers for analytical results; and a mapping between the HEIS software functions and the keyboard keys for each of the supported terminals or terminal emulators

  16. Hanford Site surface environmental surveillance

    International Nuclear Information System (INIS)

    Dirkes, R.L.

    1998-01-01

    Environmental surveillance of the Hanford Site and the surrounding region is conducted to demonstrate compliance with environmental regulations, confirm adherence to US Department of Energy (DOE) environmental protection policies, support DOE environmental management decisions, and provide information to the public. The Surface Environmental Surveillance Project (SESP) is a multimedia environmental monitoring program conducted to measure the concentrations of radionuclides and chemical contaminants in the environment and assess the integrated effects of these contaminants on the environment and the public. The monitoring program includes sampling air, surface water, sediments, soil, natural vegetation, agricultural products, fish, and wildlife. Functional elements inherent in the operation of the SESP include project management, quality assurance/control, training, records management, environmental sampling network design and implementation, sample collection, sample analysis, data management, data review and evaluation, exposure assessment, and reporting. The SESP focuses on those contaminant/media combinations calculated to have the highest potential for contributing to off-site exposure. Results of the SESP indicate that contaminant concentrations in the Hanford environs are very low, generally below environmental standards, at or below analytical detection levels, and indicative of environmental levels. However, areas of elevated contaminant concentrations have been identified at Hanford. The extent of these areas is generally limited to past operating areas and waste disposal sites

  17. Hanford whole body counting manual

    International Nuclear Information System (INIS)

    Palmer, H.E.; Rieksts, G.A.; Lynch, T.P.

    1990-06-01

    This document describes the Hanford Whole Body Counting Program as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy--Richland Operations Office (DOE-RL) and its Hanford contractors. Program services include providing in vivo measurements of internally deposited radioactivity in Hanford employees (or visitors). Specific chapters of this manual deal with the following subjects: program operational charter, authority, administration, and practices, including interpreting applicable DOE Orders, regulations, and guidance into criteria for in vivo measurement frequency, etc., for the plant-wide whole body counting services; state-of-the-art facilities and equipment used to provide the best in vivo measurement results possible for the approximately 11,000 measurements made annually; procedures for performing the various in vivo measurements at the Whole Body Counter (WBC) and related facilities including whole body counts; operation and maintenance of counting equipment, quality assurance provisions of the program, WBC data processing functions, statistical aspects of in vivo measurements, and whole body counting records and associated guidance documents. 16 refs., 48 figs., 22 tabs

  18. ALARA principle - new philosophy in radiation therapy of papillary thyroid carcinoma

    International Nuclear Information System (INIS)

    Hadjieva, T.

    2003-01-01

    The papillary thyroid carcinoma is a model for a successful multidisciplinary oncological therapy with the early stage survival similar to that for normal population. The iodine radiotherapy is a part of the complex treatment leading to these results. The radiation protection principle ALARA is created for healthy people. The authors have formulated it for the purposes of radiotherapy and have built in, as a basic philosophy, in the new radiotherapy concept. It has increased the benefit:risk ratio for the patient. In this case ALARA means: reduction of the indications for treatment with 131 I in the early stages of papillary carcinoma; achievement of tumor control with minimal possible activity in advanced cases; medicamentous, dietary and other measures, reducing the dose burden during and after the treatment, extension of the overall treatment period through a control of the tumor marker thyroglobulin; special treatment and diagnostic regime for children and adolescents, a minimum radiation invasive and economically and socially adequate algorithm for the long-time follow-up of the patients. This ensures a high life quality for the healed patients, comparable with that of the other people

  19. BNL ALARA Center experience with an information exchange system on dose control at nuclear power plants

    International Nuclear Information System (INIS)

    Baum, J.W.; Khan, T.A.

    1992-01-01

    The essential elements of an international information exchange system on dose control at nuclear power plants are summarized. Information was collected from literature abstracting services, by attending technical meetings, by circulating data collection forms, and through personal contacts. Data are assembled in various databases and periodically disseminated to several hundred interested participants through a variety of publications and at technical meetings. Immediate on-line access to the data is available to participants with modems, commercially available communications software, and a password that is provided by the Brookhaven National Laboratory (BNL) ALARA Center to authorized users of the system. Since January 1992, rapid access also has been provided to persons with fax machines. Some information is available for ''polling'' the BNL system at any time, and other data can be installed for polling on request. Most information disseminated to data has been through publications; however, new protocols, simplified by the ALARA Center staff, and the convenience of fax machines are likely to make the earlier availability of information through these mechanisms increasingly important

  20. Comparison of Measurements and FluorMOD Simulations for Solar Induced Chlorophyll Fluorescence and Reflectance of a Corn Crop under Nitrogen Treatments [SIF and Reflectance for Corn

    Science.gov (United States)

    Middleton, Elizabeth M.; Corp, Lawrence A.; Campbell, Petya K. E.

    2007-01-01

    The FLuorescence Explorer (FLEX) satellite concept is one of six semifinalist mission proposals selected in 2006 for pre-Phase studies by the European Space Agency (ESA). The FLEX concept proposes to measure passive solar induced chlorophyll fluorescence (SIF) of terrestrial ecosystems. A new spectral vegetation Fluorescence Model (FluorMOD) was developed to include the effects of steady state SIF on canopy reflectance. We used our laboratory and field measurements previously acquired from foliage and canopies of corn (Zea mays L.) under controlled nitrogen (N) fertilization to parameterize and evaluate FluorMOD. Our data included biophysical properties, fluorescence (F) and reflectance spectra for leaves; reflectance spectra of canopies and soil; solar irradiance; plot-level leaf area index; and canopy SIF emissions determined using the Fraunhofer Line Depth principal for the atmospheric telluric oxygen absorption features at 688 nm (O2-beta) and 760 nm (O2-alpha). FluorMOD simulations implemented in the default "look-up-table" mode did not reproduce the observed magnitudes of leaf F, canopy SIF, or canopy reflectance. However, simulations for all of these parameters agreed with observations when the default FluorMOD information was replaced with measurements, although N treatment responses were underestimated. Recommendations were provided to enhance FluorMOD's potential utility in support of SIF field experiments and studies of agriculture and ecosystems.

  1. A novel and selective fluoride opening of aziridines by XtalFluor-E. synthesis of fluorinated diamino acid derivatives.

    Science.gov (United States)

    Nonn, Melinda; Kiss, Loránd; Haukka, Matti; Fustero, Santos; Fülöp, Ferenc

    2015-03-06

    The selective introduction of fluorine onto the skeleton of an aminocyclopentane or cyclohexane carboxylate has been developed through a novel and efficient fluoride opening of an activated aziridine ring with XtalFluor-E. The reaction proceeded through a stereoselective aziridination of the olefinic bond of a bicyclic lactam and regioselective aziridine ring opening with difluorosulfiliminium tetrafluoroborate with the neighboring group assistance of the sulfonamide moiety to yield fluorinated diamino acid derivatives. The method based on the selective aziridine opening by fluoride has been generalized to afford access to mono- or bicyclic fluorinated substances.

  2. Volume labeling with Alexa Fluor dyes and surface functionalization of highly sensitive fluorescent silica (SiO2) nanoparticles

    Science.gov (United States)

    Wang, Wei; Nallathamby, Prakash D.; Foster, Carmen M.; Morrell-Falvey, Jennifer L.; Mortensen, Ninell P.; Doktycz, Mitchel J.; Gu, Baohua; Retterer, Scott T.

    2013-10-01

    A new synthesis approach is described that allows the direct incorporation of fluorescent labels into the volume or body of SiO2 nanoparticles. In this process, fluorescent Alexa Fluor dyes with different emission wavelengths were covalently incorporated into the SiO2 nanoparticles during their formation by the hydrolysis of tetraethoxysilane. The dye molecules were homogeneously distributed throughout the SiO2 nanoparticles. The quantum yields of the Alexa Fluor volume-labeled SiO2 nanoparticles were much higher than nanoparticles labeled using conventional organic dyes. The size of the resulting nanoparticles was controlled using microemulsion reaction media with sizes in the range of 20-100 nm and a polydispersity of cultured macrophages. Differences in particle agglomeration and cell association were clearly associated with differences in observed nanoparticle toxicity. The capacity to maintain particle fluorescence while making significant changes to surface chemistry makes these particles extremely versatile and useful for studies of particle agglomeration, uptake, and transport in environmental and biological systems.A new synthesis approach is described that allows the direct incorporation of fluorescent labels into the volume or body of SiO2 nanoparticles. In this process, fluorescent Alexa Fluor dyes with different emission wavelengths were covalently incorporated into the SiO2 nanoparticles during their formation by the hydrolysis of tetraethoxysilane. The dye molecules were homogeneously distributed throughout the SiO2 nanoparticles. The quantum yields of the Alexa Fluor volume-labeled SiO2 nanoparticles were much higher than nanoparticles labeled using conventional organic dyes. The size of the resulting nanoparticles was controlled using microemulsion reaction media with sizes in the range of 20-100 nm and a polydispersity of cultured macrophages. Differences in particle agglomeration and cell association were clearly associated with differences in

  3. TECHNICAL EVALUATION OF ELECTRICAL RESISTIVITY METHODS AT THE DEPARTMENT OF ENERGY HANFORD SITE

    International Nuclear Information System (INIS)

    PETERSEN SW

    2008-01-01

    There is a continuing need for cost-effective subsurface characterization within the vadose zone and groundwater at the U.S. Department of Energy (DOE) Hanford Site, Richland, Washington. With more than 1600 liquid and solid waste sites and 200 burial sites, contaminants have migrated to and through the vadose zone. In addition, future groundwater plumes may be generated from contaminants presently in the vadose zone. Relatively low-cost geophysical techniques can provide spatially extensive data that may provide information about the presence and extent of some contaminants. Recent electrical resistivity surveys at Hanford have provided encouraging results for mapping of some contaminants, such as nitrate, in the vadose zone. Because mobile radionuclides and trace elements may have been transported with nitrate through the vadose zone, the method may be used to map some mobile contaminants of concern, such as technetium-99 (99Tc). Validation of these recent electrical resistivity survey results remains to be completed. Electrical resistivity surveys have been conducted at various waste sites in the 200 Area of the Hanford Site: BC Cribs and Trenches (BCCT), T, S, U, C, B Tank Farms and the Purex Plant. Surveys have been completed using surface and well-to-well (WTW) array configurations. The goals of the surveys, as described by Fluor Hanford and CH2MHill Hanford staff, were to test the applicability of resistivity methods in identifying the presence of and mapping approximate extent of contaminant plumes within the vadose zone. The overall goal of the project was to evaluate the utility of electrical resistivity methods for characterizing contaminants of potential concern in the vadose zone in the 200 Area of the Hanford Site. The panel was asked to perform the following activities: (1) Evaluate recently completed and ongoing electrical resistivity projects at Hanford in terms of methodology used, results obtained, and lessons learned, with specific focus on (a

  4. ALARA plan for the Old Hydrofracture Facility tanks contents removal project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-04-01

    The purpose of the Old Hydrofracture Facility (OHF) Tanks Contents Removal Project is to remove the liquid low-level waste from the five underground storage tanks located at OHF and transfer the resulting slurry to the Melton Valley Storage Tanks facility for treatment and disposal. Among the technical objectives for the OHF Project, there is a specific provision to maintain personnel exposures as low as reasonably achievable (ALARA) during each activity of the project and to protect human health and the environment. The estimated doses and anticipated conditions for accomplishing this project are such that an ALARA Plan is necessary to facilitate formal radiological review of the campaign. This ALARA Plan describes the operational steps necessary for accomplishing the job together with the associated radiological impacts and planned controls. Individual and collective dose estimates are also provided for the various tasks. Any significant changes to this plan (i.e., planned exposures that are greater than 10% of original dose estimates) will require formal revision and concurrence from all parties listed on the approval page. Deviations from this plan (i.e., work outside the scope covered by this plan) also require the preparation of a task-specific ALARA Review that will be amended to this plan with concurrence from all parties listed on the approval page

  5. Vascular Plants of the Hanford Site

    International Nuclear Information System (INIS)

    Sackschewsky, Michael R.; Downs, Janelle L.

    2001-01-01

    This report provides an updated listing of the vascular plants present on and near the U.S. Department of Energy Hanford Site. This document is an update of a listing of plants prepared by Sackschewdky et al. in 1992. Since that time there has been a significant increase in the botanical knowledge of the Hanford Site. The present listing is based on an examination of herbarium collections held at PNNL, at WSU-Tri Cities, WSU-Pullman, Brigham Young University, and The University of Washington, and on examination of ecological literature derived from the Hanford and Benton county areas over the last 100 years. Based on the most recent analysis, there are approximately 725 different plant species that have been documented on or around the Hanford Site. This represents an approximate 20% increase in the number of species reported within Sackschewsky et al. (1992). This listing directly supports DOE and contractor efforts to assess the potential impacts of Hanford Site operations

  6. Hanford Patrol Academy demolition sites closure plan

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-30

    The Hanford Site is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office. Westinghouse Hanford Company is a major contractor to the U.S. Department of Energy, Richland Operations Office and serves as co-operator of the Hanford Patrol Academy Demolition Sites, the unit addressed in this paper. This document consists of a Hanford Facility Dangerous Waste Part A Permit Application, Form 3 (Revision 4), and a closure plan for the site. An explanation of the Part A Form 3 submitted with this closure plan is provided at the beginning of the Part A section. This Hanford Patrol Academy Demolition Sites Closure Plan submittal contains information current as of December 15, 1994.

  7. Hanford Site baseline risk assessment methodology

    International Nuclear Information System (INIS)

    1993-03-01

    This methodology has been developed to prepare human health and environmental evaluations of risk as part of the Comprehensive Environmental Response, Compensation, and Liability Act remedial investigations (RIs) and the Resource Conservation and Recovery Act facility investigations (FIs) performed at the Hanford Site pursuant to the Hanford Federal Facility Agreement and Consent Order referred to as the Tri-Party Agreement. Development of the methodology has been undertaken so that Hanford Site risk assessments are consistent with current regulations and guidance, while providing direction on flexible, ambiguous, or undefined aspects of the guidance. The methodology identifies Site-specific risk assessment considerations and integrates them with approaches for evaluating human and environmental risk that can be factored into the risk assessment program supporting the Hanford Site cleanup mission. Consequently, the methodology will enhance the preparation and review of individual risk assessments at the Hanford Site

  8. Public involvement in environmental surveillance at Hanford

    International Nuclear Information System (INIS)

    Hanf, R.W. Jr.; Patton, G.W.; Woodruff, R.K.; Poston, T.M.

    1994-08-01

    Environmental surveillance at the Hanford Site began during the mid-1940s following the construction and start-up of the nation's first plutonium production reactor. Over the past approximately 45 years, surveillance operations on and off the Site have continued, with virtually all sampling being conducted by Hanford Site workers. Recently, the US Department of Energy Richland Operations Office directed that public involvement in Hanford environmental surveillance operations be initiated. Accordingly, three special radiological air monitoring stations were constructed offsite, near hanford's perimeter. Each station is managed and operated by two local school teaches. These three stations are the beginning of a community-operated environmental surveillance program that will ultimately involve the public in most surveillance operations around the Site. The program was designed to stimulate interest in Hanford environmental surveillance operations, and to help the public better understand surveillance results. The program has also been used to enhance educational opportunities at local schools

  9. Annual Hanford seismic report - fiscal year 1996

    International Nuclear Information System (INIS)

    Hartshorn, D.C.; Reidel, S.P.

    1996-12-01

    Seismic monitoring (SM) at the Hanford Site was established in 1969 by the US Geological Survey (USGS) under a contract with the US Atomic Energy Commission. Since 1980, the program has been managed by several contractors under the US Department of Energy (USDOE). Effective October 1, 1996, the Seismic Monitoring workscope, personnel, and associated contracts were transferred to the USDOE Pacific Northwest National Laboratory (PNNL). SM is tasked to provide an uninterrupted collection and archives of high-quality raw and processed seismic data from the Hanford Seismic Network (HSN) located on and encircling the Hanford Site. SM is also tasked to locate and identify sources of seismic activity and monitor changes in the historical pattern of seismic activity at the Hanford Site. The data compiled are used by SM, Waste Management, and engineering activities at the Hanford Site to evaluate seismic hazards and seismic design for the Site

  10. Hanford Environmental Management Program implementation plan

    International Nuclear Information System (INIS)

    1988-08-01

    The Hanford Environmental Management Program (HEMP) was established to facilitate compliance with the applicable environmental statues, regulations, and standards on the Hanford Site. The HEMP provides a structured approach to achieve environmental management objectives. The Hanford Environmental Management Program Plan (HEMP Plan) was prepared as a strategic level planning document to describe the program management, technical implementation, verification, and communications activities that guide the HEMP. Four basic program objectives are identified in the HEMP Plan as follows: establish ongoing monitoring to ensure that Hanford Site operations comply with environmental requirements; attain regulatory compliance through the modification of activities; mitigate any environmental consequences; and minimize the environmental impacts of future operations at the Hanford Site. 2 refs., 24 figs., 27 tabs

  11. Hanford Site Risk Assessment Methodology. Revision 3

    International Nuclear Information System (INIS)

    1995-05-01

    This methodology has been developed to prepare human health and ecological evaluations of risk as part of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) remedial investigations (RI) and the Resource conservation and Recovery Act of 1976 (RCRA) facility investigations (FI) performed at the Hanford Site pursuant to the hanford Federal Facility Agreement and Consent Order (Ecology et al. 1994), referred to as the Tri-Party Agreement. Development of the methodology has been undertaken so that Hanford Site risk assessments are consistent with current regulations and guidance, while providing direction on flexible, ambiguous, or undefined aspects of the guidance. The methodology identifies site-specific risk assessment considerations and integrates them with approaches for evaluating human and ecological risk that can be factored into the risk assessment program supporting the Hanford Site cleanup mission. Consequently, the methodology will enhance the preparation and review of individual risk assessments at the Hanford Site

  12. [Clinical study of the effect of preventing dentine hypersensitiveness by using Fluor Protector and Green Or on the prepared vital pulp abutment teeth].

    Science.gov (United States)

    Qin, Jia-nan; Lu, Yu-miao; Zhou, Xiao-yan

    2005-04-01

    To study and evaluate the effect preventing dentine hypersensitiveness by using Fluor Protector or Green Or on the prepared vital pulp abutment teeth of PFM bridges. 118 cases, 246 prepared vital pulp abutment teeth, were randomly divided into three groups: Experimental Group A--treated with the Fluor Protector and temporary crown; Experimental Group B--treated with the Green Or and temporary crown, and Control Group--only using temporary crown. The results of desensitization in 3 groups were evaluated. F test was used for analysis (DSPV6.01). Significant differences were found between experimental Group A, B and the control group after 1 week (when cementing the PFM bridges); and also after 1 month (P0.05). The effect of preventing dental hypersensitiveness by using Fluor Protector or Green Or on the prepared vital pulp abutment teeth of PFM bridges is ideal. It is easy to use and worth being widely applied.

  13. Practical application of the ALARA principle in management of the nuclear legacy: optimization under uncertainty

    International Nuclear Information System (INIS)

    Smith, Graham; Sneve, Malgorzata K.

    2008-01-01

    Full text: Radiological protection has a long and distinguished history in taking a balanced approach to optimization. Both utilitarian and individual interests and perspectives are addressed through a process of constrained optimisation, with optimisation intended to lead to the most benefit to the most people, and constraints being operative to limit the degree of inequity among the individuals exposed. At least, expressed simplistically, that is what the recommendations on protection are intended to achieve. This paper examines the difficulties in achieving that objective, based on consideration of the active role of optimisation in regulatory supervision of the historic nuclear legacy. This example is chosen because the application of the ALARA principle has important implications for some very major projects whose objective is remediation of existing legacy facilities. But it is also relevant because timely, effective and cost efficient completion of those projects has implications for confidence in the future development of nuclear power and other uses of radioactive materials. It is also an interesting example because legacy management includes mitigation of some major short and long term hazards, but those mitigating measures themselves involve operations with their own risk, cost and benefit profiles. Like any other complex activity, a legacy management project has to be broken down into logistically feasible parts. However, from a regulatory perspective, simultaneous application of ALARA to worker protection, major accident risk mitigation and long-term environmental and human health protection presents its own challenges. Major uncertainties which exacerbate the problem arise from ill-characterised source terms, estimation of the likelihood of unlikely failures in operational processes, and prospective assessment of radiological impacts over many hundreds of years and longer. The projects themselves are set to run over decades, during which time the

  14. The Hanford Site: An anthology of early histories

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1993-10-01

    This report discusses the following topics: Memories of War: Pearl Harbor and the Genesis of the Hanford Site; safety has always been promoted at the Hanford Site; women have an important place in Hanford Site history; the boom and bust cycle: A 50-year historical overview of the economic impacts of Hanford Site Operations on the Tri-Cities, Washington; Hanford's early reactors were crucial to the sites's history; T-Plant made chemical engineering history; the UO 3 plant has a long history of service. PUREX Plant: the Hanford Site's Historic Workhorse. PUREX Plant Waste Management was a complex challenge; and early Hanford Site codes and jargon

  15. Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA; Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Sullivan, S.G.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

    1994-01-01

    Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report was prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health. It contains the fifth in a series of bibliographies on dose reduction at DOE facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE`s Office of Environment, Safety and Health, to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and accelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts.

  16. Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA; Volume 5

    International Nuclear Information System (INIS)

    Dionne, B.J.; Sullivan, S.G.; Baum, J.W.

    1994-01-01

    Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report was prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health. It contains the fifth in a series of bibliographies on dose reduction at DOE facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE's Office of Environment, Safety and Health, to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and accelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts

  17. Hanford performance evaluation program for Hanford site analytical services

    International Nuclear Information System (INIS)

    Markel, L.P.

    1995-09-01

    The U.S. Department of Energy (DOE) Order 5700.6C, Quality Assurance, and Title 10 of the Code of Federal Regulations, Part 830.120, Quality Assurance Requirements, states that it is the responsibility of DOE contractors to ensure that ''quality is achieved and maintained by those who have been assigned the responsibility for performing the work.'' Hanford Analytical Services Quality Assurance Plan (HASQAP) is designed to meet the needs of the Richland Operations Office (RL) for maintaining a consistent level of quality for the analytical chemistry services provided by contractor and commmercial analytical laboratory operations. Therefore, services supporting Hanford environmental monitoring, environmental restoration, and waste management analytical services shall meet appropriate quality standards. This performance evaluation program will monitor the quality standards of all analytical laboratories supporting the Hanforad Site including on-site and off-site laboratories. The monitoring and evaluation of laboratory performance can be completed by the use of several tools. This program will discuss the tools that will be utilized for laboratory performance evaluations. Revision 0 will primarily focus on presently available programs using readily available performance evaluation materials provided by DOE, EPA or commercial sources. Discussion of project specific PE materials and evaluations will be described in section 9.0 and Appendix A

  18. Waste minimization -- Hanford`s strategy for sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Merry, D.S.

    1998-01-30

    The Hanford Site cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single-shell storage tanks, treating waste stored in 28 double-shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored onsite, removing thousands of structures, and dealing with significant solid waste, groundwater, and land restoration issues. The Pollution Prevention/Waste Minimization (P2/WMin) Program supports the Hanford Site mission to safely clean up and manage legacy waste and to develop and deploy science and technology in many ways. Once such way is through implementing and documenting over 231 waste reduction projects during the past five years, resulting in over $93 million in cost savings/avoidances. These savings/avoidances allowed other high priority cleanup work to be performed. Another way is by exceeding the Secretary of Energy`s waste reduction goals over two years ahead of schedule, thus reducing the amount of waste to be stored, treated and disposed. Six key elements are the foundation for these sustained P2/WMin results.

  19. Hanford Environmental Information System (HEIS)

    International Nuclear Information System (INIS)

    1994-01-01

    This report discusses the procedures that establish the configuration control processes for the Hanford Environmental Information System (HEIS) software. The procedures also provide the charter and function of the HEIS Configuration Control Board (CCB) for maintaining software. The software configuration control items covered under these procedures include the HEIS software and database structure. The configuration control processes include both administrative and audit functions. The administrative role includes maintaining the overall change schedule, ensuring consistency of proposed changes, negotiating change plan adjustments, setting priorities, and tracking the status of changes. The configuration control process audits to ensure that changes are performed to applicable standards

  20. Hanford Environmental Information System (HEIS)

    International Nuclear Information System (INIS)

    Schreck, R.I.

    1994-01-01

    The Hanford Environmental Information System (HEIS) Subject Area manuals are designed as reference guides, that is, each chapter provides the information needed to make best use of each subject area, its tables, and reporting capabilities. Each subject area is documented in a chapter in one of the subject area manuals. Because these are reference manuals, most of the information is also available in the online help system as well. See Section 5.4.2 of the HEIS User's Guide (DOE-RL 1994a) for a detailed description of the online help

  1. Polyurethane/fluor-hydroxyapatite nanocomposite scaffolds for bone tissue engineering. Part I: morphological, physical, and mechanical characterization

    Science.gov (United States)

    Asefnejad, Azadeh; Behnamghader, Aliasghar; Khorasani, Mohammad Taghi; Farsadzadeh, Babak

    2011-01-01

    In this study, new nano-fluor-hydroxyapatite (nFHA)/polyurethane composite scaffolds were fabricated for potential use in bone tissue engineering. Polyester urethane samples were synthesized from polycaprolactone, hexamethylene diisocyanate, and 1,4-butanediol as chain extender. Nano fluor-hydroxyapatite (nFHA) was successfully synthesized by sol-gel method. The solid–liquid phase separation and solvent sublimation methods were used for preparation of the porous composites. Mechanical properties, chemical structure, and morphological characteristics of the samples were investigated by compressive test, Fourier transform infrared, and scanning electron microscopy (SEM) techniques, respectively. The effect of nFHA powder content on porosity and pore morphology was investigated. SEM images demonstrated that the scaffolds were constituted of interconnected and homogeneously distributed pores. The pore size of the scaffolds was in the range 50–250 μm. The result obtained in this research revealed that the porosity and pore average size decreased and compressive modulus increased with nFHA percentage. Considering morphological, physical, and mechanical properties, the scaffold with a higher ratio of nFHA has suitable potential use in tissue regeneration. PMID:21289986

  2. Spectrographic determination of chlorine and fluorine; Dosage du chlore et du fluor par spectrographie d'emission en atmosphere inerte

    Energy Technology Data Exchange (ETDEWEB)

    Contamin, G [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1965-04-01

    Experimental conditions have been investigated in order to obtain the highest sensitivity in spectrographic determination of chlorine and fluorine using the Fassel method of excitation in an inert atmosphere. The influence of the nature of the atmosphere, of the discharge conditions and of the matrix material has been investigated. The following results have been established: 1. chlorine determination is definitely possible: a working curve has been drawn between 10 {mu}g and 100 {mu}g, the detection limit being around 5 {mu}g; 2. fluorine determination is not satisfactory: the detection limit is still of the order of 80 {mu}g. The best operating conditions have been defined for both elements. (author) [French] Nous avons recherche quelles etaient les conditions permettant d'obtenir la meilleure sensibilite dans le dosage spectrographique du chlore et du fluor par la methode d'excitation en atmosphere inerte (methode de Fassel). Nous avons etudie l'influence de l'atmosphere gazeuse, des conditions de la decharge et du materiau de pastillage. Les points suivants ont ete etablis: 1. le dosage du chlore est possible: une courbe de dosage a ete tracee entre 10 {mu}g et 100 {mu}g et la limite de detection est de l'ordre de 5 {mu}g; 2. le dosage du fluor n'est pas satisfaisant: la limite de detection obtenue etant encore de l'ordre de 80 {mu}g. Les conditions operatoires ont ete precisees pour ces deux elements. (auteur)

  3. LESSONS LEARNED FROM CLEANING OUT THE SLUDGE FROM THE SPENT FUEL STORAGE BASINS AT HANFORD ICEM-07

    Energy Technology Data Exchange (ETDEWEB)

    KNOLLMEYER PM

    2007-08-31

    Until 2004, the K Basins at Hanford, in southeastern Washington State, held the largest collection of spent nuclear fuel in the United States Department of Energy (DOE) complex. The K East and K West Basins are massive pools each holding more than 4 million liters of water - that sit less than 450 meters from the Columbia River. In a significant multi-year campaign that ended in 2004, Fluor Hanford removed all of the fuel from the two Basins, over 2,300 metric tons (4.6 million pounds), dried it, and then placed it into dry storage in a specially designed facility away from the River. Removing the fuel, however, did not finish the cleanup work at the K Basins. The years of underwater storage had corroded the metallic uranium fuel, leaving behind a thick and sometimes hard-packed layer of sludge that coated the walls, floors and equipment inside the Basins. In places, the depth of the sludge was measured in feet rather than inches, and its composition was definitely not uniform. Together the Basins held an estimated 50 cubic meters of sludge (42 cubic meters in K East and 8 cubic meters in K West). The K East sludge retrieval and transfer work was completed in May 2007. Vacuuming up the sludge into large underwater containers in each of the Basins and then consolidating it all in containers in the K West Basin have presented significant challenges, some unexpected. This paper documents some of those challenges and presents the lessons learned so that other nuclear cleanup projects can benefit from the experience at Hanford.

  4. LESSONS LEARNED FROM CLEANING OUT THE SLUDGE FROM THE SPENT FUEL STORAGE BASINS AT HANFORD ICEM-07

    International Nuclear Information System (INIS)

    KNOLLMEYER PM

    2007-01-01

    Until 2004, the K Basins at Hanford, in southeastern Washington State, held the largest collection of spent nuclear fuel in the United States Department of Energy (DOE) complex. The K East and K West Basins are massive pools each holding more than 4 million liters of water - that sit less than 450 meters from the Columbia River. In a significant multi-year campaign that ended in 2004, Fluor Hanford removed all of the fuel from the two Basins, over 2,300 metric tons (4.6 million pounds), dried it, and then placed it into dry storage in a specially designed facility away from the River. Removing the fuel, however, did not finish the cleanup work at the K Basins. The years of underwater storage had corroded the metallic uranium fuel, leaving behind a thick and sometimes hard-packed layer of sludge that coated the walls, floors and equipment inside the Basins. In places, the depth of the sludge was measured in feet rather than inches, and its composition was definitely not uniform. Together the Basins held an estimated 50 cubic meters of sludge (42 cubic meters in K East and 8 cubic meters in K West). The K East sludge retrieval and transfer work was completed in May 2007. Vacuuming up the sludge into large underwater containers in each of the Basins and then consolidating it all in containers in the K West Basin have presented significant challenges, some unexpected. This paper documents some of those challenges and presents the lessons learned so that other nuclear cleanup projects can benefit from the experience at Hanford

  5. DEVELOPING AND QUANTIFYING PARAMETERS FOR CLOSURE WELDING OVERPACKS CONTAINING RESEARCH REACTOR SPENT NUCLEAR FUEL AT HANFORD

    International Nuclear Information System (INIS)

    CANNELL GR

    2007-01-01

    Fluor engineers developed a Gas Tungsten Arc Welding (GTAW) technique and parameters, demonstrated requisite weld quality and successfully closure-welded packaged spent nuclear fuel (SNF) overpacks at the Hanford Site. This paper reviews weld development and qualification activities associated with the overpack closure-welding and provides a summary of the production campaign. The primary requirement of the closure weld is to provide leaktight confinement of the packaged material against release to the environment during interim storage (40-year design term). Required weld quality, in this case, was established through up-front development and qualification, and then verification of parameter compliance during production welding. This approach was implemented to allow for a simpler overpack design and more efficient production operations than possible with approaches using routine post-weld testing and nondestructive examination (NDE). . A series of welding trials were conducted to establish the desired welding technique and parameters. Qualification of the process included statistical evaluation and American Society of Mechanical Engineers (ASME) Section IX testing. In addition, pull testing with a weighted mockup, and thermal calculation/physical testing to identify the maximum temperature the packaged contents would be subject to during welding, was performed. Thirteen overpacks were successfully packaged and placed into interim storage. The closure-welding development activities (including pull testing and thermal analysis) provided the needed confidence that the packaged SNF overpacks could be safely handled and placed into interim storage, and remain leaktight for the duration of the storage term

  6. Managing the radiological risk: ALARA, a principle, an obligation, a state of mind

    International Nuclear Information System (INIS)

    Lefaure, C.

    1995-01-01

    According to the 1993 data published by French nuclear operators and by the Ionizing Radiations Protection Office (OPRI), only two workers have exceeded the maximum annual permissible dose of 50 mSv. However, the respect of dose limits is not a sufficient warranty to accept the ionizing radiations exposure risk. The ALARA (As Low As Reasonably Achievable) principle is a masterpiece of the radiological protection system. Its goal is to maintain the exposures as low as reasonably achievable taking into account the socio-economical constraints. In France, the application of this principle is as compulsory as the respect of dose limits. The proper management and optimization of radiological risk requires the motivation of everybody. (J.S.). 2 refs., 3 figs

  7. Optimisation of structural shielding of accelerator control room for compliance with ALARA principle under Indian conditions

    International Nuclear Information System (INIS)

    Ahmad, Masood; Singh, Brijesh

    1999-01-01

    The case of a 20 MV x-ray accelerator has been considered in this paper for optimisation. An internationally recommended value of α = US$ 1000 per person-sievert has been assumed. Cost of concrete has been assumed as US$ 82.7/m 3 . It is seen that, extra shielding is needed to satisfy the ALARA principle. Further, the amount of requisite shielding increases with the degree of occupancy and, also, if the local construction materials or the labour are cheaper than considered in this paper. Accordingly 1.5 to 4.75 HVLs may be needed as extra shielding in different situations. Therefore, a site specific and installation specific optimisation of shielding is necessary

  8. Use of rank sum method in identifying high occupational dose jobs for ALARA implementation

    International Nuclear Information System (INIS)

    Cho, Yeong Ho; Kang, Chang Sun

    1998-01-01

    The cost-effective reduction of occupational radiation exposure (ORE) dose at a nuclear power plant could not be achieved without going through an extensive analysis of accumulated ORE dose data of existing plants. It is necessary to identify what are high ORE jobs for ALARA implementation. In this study, the Rank Sum Method (RSM) is used in identifying high ORE jobs. As a case study, the database of ORE-related maintenance and repair jobs for Kori Units 3 and 4 is used for assessment, and top twenty high ORE jobs are identified. The results are also verified and validated using the Friedman test, and RSM is found to be a very efficient way of analyzing the data. (author)

  9. BNL ALARA center's development of a computerized Radiological Assessment and Design System (RADS)

    International Nuclear Information System (INIS)

    Dionne, B.J.; Connelly, J.M.

    1993-01-01

    The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation at DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of open-quotes good-practice documentsclose quotes will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called open-quotes Radiological Assessment and Design Systemclose quotes (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analysis, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative ratings of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

  10. BNL ALARA Center's development of a computerized radiological assessment and design system (RADS)

    International Nuclear Information System (INIS)

    Dionne, B.J.; Masciulli, S.; Connelly, J.M.

    1993-01-01

    The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation of DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of good-practice documents will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called Radiological Assessment and Design System (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analyses, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative rating of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

  11. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Willis, N.P.; Triner, G.C.

    1991-09-01

    Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

  12. Hanford 200 Areas Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Rinne, C.A.; Daly, K.S.

    1993-08-01

    The purpose of the Hanford 200 Areas Development Plan (Development Plan) is to guide the physical development of the 200 Areas (which refers to the 200 East Area, 200 West Area, and 200 Area Corridor, located between the 200 East and 200 West Areas) in accordance with US Department of Energy (DOE) Order 4320.lB (DOE 1991a) by performing the following: Establishing a land-use plan and setting land-use categories that meet the needs of existing and proposed activities. Coordinating existing, 5-year, and long-range development plans and guiding growth in accordance with those plans. Establishing development guidelines to encourage cost-effective development and minimize conflicts between adjacent activities. Identifying site development issues that need further analysis. Integrating program plans with development plans to ensure a logical progression of development. Coordinate DOE plans with other agencies [(i.e., Washington State Department of Ecology (Ecology) and US Environmental Protection Agency (EPA)]. Being a support document to the Hanford Site Development Plan (DOE-RL 1990a) (parent document) and providing technical site information relative to the 200 Areas.

  13. Cancer mortality in Hanford workers

    International Nuclear Information System (INIS)

    Marks, S.; Gilbert, E.S.; Breitenstein, B.D.

    1978-01-01

    Personnel and radiation exposure data for past and present employees of the Hanford plant have been collected and analysed for a possible relationship of exposure to mortality. The occurrence of death in workers was established by the Social Security Administration and the cause of death obtained from death certificates. Mortality from all causes, all cancer cases and specific cancer types was related to the population at risk. Standardized mortality ratios were calculated for white males, using age- and calendar year-specific mortality rates for the U.S. population in the calculation of expected deaths. This analysis showed a substantial 'healthy worker effect' and no significantly high standardized mortality ratios for specific disease categories. A test for association of mortality with levels of radiation exposure revealed no correlation for all causes and all cancer. In carrying out this test, adjustment was made for age and calendar year of death, length of employment and occupational category. A statistically significant test for trend was obtained for multiple myeloma and carcinoma of the pancreas. However, in view of the absence of such a correlation for diseases more commonly associated with radiation exposure such as myeloid leukaemia, as well as the small number of deaths in higher exposure groups, the results cannot be considered definitive. Any conclusions based on these associations should be viewed in relation to the results of other studies. These results are compared with those of other investigators who have analysed the Hanford data. (author)

  14. Hanford transuranic storage corrosion review

    International Nuclear Information System (INIS)

    Nelson, J.L.; Divine, J.R.

    1980-12-01

    The rate of atmospheric corrosion of the transuranic (TRU) waste drums at the US Department of Energy's Hanford Project, near Richland, Washington, was evaluated by Pacific Northwest Laboratory (PNL). The rate of corrosion is principally contingent upon the effects of humidity, airborne pollutants, and temperature. Results of the study indicate that actual penetration of barrels due to atmospheric corrosion will probably not occur within the 20-year specified recovery period. Several other US burial sites were surveyed, and it appears that there is sufficient uncertainty in the available data to prevent a clearcut statement of the corrosion rate at a specific site. Laboratory and site tests are recommended before any definite conclusions can be made. The corrosion potential at the Hanford TRU waste site could be reduced by a combination of changes in drum materials (for example, using galvanized barrels instead of the currently used mild steel barrels), environmental exposure conditions (for example, covering the barrels in one of numerous possible ways), and storage conditions

  15. Hanford 200 Areas Development Plan

    International Nuclear Information System (INIS)

    Rinne, C.A.; Daly, K.S.

    1993-08-01

    The purpose of the Hanford 200 Areas Development Plan (Development Plan) is to guide the physical development of the 200 Areas (which refers to the 200 East Area, 200 West Area, and 200 Area Corridor, located between the 200 East and 200 West Areas) in accordance with US Department of Energy (DOE) Order 4320.lB (DOE 1991a) by performing the following: Establishing a land-use plan and setting land-use categories that meet the needs of existing and proposed activities. Coordinating existing, 5-year, and long-range development plans and guiding growth in accordance with those plans. Establishing development guidelines to encourage cost-effective development and minimize conflicts between adjacent activities. Identifying site development issues that need further analysis. Integrating program plans with development plans to ensure a logical progression of development. Coordinate DOE plans with other agencies [(i.e., Washington State Department of Ecology (Ecology) and US Environmental Protection Agency (EPA)]. Being a support document to the Hanford Site Development Plan (DOE-RL 1990a) (parent document) and providing technical site information relative to the 200 Areas

  16. An Integrated Biological Control System At Hanford

    International Nuclear Information System (INIS)

    Johnson, A.R.; Caudill, J.G.; Giddings, R.F.; Rodriguez, J.M.; Roos, R.C.; Wilde, J.W.

    2010-01-01

    In 1999 an integrated biological control system was instituted at the U.S. Department of Energy's Hanford Site. Successes and changes to the program needed to be communicated to a large and diverse mix of organizations and individuals. Efforts at communication are directed toward the following: Hanford Contractors (Liquid or Tank Waste, Solid Waste, Environmental Restoration, Science and Technology, Site Infrastructure), General Hanford Employees, and Hanford Advisory Board (Native American Tribes, Environmental Groups, Local Citizens, Washington State and Oregon State regulatory agencies). Communication was done through direct interface meetings, individual communication, where appropriate, and broadly sharing program reports. The objectives of the communication efforts was to have the program well coordinated with Hanford contractors, and to have the program understood well enough that all stakeholders would have confidence in the work performed by the program to reduce or elimate spread of radioactive contamination by biotic vectors. Communication of successes and changes to an integrated biological control system instituted in 1999 at the Department of Energy's Hanford Site have required regular interfaces with not only a diverse group of Hanford contractors (i.e., those responsible for liquid or tank waste, solid wastes, environmental restoration, science and technology, and site infrastructure), and general Hanford employees, but also with a consortium of designated stake holders organized as the Hanford Advisory Board (i.e., Native American tribes, various environmental groups, local citizens, Washington state and Oregon regulatory agencies, etc.). Direct interface meetings, individual communication where appropriate, and transparency of the biological control program were the methods and outcome of this effort.

  17. AN INTEGRATED BIOLOGICAL CONTROL SYSTEM AT HANFORD

    Energy Technology Data Exchange (ETDEWEB)

    JOHNSON AR; CAUDILL JG; GIDDINGS RF; RODRIGUEZ JM; ROOS RC; WILDE JW

    2010-02-11

    In 1999 an integrated biological control system was instituted at the U.S. Department of Energy's Hanford Site. Successes and changes to the program needed to be communicated to a large and diverse mix of organizations and individuals. Efforts at communication are directed toward the following: Hanford Contractors (Liquid or Tank Waste, Solid Waste, Environmental Restoration, Science and Technology, Site Infrastructure), General Hanford Employees, and Hanford Advisory Board (Native American Tribes, Environmental Groups, Local Citizens, Washington State and Oregon State regulatory agencies). Communication was done through direct interface meetings, individual communication, where appropriate, and broadly sharing program reports. The objectives of the communication efforts was to have the program well coordinated with Hanford contractors, and to have the program understood well enough that all stakeholders would have confidence in the work performed by the program to reduce or elimated spread of radioactive contamination by biotic vectors. Communication of successes and changes to an integrated biological control system instituted in 1999 at the Department of Energy's Hanford Site have required regular interfaces with not only a diverse group of Hanford contractors (i.e., those responsible for liquid or tank waste, solid wastes, environmental restoration, science and technology, and site infrastructure), and general Hanford employees, but also with a consortium of designated stake holders organized as the Hanford Advisory Board (i.e., Native American tribes, various environmental groups, local citizens, Washington state and Oregon regulatory agencies, etc.). Direct interface meetings, individual communication where appropriate, and transparency of the biological control program were the methods and outcome of this effort.

  18. Overview of the Hanford risk management plan

    International Nuclear Information System (INIS)

    Halverson, T.G.

    1998-01-01

    The Project Hanford Management Contract called for the enhancement of site-wide decision processes, and development of a Hanford Risk Management Plan to adopt or develop a risk management system for the Hanford Site. This Plan provides a consistent foundation for Site issues and addresses site-wide management of risks of all types. It supports the Department of Energy planning and sitewide decision making policy. Added to this requirement is a risk performance report to characterize the risk management accomplishments. This paper presents the development of risk management within the context of work planning and performance. Also discussed are four risk elements which add value to the context

  19. Hanford's Radioactive Mixed Waste Disposal Facility

    International Nuclear Information System (INIS)

    McKenney, D.E.

    1995-01-01

    The Radioactive Mixed Waste Disposal Facility, is located in the Hanford Site Low-Level Burial Grounds and is designated as Trench 31 in the 218-W-5 Burial Ground. Trench 31 is a Resource Conservation and Recovery Act compliant landfill and will receive wastes generated from both remediation and waste management activities. On December 30, 1994, Westinghouse Hanford Company declared readiness to operate Trench 31, which is the Hanford Site's (and the Department of Energy complex's) first facility for disposal of low-level radioactive mixed wastes

  20. Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel

    International Nuclear Information System (INIS)

    Lochard, Jacques; Lefaure, Christian

    1990-01-01

    This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example

  1. Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel

    International Nuclear Information System (INIS)

    Lochard, Jacques; Lefaure, Christian

    1989-12-01

    This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example

  2. Hanford Laboratories monthly activities report, November 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-12-15

    This is the monthly report for the Hanford Laboratories Operation, November 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research.

  3. Hanford Laboratories monthly activities report, March 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-04-15

    This is the monthly report for the Hanford Laboratories Operation March 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

  4. Hanford Site baseline risk assessment methodology

    International Nuclear Information System (INIS)

    1992-03-01

    This report describes risk assessment methodology associated with the remedial action programs at the Hanford Reservation. Topics addressed include human health evaluation, pollutant and radionuclide transport through the environment, and environmental transport pathways

  5. Hanford Laboratories monthly activities report, December 1963

    Energy Technology Data Exchange (ETDEWEB)

    1964-01-15

    The monthly report for the Hanford Laboratories Operation, December 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.

  6. Hanford Environmental Information System Configuration Management Plan

    International Nuclear Information System (INIS)

    1996-06-01

    The Hanford Environmental Information System (HEIS) Configuration Management Plan establishes the software and data configuration control requirements for the HEIS and project-related databases maintained within the Environmental Restoration Contractor's data management department

  7. Hanford Laboratories monthly activities report, October 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-11-15

    This is the monthly report for the Hanford Laboratories Operation, October 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

  8. Hanford Laboratories monthly activities report, January 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-02-14

    This is the monthly report for the Hanford Laboratories Operation, January 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

  9. Hanford Laboratories monthly activities report, August 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-09-16

    This is the monthly report for the Hanford Laboratories Operation, August 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

  10. Hanford Laboratories monthly activities report, May 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-06-15

    This is the monthly report for the Hanford Laboratories Operation, May 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

  11. Hanford Laboratories monthly activities report, January 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-02-15

    This is the monthly report for the Hanford Laboratories Operation January 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

  12. Hanford Laboratories monthly activities report, September 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-10-15

    This is the monthly report for the Hanford Laboratories Operation, September 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

  13. Hanford Laboratories monthly activities report, July 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-08-15

    This is the monthly report for the Hanford Laboratories Operation, July 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

  14. Hanford Laboratories monthly activities report, May 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-06-14

    The monthly report for the Hanford Laboratories Operation, May 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operation are discussed.

  15. Hanford Laboratories monthly activities report, February 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-03-16

    This is the monthly report for the Hanford Laboratories Operation, February, 1964. Reactor fuels, chemistry, dosimetry, separation process, reactor technology financial activities, biology operation, physics and instrumentation research, employee relations, applied mathematics, programming, and radiation protection are discussed.

  16. Hanford Laboratories monthly activities report, June 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-07-15

    This is the monthly report for the Hanford Laboratories Operation, June 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

  17. Continuing study of mortality in Hanford workers

    International Nuclear Information System (INIS)

    Marks, S.; Gilbert, E.S.

    1979-10-01

    The mortality of workers at the Hanford Plant in southeastern Washington who have been exposed to penetrating external ionizing radiation is studied. Deaths are analyzed statistically and compared to standardized mortality ratios. Cancer deaths in particular are examined

  18. Hanford Laboratories monthly activities report, April 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-05-15

    This is the monthly report for the Hanford Laboratories Operation, April 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

  19. Hanford Laboratories monthly activities report, July 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-08-14

    This is the monthly report for the Hanford Laboratories Operation, July 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

  20. Hanford Laboratories monthly activities report, March 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-04-15

    The monthly report for the Hanford Laboratories Operation, March 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operation, and programming operations are discussed.

  1. Hanford Laboratories monthly activities report, April, 1963

    Energy Technology Data Exchange (ETDEWEB)

    1963-05-15

    This is the monthly report for the Hanford Laboratories Operation, April, 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, biology operation, physics and instrumentation research, employee relations, applied mathematics operation, programming, and radiation protection operation discussed.

  2. Hanford Laboratories monthly activities report, August 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-09-15

    The monthly report for the Hanford Laboratories Operation, August 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.

  3. Hanford Laboratories monthly activities report, October 1964

    Energy Technology Data Exchange (ETDEWEB)

    1964-11-16

    The monthly report for the Hanford Laboratories Operation, October 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operations are discussed.

  4. FluorWPS: A Monte Carlo ray-tracing model to compute sun-induced chlorophyll fluorescence of three-dimensional canopy

    Science.gov (United States)

    A model to simulate radiative transfer (RT) of sun-induced chlorophyll fluorescence (SIF) of three-dimensional (3-D) canopy, FluorWPS, was proposed and evaluated. The inclusion of fluorescence excitation was implemented with the ‘weight reduction’ and ‘photon spread’ concepts based on Monte Carlo ra...

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

    International Nuclear Information System (INIS)

    SONNICHSEN, J.C.

    2000-01-01

    As directed by the U.S. Department of Energy (DOE), Richland Operations Office (DOE-RL), Fluor Hanford, Inc. will implement the requirements of DOE Order 435.1, Radioactive Waste Management, as the requirements relate to the continued operation of the low-level waste disposal facilities on the Hanford Site. DOE Order 435.1 requires a disposal authorization statement authorizing operation (or continued operation) of a low-level waste disposal facility. The objective of this Order is to ensure that all DOE radioactive waste is managed in a manner that protects the environment and personnel and public health and safety. The manual (DOE Order 435.1 Manual) implementing the Order states that a disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) of 1980 documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility. Failure to obtain a disposal authorization statement shall result in shutdown of an operational disposal facility. In fulfillment of the requirements of DOE Order 435.1, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area and the 200 West Area Low-Level Burial Grounds. The disposal authorization statement constitutes approval of the performance assessment and composite analysis, authorizes operation of the facility, and includes conditions that the disposal facility must meet. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area Low-Level Burial Grounds be written and approved by the DOE-RL. The monitoring plan is to be updated and implemented within 1 year following issuance of the disposal authorization statement to

  6. Hanford Engineer Works technical manual

    Energy Technology Data Exchange (ETDEWEB)

    1944-05-01

    The uranium metal, as discharged from the piles in the 100 Areas, contains the alpha emitting product, plutonium, in concentration in the neighborhood of 150--250 grams per metric ton, along with similar amounts of beta and gamma fission elements. It is the purpose of the Separations Plant to effect the separation of this product from the uranium metal and fission elements, and to prepare a concentrated, relatively pure solution of plutonium nitrate as the final product of the Hanford Plant. This section of the manual discusses the chemistry of the separations process, describes the buildings and equipment provided for carrying out the various steps in the operation, and presents the detailed operating procedures used. There are included, in many instances, references to other documents presenting a more detailed view of a specific point in the process.

  7. Hanford Nuclear Energy Center study

    International Nuclear Information System (INIS)

    Harty, H.

    1976-01-01

    Studies of a Nuclear Energy Center (NEC) at Hanford have not revealed any insurmountable technical problems, but problems have been identified that appear to be more difficult to resolve than for dispersed siting. Major technical developments in meteorology, and probably in seismology, are needed before an environmental report or safety analysis report could be prepared for an NEC. It would be helpful in further NEC studies if licensing requirements (and related criteria) were defined for them. An NEC will likely cause a step change in the amount of planning and involvement of regional groups in the energy picture compared to dispersed siting. The tools that must be developed for analysis of NECs will probably be used for evaluating dispersed siting in greater detail. NECs will probably bring about the use of dry or wet/dry cooling before it is required in equivalent amount for dispersed plants

  8. Hanford cultural resources management plan

    Energy Technology Data Exchange (ETDEWEB)

    Chatters, J.C. (ed.)

    1989-06-01

    As a federal agency, the US Department of Energy (DOE) has been directed by Congress and the President to provide leadership in the preservation of prehistoric, historical, and cultural resources on lands it administers, to manage these in a spirit of stewardship for future generations, and to protect and preserve the rights of Native Americans to religious freedom. The purpose of this document is to describe how the DOE-Richland Operations (DOE-RL) will meet those responsibilities on the Hanford Site, pursuant to guidelines for Agency Responsibilities under the Historic Preservation Act (FR 53:31, February 17, 1988). This document is intended for multiple uses. Among other things, the text is designed as a manual for cultural resource managers to follow and as an explanation of the process of cultural resource regulatory compliance for the DOE-RL and Site contractors. 10 refs., 17 figs., 11 tabs.

  9. Hanford 300 Area Development Plan

    International Nuclear Information System (INIS)

    Daly, K.S.; Seiler, S.W.; Hail, J.C.

    1991-09-01

    The purpose of the Hanford 300 Area Development Plan (Development Plan) is to guide the physical development of the 300 Area in accordance with US Department of Energy (DOE) Order 4320.1B (DOE 1991b) by performing the following: (1) Establishing a land use plan, setting land use categories that meet the needs of existing and proposed activities; (2) Coordinating existing, 5-yr, and long-range development plans and guiding growth in accordance with those plans; (3) Establishing development guidelines to encourage cost-effective development and minimize conflicts between adjacent activities; (4) Identifying site development issues that need further analysis; Integrating program plans with development plans to ensure a logical progression of development; and, (6) Integrating DOE plans with local agency plans (i.e., city, country, state, and Tri-Cities Science and Technology Park plans)

  10. Aluminum precipitation from Hanford DSSF

    International Nuclear Information System (INIS)

    Borgen, D.; Frazier, P.; Staton, G.

    1994-01-01

    A series of pilot scale tests using simulated Double Shell Slurry Feed (DSSF) showed that well-settled aluminum precipitate can be produced in Hanford double shell tank (DST) high level waste by slow neutralization with carbon dioxide. This pretreatment could provide an early grout feed and free tank space, as well as facilitate downstream processes such as ion exchange by providing a less caustic feed. A total of eight test runs were completed using a 10-ft tall 3-in i.d. glass column. The 10-ft height corresponds to about one third of the vertical height of a DST, hence providing a reasonable basis for extrapolating the observed precipitate settling and compaction to the actual waste tank environment. Four runs (three with a simplified simulant and one with a chemically complete simulant) produced well settled precipitates averaging 1.5 to 2 feet high. Aluminum gel rather than settled precipitate resulted from one test where neutralization was too rapid

  11. Hanford Environmental Information System (HEIS)

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of the Tank Characterization Data subject area of the Hanford Environmental Information System (HEIS) is to manage data acquired from waste tank characterization efforts. Tank samples provide the data stored in this subject area. Also included are data from tank inventories. These data are analyzed to determine disposal requirements, such as suitability for grout or vitrification. The data provide the basis for developing safety analyses and closure plans, and for establishing and verifying compliance with waste acceptance specifications. Two major sources of data make up the tank characterization data subject area: Data from single-shell and double-shell tank core samples -- core sampling analytical results include physical properties, radionuclides, major chemicals, and hazardous components; and data from waste tank supernatant samples. Four types of data are stored in the TCD subject area. Qualifiers for TCD analytical result data are listed in Appendix A. Data loading and verification procedures are described in Appendix B

  12. Hanford Nuclear Energy Center study

    Energy Technology Data Exchange (ETDEWEB)

    Harty, H.

    1976-03-16

    Studies of a Nuclear Energy Center (NEC) at Hanford have not revealed any insurmountable technical problems, but problems have been identified that appear to be more difficult to resolve than for dispersed siting. Major technical developments in meteorology, and probably in seismology, are needed before an environmental report or safety analysis report could be prepared for an NEC. It would be helpful in further NEC studies if licensing requirements (and related criteria) were defined for them. An NEC will likely cause a step change in the amount of planning and involvement of regional groups in the energy picture compared to dispersed siting. The tools that must be developed for analysis of NECs will probably be used for evaluating dispersed siting in greater detail. NECs will probably bring about the use of dry or wet/dry cooling before it is required in equivalent amount for dispersed plants.

  13. Hanford: The evolution of a dinosaur

    International Nuclear Information System (INIS)

    Fulton, J.

    1995-01-01

    This article describes how the Westinghouse Hanford Company is reinventing the US DOE's Hanford Site, turning a 1940s-era dinosaur into a 1990s-style business. The major topics covered include the following: breaking the logjam by ending the inefficient cost-plus days; Concentrating resources on resolving urgent safety issues; contract reform with more incentive, greater risk; finally reengineering: the next step

  14. Hanford Environmental Dose Reconstruction Project monthly report

    International Nuclear Information System (INIS)

    Finch, S.M.

    1991-10-01

    The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doeses that individuals and populations could have received from nuclear operations at Hanford since 1944. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed, from release to impact on humans (dose estimates): Source terms; environmental transport; environmental monitoring data; demographics, agriculture, food habits; environmental pathways and dose estimates

  15. Hanford soil partitioning and vapor extraction study

    International Nuclear Information System (INIS)

    Yonge, D.; Hossain, A.; Cameron, R.; Ford, H.; Storey, C.

    1996-07-01

    This report describes the testing and results of laboratory experiments conducted to assist the carbon tetrachloride soil vapor extraction project operating in the 200 West Area of the Hanford Site in Richland, Washington. Vapor-phase adsorption and desorption testing was performed using carbon tetrachloride and Hanford Site soils to estimate vapor-soil partitioning and reasonably achievable carbon tetrachloride soil concentrations during active vapor extractions efforts at the 200 West Area. (CCl 4 is used in Pu recovery from aqueous streams.)

  16. Hanford Site Waste management units report

    International Nuclear Information System (INIS)

    1992-01-01

    This report summarizes the operable units in several areas of the Hanford Site Waste Facility. Each operable unit has several waste units (crib, ditch, pond, etc.). The operable units are summarized by describing each was unit. Some of the descriptions are unit name, unit type, waste category start data, site description, etc. The descriptions will vary for each waste unit in each operable unit and area of the Hanford Site

  17. Environmental surveillance at Hanford for CY 1977

    International Nuclear Information System (INIS)

    Houston, J.R.; Blumer, P.J.

    1978-04-01

    Environmental data collected during 1977 show continued compliance by Hanford with all applicable state and federal regulations. Data were collected for most environmental media including air, Columbia River water, external radiation, foodstuffs (milk, beef, eggs, poultry, and produce) and wildlife (deer, fish, game birds, and oysters from Willapa Bay), as well as soil and vegetation samples. In general, offsite levels of radionuclides attributable to Hanford operations during 1977 were indistinguishable from background levels

  18. History of Hanford Site Defense Production (Brief)

    Energy Technology Data Exchange (ETDEWEB)

    GERBER, M S

    2001-02-01

    This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history.

  19. Researchers take up environmental challenge at Hanford

    International Nuclear Information System (INIS)

    Illman, D.L.

    1993-01-01

    The Hanford nuclear site, built to produce plutonium for the nation's first atomic weapons, occupies 560 square miles of desert in southeastern Washington State. Only 29 months after ground was broken at the site in March 1943, the Hanford project delivered the plutonium used in the bomb that was dropped on Nagasaki, Japan, at the end of World War II. Secrecy surrounding the nuclear weapons program continued through the Cold War years, concealing the fact that for decades, hazardous and radioactive wastes were discharged to the ground, water, and air at Hanford. Only in 1986 were documents finally declassified--tens of thousands of them--describing the construction, operation, and maintenance of the Hanford facilities, allowing a picture to be pieced together of the environmental cost there of the nuclear weapons buildup. That cost may never be completely tallied. But Westinghouse Hanford, Co., the principal operations contractor on the site, and Pacific Northwest Laboratories (PNL), operated by Battelle Memorial Institute for the Department of Energy (DOE), have now begun working together to develop new technologies that are needed to address the short-term and long-term challenges of environmental restoration at Hanford. The paper discusses the problems and possible solutions that are being investigated

  20. Hanford Site Tank Waste Remediation System

    International Nuclear Information System (INIS)

    1993-05-01

    The US Department of Energy's (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives

  1. A corporative ALARA engineering support for all EDF sites a major improvement: the generic work areas optimization studies

    International Nuclear Information System (INIS)

    Quiot, A.; Lebeau, J.

    2005-01-01

    ALARA studies performed by EDF plants are quite simple and empirical. Most often, feedback experience and common sense, with the help of simple calculations allow reaching useful and efficient decisions. This is particularly the case when the exposure situations are not complex, within a simple environment and with a single source, or one major source. However, in more complex cases this is not enough to guarantee that actual ALARA solutions are implemented. EDF has then decided to use its national corporate engineering as a support for its sites. That engineering support is in charge of using very efficient tools such as PANTHER-RP. The objective of the presentation is to describe the engineering process and tools now available at EDF, to illustrate them with a few case studies and to describe the goals and procedures set up by EDF. (authors)

  2. A corporate ALARA engineering support for all EDF sites. A major improvement: the generic work areas optimisation studies

    Energy Technology Data Exchange (ETDEWEB)

    Quiot, Alain [EDF, SPT, UTO, Le Central, Bat. 420, BP 129, 93162 Noisy-le-Grand Cedex (France); Lebeau, Jacques [Electricite de France, ALARA Project, Site Cap Ampere, 1, place Pleyel, 93282 Saint Denis Cedex (France)

    2004-07-01

    ALARA studies performed by EDF plants are quite simple and empirical. Most often, feedback experience and common sense, with the help of simple calculations allow reaching useful and efficient decisions. This is particularly the case when the exposure situations are not complex, within a simple environment and with a single source, or one major source. However, in more complex cases this is not enough to guarantee that actual ALARA solutions are implemented. EDF has then decided to use its national corporate engineering as a support for its sites. That engineering support is in charge of using very efficient tools such as PANTHER-RP. The objective of the presentation is to describe the engineering process and tools now available at EDF, to illustrate them with a few case studies and to describe the goals and procedures set up by EDF. (authors)

  3. ALARA Review of the Activation/Repair of Fire Detectors in Zone Three at the 233-S Facility

    International Nuclear Information System (INIS)

    Kornish, M.J.

    1998-07-01

    A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure 1.22, 'Planning Radiological Work', when radiological conditions exceed trigger levels. The level of contamination inside the viewing room meets this criterion. This ALARA review is for task instruction 1997-03-18-005-8.3.3 (mini task instruction to a living work package), 'Instructions for D ampersand D Support of Fire Detector Troubleshooting and Minor Maintenance Work at 233-S,' and DynCorp 2G-98-7207C, '233-S Reconnect Smoke Detectors Zone 3.' The Radiological Work Permit (RWP) request broke these two task instructions into four separate tasks. The four tasks identified in the RWP request were used to estimate airborne concentrations and the total exposure

  4. Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA

    International Nuclear Information System (INIS)

    Baum, J.W.; Khan, T.A.

    1986-10-01

    This report is the third in a series of bibliographies supporting the efforts at Brookhaven National Laboratory on dose reduction at nuclear power plants. Abstracts for this report were selected from papers presented at recent technical meetings, journals and research reports reviewed at the BNL ALARA Center, and searches of the DOE/RECON data base on energy-related publications. The references selected for inclusion in the bibliography relate not only to operational health physics topics but also to plant chemistry, stress corrosion cracking, and other aspects of plant operation which have important impacts on occupational exposure. Also included are references to improved design, planning, materials selection and other topics related to what might be called ALARA engineering. Thus, an attempt has been made to cover a broad spectrum of topics related directly or indirectly to occupational exposure reduction. The report contains 252 abstracts and both author and subject indices

  5. Efektivitas Desensitizing Agent dengan dan tanpa Fluor pada Metode in Office Bleaching terhadap Kandungan Mineral Gigi (Kajian In Vitro

    Directory of Open Access Journals (Sweden)

    Yulita Kristanti

    2015-12-01

    Full Text Available In office bleaching menggunakan hidrogen peroksida 40% sering memberikan efek samping berupa linu baik selama maupun setelah perawatan tersebut dilakukan. Penelitian ini dilakukan dengan tujuan untuk mengetahui pengaruh waktu aplikasi dan kandungan fluor desensitizing agent pada metode in office bleaching terhadap kandungan mineral gigi. Delapan gigi masing-masing dipotong menjadi 4 bagian, 6 potong digunakan untuk pemeriksaan XRD awal. Gigi dikeringkan dalam oven suhu 50° selama 30 menit diserbuk, diambil 1 mg untuk diperiksa kandungan mineralnya dengan goniometer. Dua puluh empat potong yang lain dibagi dalam 4 kelompok perlakuan. Kelompok I: gigi diaplikasi bahan bleaching 0,5-1 mm hidrogen peroksida 40% selama 1 jam, dicuci, dikeringkan, diikuti aplikasi 0,1 ml desensitizing agent tanpa fluor (CPP-ACP selama 30 menit, dicuci, dikeringkan. Kelompok II : gigi diaplikasi CPP-ACP 30 menit, dicuci, dikeringkan, dibleaching menggunakan hidrogen peroksida 40% selama 1 jam. Selanjutnya gigi diaplikasi CPP-ACP 30 menit lagi, dicuci, dikeringkan. Kelompok III gigi dibleaching menggunakan hidrogen peroksida 40% selama 1 jam, dicuci, dikeringkan, diikuti aplikasi desensitizing agent yang mengandung fluor (CPP-ACFP selama 30 menit, dicuci, dikeringkan. Kelompok IV: gigi diaplikasi CPP-ACFP 30 menit, dicuci, dikeringkan, dibleaching menggunakan hidrogen peroksida 40% selama 1 jam. Selanjutnya gigi diaplikasi CPP-ACFP selama 30 menit, dicuci dikeringkan. Sesudah perlakuan, semua gigi dilakukan pemeriksaan kandungan mineral gigi dengan prosedur yang sama. Uji Mann Whitney menunjukkan penurunan mineral paling sedikit terjadi pada kelompok IV (4500. Desensitizing agent mengandung F sebelum dan sesudah perlakuan in office bleaching menunjukkan penurunan mineral paling kecil.   The Effectiveness of Desensitizing Agent with and without Fluorine in Office Bleaching Method to Tooth Mineral content. Tooth sensitivity arises during or after an in

  6. Use of computerized, 3-dimensional solids modeling and data base management to support radiation mapping and ALARA planning

    International Nuclear Information System (INIS)

    Schauss, R.D.; Slobodien, M.S.

    1986-01-01

    The RADiation Mapping and ALARA Planning System (RADMAPS) under development by GPU Nuclear Corporation in conjunction with Construction Systems Associates, Inc., integrates computerized solids modeling and data base management to provide an automated, integrated systems solution to the problems associated with acquiring, managing, and communicating plant radiological data at nuclear facilities. This presentation describes the status of the RADMAPS development and outlines plans for future expansion

  7. Excellence in occupational dose reduction in the new millennium: the first international Alara symposium in the 21st century

    International Nuclear Information System (INIS)

    Martin, A.

    2001-01-01

    The International Symposium ALARA 2001 on Radiological Protection Challenges in NPP's Management on the Verge of the XXI Century took place in Anaheim. California on February 5-7. In this congress, Anibal Martin, Vice-President of the Consejo de Seguridad Nuclear, received an honorable mention from the Health Physics Society for his professional career in the nuclear arena. After being awarded the commemorative plague, Anibal martin addressed the meeting. His speech is reproduced below. (Author)

  8. Radionuclide releases to the atmosphere from Hanford Operations, 1944--1972. Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Heeb, C.M.

    1994-05-01

    The purpose of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. The first step in determining dose is to estimate the amount and timing of radionuclide releases to air and water. This report provides the air release information.

  9. Implementation of ALARA radiation protection on the ISS through polyethylene shielding augmentation of the Service Module Crew Quarters

    Science.gov (United States)

    Shavers, M. R.; Zapp, N.; Barber, R. E.; Wilson, J. W.; Qualls, G.; Toupes, L.; Ramsey, S.; Vinci, V.; Smith, G.; Cucinotta, F. A.

    2004-01-01

    With 5-7 month long duration missions at 51.6° inclination in Low Earth Orbit, the ionizing radiation levels to which International Space Station (ISS) crewmembers are exposed will be the highest planned occupational exposures in the world. Even with the expectation that regulatory dose limits will not be exceeded during a single tour of duty aboard the ISS, the "as low as reasonably achievable" (ALARA) precept requires that radiological risks be minimized when possible through a dose optimization process. Judicious placement of efficient shielding materials in locations where crewmembers sleep, rest, or work is an important means for implementing ALARA for spaceflight. Polyethylene (C nH n) is a relatively inexpensive, stable, and, with a low atomic number, an effective shielding material that has been certified for use aboard the ISS. Several designs for placement of slabs or walls of polyethylene have been evaluated for radiation exposure reduction in the Crew Quarters (CQ) of the Zvezda (Star) Service Module. Optimization of shield designs relies on accurate characterization of the expected primary and secondary particle environment and modeling of the predicted radiobiological responses of critical organs and tissues. Results of the studies shown herein indicate that 20% or more reduction in equivalent dose to the CQ occupant is achievable. These results suggest that shielding design and risk analysis are necessary measures for reducing long-term radiological risks to ISS inhabitants and for meeting legal ALARA requirements. Verification of shield concepts requires results from specific designs to be compared with onboard dosimetry.

  10. ALARA review for the decontamination and decommissioning of the 233-S P.R. can loadout and decontamination

    International Nuclear Information System (INIS)

    Kornish, J.M.

    1998-01-01

    The 233-S Facility was completed in 1955 to expand plutonium production by further concentrating the plutonium nitrate product solution from the Reduction Oxidation (REDOX) Plant. The facility is radiologically contaminated because of operations and accidents. The building is presently a Hazard Category 2 Nuclear Facility. Disassembly of the loadout hood and its associated equipment may be done in parallel with the isolation of 233-S from REDOX via the pipe trench equipment removal. The work scope is to remove the entire loadout hood from the Product Receiver (P.R.) Can Loadout and Decon Room inside the 233-S Facility. A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure 1.22, Planning Radiological Work, when radiological conditions exceed trigger levels. The level of contamination inside the loadout hood and its associated equipment is unknown. The potential exists to exceed the level of loose surface contamination, which requires a formal ALARA review when opening the loadout hood and disassembly commences. This ALARA review is for the task instruction 1997-03-18-010 Revision 0, 233-S Loadout Hood Decon and Dismantlement

  11. Application of ALARA to transport of Radio-Isotopes for Medical use

    International Nuclear Information System (INIS)

    Fett, H. J.; Lange, F.; Schwarz, G.; Van Hienen, J. F. A.; Jansma, R.; Gelder, R.; Shaw, K. B.; Gulberg, O.; Josefsson, D.; Svahn, B.

    2002-01-01

    In 1999 a multi-national research project on transport safety commissioned by DG-TREN of the European Commission was completed and reported in The Evaluation of the Situation in the EC as regards Safety in the Transport of Radioactive Material and the Prospects for the Development of such Type of Transport (EC Contract No 4.1020/D/97-003. The result project was focussed on the radiological protection for routine (incident-free) shipments of radioactive material (RAM) in the public domain in four EU Member States Germany, the Netherlands, Sweden and the UK. This information satisfies the requirements of the Euratom Basic Safety Standards, Article 14, which calls for reasonable steps taken by EU Member States to ensure and to substantiate that the contribution to exposure from practices including transport operations involving radioactive substances, is kept as low as reasonably achievable (ALARA), economic and social factors being taken into account. The present paper, which has been partially based on the 1999 study for the European Commission, is focussed on the application of ALARA to the shipments by road in the four countries of radioactive material used for health care, research and industry. From the analysis of the data for these shipment it has been found that these shipments result in transport worker effective doses that vary from very low values which represent a major fraction of the applicable dose limit of 20 mSv/yr. From the primarily recorded worker radiation doses collected at the national level indicate, however, that the vast majority of transport workers, i. e. drivers and handlers, receive typically annual effective doses in the range of up to 10 mSv/yr with most values being in the low dose range. The maximum recorded occupational doses of workers involved primarily in manual handling, sorting and moving of high-T1 multiple-package radioisotope shipments at depots, re-distribution centres etc. were found to be from about 10-14 mSv/yr, From the

  12. Hanford science and technology needs statements document

    Energy Technology Data Exchange (ETDEWEB)

    Piper, L.L.

    1997-12-31

    This document is a compilation of the Hanford science and technology needs statements for FY 1998. The needs were developed by the Hanford Site Technology Coordination Group (STCG) with full participation and endorsement of site user organizations, stakeholders, and regulators. The purpose of this document is to: (a) provide a comprehensive listing of Hanford science and technology needs, and (b) identify partnering and commercialization opportunities with industry, other federal and state agencies, and the academic community. The Hanford STCG reviews and updates the needs annually. Once completed, the needs are communicated to DOE for use in the development and prioritization of their science and technology programs, including the Focus Areas, Cross-Cutting Programs, and the Environmental Management Science Program. The needs are also transmitted to DOE through the Accelerating Cleanup: 2006 Plan. The public may access the need statements on the Internet on: the Hanford Home Page (www.hanford.gov), the Pacific Rim Enterprise Center`s web site (www2.pacific-rim.org/pacific rim), or the STCG web site at DOE headquarters (em-52.em.doegov/ifd/stcg/stcg.htm). This page includes links to science and technology needs for many DOE sites. Private industry is encouraged to review the need statements and contact the Hanford STCG if they can provide technologies that meet these needs. On-site points of contact are included at the ends of each need statement. The Pacific Rim Enterprise Center (206-224-9934) can also provide assistance to businesses interested in marketing technologies to the DOE.

  13. Hydrogeologic model for the old Hanford townsite

    International Nuclear Information System (INIS)

    MacDonald, Q.; Csun, C.

    1994-01-01

    The Hanford Site in southeastern Washington state produced the country's first plutonium during WW II, and production continued through the end of the cold war. This plutonium production generated significant volumes of chemical and radioactive wastes, some of which were discharged directly to the local sediments as wastewater. Artifical recharge is still the dominating influence on the uppermost and unconfined aquifer over much of the Hanford site. Groundwater from a portion of this aquifer, which is in excess of drinking water standards for tritium, discharges to the Columbia River in the vicinity of the old Hanford townsite. The Hanford site lies within the Pasco basin, which is a structural basin in the Columbia Plateau. Columbia River basalt is overlain by the fluvial and lacustrian Ringold formation. The Ringold is unconformably overlain by the informal Hanford formation. Relatively impermeable basalt outcrops and subcrops along a northwest-southeast-trending anticline across the study area. Hanford sediments include both fluvial and glacial flood deposits lying on an irregular surface of basalt and sedimentary rocks. The coarser flood deposits have very high hydraulic conductivity and probably are the most important conduit for contaminant transport within the aquifer. A finite element model (CFEST-SC) is being used to study the effect of changing river stage on baseflow to the Columbia River near the old Hanford townsite. A steady-state version of the model produces calculated head within 1 m of observed values. Transient flow and solute transport results are expected to help further define the relationship between the contaminated aquifer and the Columbia River

  14. Environmental monitoring at Hanford for 1984

    International Nuclear Information System (INIS)

    Price, K.R.; Carlile, J.M.V.; Dirkes, R.L.; Jaquish, R.E.; Trevathan, M.S.; Woodruff, R.K.

    1985-05-01

    Environmental surveillance activities performed by the Pacific Northwest Laboratory for the Department of Energy's Hanford Site for 1984 are discussed in this report. Samples of environmental media were collected in support of the Hanford Environmental Monitoring Program to determine radionuclide concentrations in the Hanford environs. Radiological impacts in terms of radiation dose equivalents as a result of Hanford operations are also discussed. Gross beta radioactivity concentrations in airborne particulates at all sampling locations were lower in 1984 than during 1983 as a result of declining levels of worldwide fallout. Slightly higher levels of 85 Kr and 129 I were noted at several onsite and offsite locations. The sampling location in close proximity to the PUREX plant also detected increased 3 H. Very low levels of radionuclides were detected in samples of Columbia River water during 1984. An extensive groundwater monitoring program was performed for the Hanford Site during 1984. The 3 H and nitrate plumes continued to move slowly toward the Columbia River. All 3 H results were within applicable concentration guides. Samples of deer, rabbits, game birds, waterfowl and fish were collected onsite or in the Columbia River at locations where the potential for radionuclide uptake was most likely, or at the nearest locations where wildlife samples were available. Radioisotope levels were measured. Dose rates from external penetrating radiation measured in the vicinity of residential areas were similar to those observed in the previous years, and no contribution from Hanford activities could be identified. An assessment of the 1984 potential radiological impacts attributable to the Hanford operations indicated that measured and calculated radiation doses to the public continued to be low, and well below applicable regulatory limits. 21 refs., 48 figs., 83 tabs

  15. The Hanford Site: An anthology of early histories

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S.

    1993-10-01

    This report discusses the following topics: Memories of War: Pearl Harbor and the Genesis of the Hanford Site; safety has always been promoted at the Hanford Site; women have an important place in Hanford Site history; the boom and bust cycle: A 50-year historical overview of the economic impacts of Hanford Site Operations on the Tri-Cities, Washington; Hanford`s early reactors were crucial to the sites`s history; T-Plant made chemical engineering history; the UO{sub 3} plant has a long history of service. PUREX Plant: the Hanford Site`s Historic Workhorse. PUREX Plant Waste Management was a complex challenge; and early Hanford Site codes and jargon.

  16. Criticality codes migration to workstations at the Hanford site

    International Nuclear Information System (INIS)

    Miller, E.M.

    1993-01-01

    Westinghouse Hanford Company, Hanford Site Operations contractor, Richland, Washington, currently runs criticality codes on the Cray X-MP EA/232 computer but has recommended that US Department of Energy DOE-Richland replace the Cray with more economical workstations

  17. Magnetic study of solid uranium-fluorine complexes; Contribution a l'etude magnetique de composes fluores solides de l'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Dianoux, A J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-06-01

    A study of the magnetic susceptibility of uranium V fluorine complexes and of the magnetic resonance of fluorine atoms in uranium VI fluorine complexes has made it possible to put forward a structural model for these compounds for which it is impossible, because of the lack of suitable single crystals for X-ray diffraction work, to deduce the exact position of the fluorine atoms. It is shown that it is difficult to interpret the paramagnetism of uranium fluorides, because the uranium ions are in low-symmetry sites. A theoretical study of the magnetism of the U{sup V} ion in complex fluorides of the type M{sub 3}UF{sub 8} (M = NH{sub 4}, Na, Rb, Cs) leads to an interpretation based on a trigonal deformation of the eight fluorine atom structure surrounding the uranium atom. By applying a Hamiltonian spin formalism and making a systematic use of group theory, it is possible to present the susceptibility calculations very concisely. Study of the resonance and of the relaxation of the fluorine atoms in powdered uranium VI complex fluorides suggests a structural model in the case of NaUF{sub 7}. It is shown that the shape of the magnetic resonance absorption lines is strongly affected by the presence of large anisotropic chemical shifts. In the model proposed here, six fluorine atoms are linked to the uranium, atom by strongly covalent bonds in a deformed UF{sub 6} octahedral structure; the seventh fluorine atom remains ionic. The occurrence of a rotational movement of the octahedron is confirmed by a study of the longitudinal relaxation of the fluorine atoms, the activation energy being 0.46 eV. (author) [French] L'etude de la susceptibilite magnetique de complexes fluores d'uranium V et la resonance magnetique des fluors dans des complexes fluores d'uranium VI permettent de proposer un modele structural pour ces composes, ou la diffraction des rayons X, en l'absence de monocristaux convenables, est incapable de preciser la position des atomes de fluor. Nous montrons

  18. Magnetic study of solid uranium-fluorine complexes; Contribution a l'etude magnetique de composes fluores solides de l'uranium

    Energy Technology Data Exchange (ETDEWEB)

    Dianoux, A.J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-06-01

    A study of the magnetic susceptibility of uranium V fluorine complexes and of the magnetic resonance of fluorine atoms in uranium VI fluorine complexes has made it possible to put forward a structural model for these compounds for which it is impossible, because of the lack of suitable single crystals for X-ray diffraction work, to deduce the exact position of the fluorine atoms. It is shown that it is difficult to interpret the paramagnetism of uranium fluorides, because the uranium ions are in low-symmetry sites. A theoretical study of the magnetism of the U{sup V} ion in complex fluorides of the type M{sub 3}UF{sub 8} (M = NH{sub 4}, Na, Rb, Cs) leads to an interpretation based on a trigonal deformation of the eight fluorine atom structure surrounding the uranium atom. By applying a Hamiltonian spin formalism and making a systematic use of group theory, it is possible to present the susceptibility calculations very concisely. Study of the resonance and of the relaxation of the fluorine atoms in powdered uranium VI complex fluorides suggests a structural model in the case of NaUF{sub 7}. It is shown that the shape of the magnetic resonance absorption lines is strongly affected by the presence of large anisotropic chemical shifts. In the model proposed here, six fluorine atoms are linked to the uranium, atom by strongly covalent bonds in a deformed UF{sub 6} octahedral structure; the seventh fluorine atom remains ionic. The occurrence of a rotational movement of the octahedron is confirmed by a study of the longitudinal relaxation of the fluorine atoms, the activation energy being 0.46 eV. (author) [French] L'etude de la susceptibilite magnetique de complexes fluores d'uranium V et la resonance magnetique des fluors dans des complexes fluores d'uranium VI permettent de proposer un modele structural pour ces composes, ou la diffraction des rayons X, en l'absence de monocristaux convenables, est incapable de preciser la position des atomes de

  19. Commissioning of experimental enclosures (Hutches) at the Advanced Photon Source - A to Z ALARA

    International Nuclear Information System (INIS)

    Vacca, J.; Job, P. K.; Rauchas, A.; Justus, A.; Veluri, V. R.

    2000-01-01

    The Advanced Photon Source (APS), 7 GeV electron Storage Ring at the Argonne National Laboratory is designed to be a major national user facility providing high-brilliance x-ray beams. Figure 1 shows a plan view of the APS. At completion, APS will have 35 bending magnet (BM) beamlines and 35 insertion device (ID) beamlines. A typical x-ray beamline at APS comprises of a front end (FE) that confines the beam; a first optics enclosure (FOE) which houses optics to filter and monochromatize the beam; and beam transports, additional optics, and the experiment stations. Figure 2 shows a section of the storage ring with the layout of the ID and BM beamlines and typical experiment stations. The first x-ray beam was delivered to an experiment station in 1995. Ever since, to date, over 120 experimental stations (hutches) have been commissioned and are receiving intense x-ray beams of varying energies for various experiments. This paper describes in some detail the steps involved in the process of commissioning experimental stations and the implementation of the ALARA at each step

  20. Health physics experiences in achieving ALARA exposures to plant personnel at NAPS

    International Nuclear Information System (INIS)

    Ramakrishna, V.; Lal Chand

    2000-01-01

    Unit 1 of NAPS achieved first criticality on 12.3.1989 and Unit 2 achieved on 24.10.1991. Till the end of Feb-2000 these units have completed 1890 and 1811 full power days respectively. The performance of NAPS was expected to be better than the earlier Indian reactors in respect of safe production as well as cumulative radiation exposures. This is because of the major design improvements like: fully double containment system, elimination of 41 Ar by introducing light water in calandria vault, reduction of core based fuel failure rate, separation of high radiation equipment to no occupancy areas during normal operation, a separate purification building for the purification of both moderator and PHT systems, a better layout of equipment and plant areas, elimination of unnecessary equipment in various systems besides ensuring the reliability of equipment for safe operation, selection of materials with low corrosion and activation characteristics etc. In this paper, the operational health physics experiences at NAPS to achieve ALARA exposures to plant personnel are described briefly. (author)

  1. Hanford Waste Vitrification Plant applied technology plan

    International Nuclear Information System (INIS)

    Kruger, O.L.

    1990-09-01

    This Applied Technology Plan describes the process development, verification testing, equipment adaptation, and waste form qualification technical issues and plans for resolution to support the design, permitting, and operation of the Hanford Waste Vitrification Plant. The scope of this Plan includes work to be performed by the research and development contractor, Pacific Northwest Laboratory, other organizations within Westinghouse Hanford Company, universities and companies with glass technology expertise, and other US Department of Energy sites. All work described in this Plan is funded by the Hanford Waste Vitrification Plant Project and the relationship of this Plan to other waste management documents and issues is provided for background information. Work to performed under this Plan is divided into major areas that establish a reference process, develop an acceptable glass composition envelope, and demonstrate feed processing and glass production for the range of Hanford Waste Vitrification Plant feeds. Included in this work is the evaluation and verification testing of equipment and technology obtained from the Defense Waste Processing Facility, the West Valley Demonstration Project, foreign countries, and the Hanford Site. Development and verification of product and process models and other data needed for waste form qualification documentation are also included in this Plan. 21 refs., 4 figs., 33 tabs

  2. Natural phenomena analyses, Hanford Site, Washington

    International Nuclear Information System (INIS)

    Tallman, A.M.

    1989-01-01

    Probabilistic seismic hazard studies completed for the Washington Public Power Supply System's Nuclear Plant 2 and for the US Department of Energy's N Reactor sites, both on the Hanford Site, suggested that the Lawrence Livermore National Laboratory seismic exposure estimates were lower than appropriate, especially for sites near potential seismic sources. A probabilistic seismic hazard assessment was completed for those areas that contain process and/or waste management facilities. the lower bound magnitude of 5.0 is used in the hazard analysis and the characteristics of small-magnitude earthquakes relatively common to the Hanford Site are addressed. The recommended ground motion for high-hazard facilities is somewhat higher than the Lawrence Livermore National Laboratory model and the ground motion from small-magnitude earthquakes is addressed separately from the moderate- to large-magnitude earthquake ground motion. The severe wind and tornado hazards determined for the Hanford Siste are in agreement with work completed independently using 43 years of site data. The low-probability, high-hazard, design-basis flood at the Hanford Site is dominated by dam failure on the Columbia River. Further evaluation of the mechanisms and probabilities of such flooding is in progress. The Hanford Site is downwind from several active Cascade volcanoes. Geologic and historical data are used to estimate the ashfall hazard

  3. Hanford Waste Vitrification Plant Technology Plan

    International Nuclear Information System (INIS)

    Sexton, R.A.

    1988-06-01

    The reference Hanford plan for disposal of defense high-level waste is based on waste immobilization in glass by the vitrification process and temporary vitrified waste storage at the Hanford Site until final disposal in a geologic repository. A companion document to the Hanford Waste Management Plan (HWMP) is the Draft, Interim Hanford Waste Management Technology Plan (HWMTP), which provides a description of the technology that must be developed to meet the reference waste management plan. One of the issues in the HWMTP is DST-6, Immobilization (Glass). The HWMTP includes all expense funding needed to complete the Hanford Waste Vitrification Plant (HWVP) project. A preliminary HWVP Technology Plan was prepared in 1985 as a supporting document to the HWMTP to provide a more detailed description of the technology needed to construct and operate a vitrification facility. The plan was updated and issued in 1986, and revised in 1987. This document is an annual update of the plan. The HWVP Technology Plan is limited in scope to technology that requires development or confirmation testing. Other expense-funded activities are not included. The relationship between the HWVP Technology Plan and other waste management issues addressed in the HWMTP is described in section 1.6 of this plan. 6 refs., 4 figs., 34 tabs

  4. Hanford site transuranic waste sampling plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed

  5. Hanford Site Environmental Management Specification

    International Nuclear Information System (INIS)

    DAILY, J.L.

    2001-01-01

    The US Department of Energy, Richland Operations Office (RL) has established a document hierarchy as part of its integrated management system. The Strategic Plan defines the vision, values, missions, strategic goals, high-level outcomes, and the basic strategies in achieving those outcomes. As shown in Figure 1-1, the Site Specification derives requirements from the Strategic Plan and documents the top-level mission technical requirements for the work involved in the RL Hanford Site cleanup and infrastructure activities under the responsibility of the U.S. Department of Energy, Office of Environmental Management (EM). It also provides the basis for all contract technical requirements. Since this is limited to the EM work, neither the Fast Flux Test Facility (FFTF) nor the Pacific Northwest National Laboratory (PNNL) non-EM science activities are included. Figure 1-1 also shows the relationship between this Site Specification and the other Site management and planning documents. Similarly, the documents, orders, and laws referenced in this document represent only the most salient sources of requirements. Current and contractual reference data contain a complete set of source documents

  6. Hanford Tank Waste Particle Atlas

    Energy Technology Data Exchange (ETDEWEB)

    Herting, D. L. [Washington River Protection Solutions LLC (WRPS), Richland, WA (United States); Cooke, G. A. [Washington River Protection Solutions LLC (WRPS), Richland, WA (United States); Page, J S [Washington River Protection Solutions LLC (WRPS), Richland, WA (United States); Valerio, J. L. [Washington River Protection Solutions LLC (WRPS), Richland, WA (United States)

    2015-08-01

    Several methods have been utilized to perform solid phase characterization. Polarized light microscopy (PLM) is used to identify individual particles based on size, shape, color, and optical properties (e.g., refractive index1, birefringence, extinction positions, and interference figures). Scanning electron microscopy with energy-dispersive spectroscopy (SEM/EDS) is used to detect which elements are present in individual particles and to infer chemical phase identification based on the metals present in combination with the size and shape of the particles. Powder X-ray diffraction (XRD) is used to identify crystalline phases present in bulk samples by matching the X-ray patterns with a library of known patterns for pure phases. Transmission electron microscopy (TEM) is used to identify individual particles by their X-ray diffraction patterns. RAMAN analysis is used to identify bulk sample compositions by matching RAMAN spectra with a library of known patterns. Other specialized techniques have not been employed routinely for Hanford tank waste samples.

  7. The Hanford summit and sustainable development

    International Nuclear Information System (INIS)

    Sullivan, C.T.

    1994-05-01

    Since the days of the Manhattan Project of World War II, the economic well being of the Tri-Cities (Pasco, Kennewick, and Richland) of Washington State has been tied to the US Department of Energy missions at the nearby Hanford Site. As missions at the Site changed, so did the well being of the region. The Hanford Site is now poised to complete its final mission, that of environmental restoration. When restoration is compiled, the Site may be closed and the effect on the local economy will be devastating if action is not taken now. To that end, economic diversification and transition are being planned. To facilitate the process, the Hanford Site will become a sustainable development demonstration project -- a project with regional, national, and international application

  8. Environmental monitoring at Hanford for 1987

    International Nuclear Information System (INIS)

    Jacquish, R.E.; Mitchell, P.J.

    1988-05-01

    Envoronmental monitoring activities performed on the Hanford Site for 1987 are discussed in this report. Samples of environmental media were collected to determine radionuclide and chemical concentrations at locations in the geographical area. Results are discussed in detail in subsequent sections of this report. Surveillance of radioactivity in the Hanford vicinity during 1987 indicated concentrations well below applicable DOE and US Environmental Protection Agency (EPA) standards. Radioactive materials released from Hanford operations were generally indistinguishable above background in the offsite environment. Continued influence from the 1986 reactor accident at the Chernobyl Nuclear Power Station in the USSR was not apparent this year. Chemical concentrations in air were below applicable standards established by the EPA and the State of Washington. Chemicals detected in the ground water beneath the Site can be attributed to both Site operations and natural background levels. Several chemicals regulated by the EPA and the State of Washington exceeded EPA drinking water standards (DWS). 106 refs., 71 figs., 110 tabs

  9. Westinghouse Hanford Company package testing capabilities

    International Nuclear Information System (INIS)

    Hummer, J.H.; Mercado, M.S.

    1993-07-01

    The Department of Energy's Hanford Site is a 1,450-km 2 (560-mi 2 ) installation located in southeastern Washington State. Established in 1943 as a plutonium production facility, Hanford's role has evolved into one of environmental restoration and remediation. Many of these environmental restoration and remediation activities involve transportation of radioactive/hazardous materials. Packagings used for the transportation of radioactive/hazardous materials must be capable of meeting certain normal transport and hypothetical accident performance criteria. Evaluations of performance to these criteria typically involve a combination of analysis and testing. Required tests may include the free drop, puncture, penetration, compression, thermal, heat, cold, vibration, water spray, water immersion, reduced pressure, and increased pressure tests. The purpose of this paper is to outline the Hanford capabilities for performing each of these tests

  10. Hanford facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-01-01

    This document, Set 2, the Hanford Facility Dangerous Waste Part B Permit Application, consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 CFR 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of WAC 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. This permit application contains ''umbrella- type'' documentation with overall application to the Hanford Facility. This documentation is broad in nature and applies to all TSD units that have final status under the Hanford Facility Permit

  11. Environmental surveillance at Hanford for CY-1979

    International Nuclear Information System (INIS)

    Houston, J.R.; Blumer, P.J.

    1980-04-01

    Environmental data were collected for most environmental media including air, Columbia River water, external radiation, foodstuffs (milk, beef, eggs, poultry, and produce) and wildlife (deer, fish, and game birds), as well as soil and vegetation samples. In general, offsite levels of radionuclides attributable to Hanford operations during 1979 were indistinguishable from background levels. The data are summarized in the following highlights. Air quality measurements of NO 2 in the vicinity of the Hanford Site and releases of SO 2 onsite were well within the applicable federal and state standards. Particulate air concentrations exceed the standards primarily because of agricultural activities in the area. Discharges of waste water from Hanford facilities in the Columbia River under the National Pollution Discharge Elimination System (NPDES) permit were all within the parameter limits on the permit

  12. Vitrification technology for Hanford Site tank waste

    International Nuclear Information System (INIS)

    Weber, E.T.; Calmus, R.B.; Wilson, C.N.

    1995-04-01

    The US Department of Energy's (DOE) Hanford Site has an inventory of 217,000 m 3 of nuclear waste stored in 177 underground tanks. The DOE, the US Environmental Protection Agency, and the Washington State Department of Ecology have agreed that most of the Hanford Site tank waste will be immobilized by vitrification before final disposal. This will be accomplished by separating the tank waste into high- and low-level fractions. Capabilities for high-capacity vitrification are being assessed and developed for each waste fraction. This paper provides an overview of the program for selecting preferred high-level waste melter and feed processing technologies for use in Hanford Site tank waste processing

  13. Hanford Tanks Initiative quality assurance implementation plan

    International Nuclear Information System (INIS)

    Huston, J.J.

    1998-01-01

    Hanford Tanks Initiative (HTI) Quality Assurance Implementation Plan for Nuclear Facilities defines the controls for the products and activities developed by HTI. Project Hanford Management Contract (PHMC) Quality Assurance Program Description (QAPD)(HNF-PRO599) is the document that defines the quality requirements for Nuclear Facilities. The QAPD provides direction for compliance to 10 CFR 830.120 Nuclear Safety Management, Quality Assurance Requirements. Hanford Tanks Initiative (HTI) is a five-year activity resulting from the technical and financial partnership of the US Department of Energy's Office of Waste Management (EM-30), and Office of Science and Technology Development (EM-50). HTI will develop and demonstrate technologies and processes for characterization and retrieval of single shell tank waste. Activities and products associated with HTI consist of engineering, construction, procurement, closure, retrieval, characterization, and safety and licensing

  14. Annual Hanford Site Environmental Permitting Status Report

    International Nuclear Information System (INIS)

    HOMAN, N.A.

    2000-01-01

    The information contained in, and/or referenced in, this Annual Hanford Site Environmental Permitting Status Report addresses Permit Condition II.W (Other Permits and/or Approvals) of the Dangerous Waste Portion of the Resource Conservation and Recovery Act Permit for the Treatment, Storage, and Disposal of Dangerous Waste, issued by the Washington State Department of Ecology (WA7890008967). Condition II.W specifies that the Permittees are responsible for obtaining all other applicable federal, state, and local permits authorizing the development and operation of the Hanford Facility. This status report also addresses Permit Condition I.E.22, as interpreted in Section 12.1.25 of the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Rev. 4), that states this report will be prepared annually and a copy of this report will be placed in the Facility Operating Record, General Information file by October 1 of each year

  15. In situ bioremediation of Hanford groundwater

    International Nuclear Information System (INIS)

    Skeen, R.S.; Roberson, K.R.; Workman, D.J.; Petersen, J.N.; Shouche, M.

    1992-04-01

    Liquid wastes containing radioactive, hazardous, and regulated chemicals have been generated throughout the 40+ years of operations at the US Department of Energy's (DOE) Hanford Site. Some of these wastes were discharged to the soil column and many of the waste components, including nitrate, carbon tetrachloride (CCl 4 ), and several radionuclides, have been detected in the Hanford groundwater. Current DOE policy prohibits the disposal of contaminated liquids directly to the environment, and remediation of existing contaminated groundwaters may be required. In situ bioremediation is one technology currently being developed at Hanford to meet the need for cost effective technologies to clean groundwater contaminated with CCl 4 , nitrate, and other organic and inorganic contaminants. This paper focuses on the latest results of an on going effort to develop effective in situ remediation strategies through the use of predictive simulations

  16. Hanford Environmental Information System (HEIS) user's manual

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. The HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. Data stored in the HEIS are collected under several regulatory programs. Currently these include the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the Resource Conservation and Recovery Act of 1976 (RCRA); and the Ground-Water Environmental Surveillance Project, managed by the Pacific Northwest Laboratory. The HEIS is an information system with an inclusive database. The manual, the HEIS User's Manual, describes the facilities available to the scientist, engineer, or manager who uses the system for environmental monitoring, assessment, and restoration planning; and to the regulator who is responsible for reviewing Hanford Site operations against regulatory requirements and guidelines

  17. Assessment of groundwater management at Hanford

    International Nuclear Information System (INIS)

    Deju, R.A.

    1975-01-01

    A comprehensive review of the groundwater management and environmental monitoring programs at the Hanford reservation was initiated in 1973. A large number of recommendations made as a result of this review are summarized. The purpose of the Hanford Hydrology Program is to maintain a groundwater surveillance network to assess contamination of the natural water system. Potential groundwater contamination is primarily a function of waste management decisions. The review revealed that although the hydrology program would greatly benefit from additional improvements, it is adequate to predict levels of contaminants present in the groundwater system. Studies are presently underway to refine advanced mathematical models to use results of the hydrologic investigation in forecasting the response of the system to different long-term management decisions. No information was found which indicates that a hazard through the groundwater pathway presently exists as a result of waste operations at Hanford. (CH)

  18. Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel; Proposition d'organisation et procedure ALARA pour la preparation le suivi et le retour d'experience des chantiers de maintenance: application au RGV

    Energy Technology Data Exchange (ETDEWEB)

    Lochard, Jacques; Lefaure, Christian

    1990-01-01

    This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example.

  19. Proposal of organisation and ALARA procedure for preparation, follow-up and experience gained from maintenance: application to replacement of pressure vessel; Proposition d'organisation et procedure ALARA pour le suivi et le retour d'experience des chantiers de maintenance: application au RGV

    Energy Technology Data Exchange (ETDEWEB)

    Lochard, Jacques; Lefaure, Christian

    1989-12-01

    This report proposes the organisation and ALARA procedures for preparation, follow-up and analysis of the lessons learned during maintenance works at a nuclear power plant. After a brief description of the ALARA principle in the first chapter, the following chapters describe proposals for establishing and start-up of a maintenance building site. The proposals are illustrated by the replacement of the pressure vessel as an example.

  20. HANFORD SITE CENTRAL PLATEAU CLEANUP COMPLETION STRATEGY

    International Nuclear Information System (INIS)

    Bergman, T.B.

    2011-01-01

    Cleanup of the Hanford Site is a complex and challenging undertaking. The U.S. Department of Energy (DOE) has developed a comprehensive vision for completing Hanford's cleanup mission including transition to post-cleanup activities. This vision includes 3 principle components of cleanup: the ∼200 square miles ofland adjacent to the Columbia River, known as the River Corridor; the 75 square miles of land in the center of the Hanford Site, where the majority of the reprocessing and waste management activities have occurred, known as the Central Plateau; and the stored reprocessing wastes in the Central Plateau, the Tank Wastes. Cleanup of the River Corridor is well underway and is progressing towards completion of most cleanup actions by 2015. Tank waste cleanup is progressing on a longer schedule due to the complexity of the mission, with construction of the largest nuclear construction project in the United States, the Waste Treatment Plant, over 50% complete. With the progress on the River Corridor and Tank Waste, it is time to place increased emphasis on moving forward with cleanup of the Central Plateau. Cleanup of the Hanford Site has been proceeding under a framework defmed in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In early 2009, the DOE, the State of Washington Department of Ecology, and the U.S. Environmental Protection Agency signed an Agreement in Principle in which the parties recognized the need to develop a more comprehensive strategy for cleanup of the Central Plateau. DOE agreed to develop a Central Plateau Cleanup Completion Strategy as a starting point for discussions. This DOE Strategy was the basis for negotiations between the Parties, discussions with the State of Oregon, the Hanford Advisory Board, and other Stakeholder groups (including open public meetings), and consultation with the Tribal Nations. The change packages to incorporate the Central Plateau Cleanup Completion Strategy were signed by the

  1. Vascular Plants of the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Sackschewsky, Michael R.; Downs, Janelle L.

    2001-09-28

    This report provides an updated listing of the vascular plants present on and near the U.S. Department of Energy Hanford Site. This document is an update of a listing of plants prepared by Sackschewdky et al. in 1992. Since that time there has been a significant increase in the botanical knowledge of the Hanford Site. The present listing is based on an examination of herbarium collections held at PNNL, at WSU-Tri Cities, WSU-Pullman, Bringham Young University, and The University of Washington, and on examination of ecological literature derived from the Hanford and Benton county areas over the last 100 years. Based on the most recent analysis, there are approximately 725 different plant species that have been documented on or around the Hanford Site. This represents an approximate 20% increase in the number of species reported within Sackschewsky et al. (1992). This listing directly supports DOE and contractor efforts to assess the potential impacts of Hanford Site operations on the biological environment, including impacts to rare habitats and to species listed as endangered or\\ threatened. This document includes a listing of plants currently listed as endangered, threatened, or otherwise of concern to the Washington Natural Heritage Program or the U.S. Fish and Wildlife Service, as well as those that are currently listed as noxious weeds by the State of Washington. Also provided is an overview of how plants on the Hanford Site can be used by people. This information may be useful in developing risk assessment models, and as supporting information for clean-up level and remediation decisions.

  2. Environmental surveillance at Hanford for CY-1974

    International Nuclear Information System (INIS)

    Fix, J.J.

    1975-04-01

    During 1974, the work at Hanford included N Reactor operation, nuclear fuel fabrication, liquid waste solidification, continued construction of the Fast Flux Test Facility, continued construction of Washington Public Power Supply System (WPPSS) No. 2 power reactor, Arid Lands Ecology studies, as well as continued use of a variety of research and laboratory facilities. Environmental data collected during 1974 showed continued compliance of Hanford operations with all applicable state and federal regulations. Levels of radioactivity in the atmosphere from Hanford operations at all offsite sampling locations were indistinguishable from levels due to natural causes and fallout from nuclear detonations in the atmosphere. Air quality measurements of NO 2 in the Hanford environs recorded a maximum yearly average concentration of 0.006 ppM or 12 percent of the ambient air standard. There was no indication that Hanford operations contributed significantly to these levels. All SO 2 results were less than the detection limit of 0.005 ppM or 25 percent of the ambient air quality standard. Routine radiological, chemical, biological, and physical analyses of Columbia River water upstream and downstream of the Hanford Reservation operations with the possible exception of water temperature. Levels of radioactivity were similar at both locations and were due to natural and fallout radioactivity. Estimates are included of the radiation dose to the human population within an 80-kilometer (50-mile) radius of the site during 1974. Methods used in calculations of the annual dose and 50-year dose commitment from radioactive effluents are discussed. (U.S.)

  3. HANFORD SITE SUSTAINABILITY PROGRAM RICHLAND WASHINGTON - 12464

    Energy Technology Data Exchange (ETDEWEB)

    FRITZ LL

    2012-01-12

    In support of implementation of Executive Order (EO) 13514, Federal Leadership in Environmental, Energy and Economic Performance, the Hanford Site Sustainability Plan was developed to implement strategies and activities required to achieve the prescribed goals in the EO as well as demonstrate measurable progress in environmental stewardship at the Hanford Site. The Hanford Site Sustainability Program was developed to demonstrate progress towards sustainability goals as defined and established in Executive Order (EO) 13514, Federal Leadership in Environmental, Energy and Economic Performance; EO 13423, Strengthening Federal Environmental, Energy and Transportation Management, and several applicable Energy Acts. Multiple initiatives were undertaken in Fiscal Year (FY) 2011 to implement the Program and poise the Hanford Site as a leader in environmental stewardship. In order to implement the Hanford Site Sustainability Program, a Sustainability Plan was developed in conjunction with prime contractors, two U.S. Department of Energy (DOE) Offices, and key stakeholders to serve as the framework for measuring progress towards sustainability goals. Based on the review of these metrics and future plans, several activities were initiated to proactively improve performance or provide alternatives for future consideration contingent on available funding. A review of the key metric associated with energy consumption for the Hanford Site in FY 2010 and 2011 indicated an increase over the target reduction of 3 percent annually from a baseline established in FY 2003 as illustrated in Figure 1. This slight increase was attributed primarily from the increased energy demand from the cleanup projects funded by the American Recovery and Reinvestment Act (ARRA) in FY 2010 and 2011. Although it is forecasted that the energy demand will decrease commensurate with the completion of ARRA projects, several major initiatives were launched to improve energy efficiency.

  4. Radioactive waste management at the Hanford Reservation

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    During some 30 years of plutonium production, the Hanford Reservation has accumulated large quantities of low- and high-level radioactive wastes. The high-level wastes have been stored in underground tanks, and the low-level wastes have been percolated into the soil. In recent years some programs for solidification and separation of the high-level wastes have been initiated. The Hanford waste-management system was studied by a panel of the Committee on Radioactive Waste Management of the National Academy of Sciences. The panel concluded that Hanford waste-management practices were adequate at present and for the immediate future but recommended increased research and development programs related to long-term isolation of the wastes. The panel also considered some alternatives for on-site disposal of the wastes. The Hanford Reservation was originally established for the production of plutonium for military purposes. During more than 30 years of operation, large volumes of high- and low-level radioactive wastes have been accumulated and contained at the site. The Management of these wastes has been the subject of controversy and criticism. To obtain a true technical evaluation of the Hanford waste situation, the Energy Research and Development Administration (now part of the Department of Energy) issued a contract to the National Academy of Sciences and the National Research Councilto conduct an independent review and evaluation of the Hanford waste-management practices and plans. A panel of the Committee on Radioactive Waste Management (CRWM) of the National Academy of Sciences conducted this study between the summer of 1976 and the summer of 1977. This article is a summary of the final report of that panel

  5. Measurement of 2-5 keV x-ray emission from laser-target interactions by using fluor-MCP and CsI-XRD detectors

    International Nuclear Information System (INIS)

    Lee, P.H.Y.; Tirsell, K.G.; Leipelt, G.R.; Laird, W.B.

    1981-01-01

    For inertial confinement fusion plasma diagnostics, x-ray diode (XRD) detectors using conventional cathodes are not sensitive enough to measure x-rays above approx. 1.5 keV. However, for laser driver fusion targets, x-rays in the range of 2 to 5 keV are important because of their mobility in the target. We have successfully used fluor-microchannel plate (MCP) detectors to obtain absolute x-ray measurements in the 2 to 5 keV range. Recent data obtained from experiments on the Shiva laser system are presented. In addition, designs for a variety of channels in the range using fluor-MCP and CsI-XRD's above 1.5 keV will be discussed

  6. The effect of monofluorophosphate implant in white rat mothers towards the level of fluor in the incisors of their young babies (Rattus-rattus

    Directory of Open Access Journals (Sweden)

    Widjijono Widjijono

    2010-06-01

    Full Text Available Background: Fluoride has been widely used in the prevention of dental caries for a long time. To prevent dental caries, fluoride must be induced in low amount at high frequency. Inducing it through implantation process even make slow release of small concentration of fluoride. Purpose: The aim of this research was to analyze whether the induction of monofluorophosphate (MFP implant into the white rat mothers affects the level of fluoride in the incisors of their young babies. Method: The objects of the research were twenty white rat mothers in two days of pregnancy which then were divided into four groups (n=5. First, those mothers have been induced with implant under their back skin until their born young babies in the age of 35 days (n=5. The level of fluoride in the incisors of those young babies then is measured with Potentiometer. The obtained data were finally analyzed with One-Way ANOVA test and continued by with LSD test (p=0.05. Result: The result of this research showed that the means of the fluoride level in the incisors of those babies divided into those four groups in series were about 11956.16±201.35 ppb (K, 27328.04±234.56 ppb (P1, 37267.21±248.86 ppb (P2, and 18103.50±267.11 ppb (P3. The result of ANOVA test then showed that the induction of various MFP implant levels significantly affected the level of fluoride in the incisors of the babies. The mean differences among the treatment groups after being tested with LSD 0.05 were also significant. Conclusion: The finding confirm that the significant increasing of the optimal fluoride retention in the incisors of white rat babies can be achieved with the induction of fluoride with MFP ions implant in about 52.98 mg.Latar belakang: Pencegahan karies gigi menggunakan senyawa fluor telah banyak dilakukan dan berlangsung dalam jangka waktu lama. Pemberian fluor dalam jumlah rendah dan frekuensi tinggi merupakan pemenuhan kebutuhan pencegahan karies gigi. Pemberian dengan cara

  7. Hanford Site ground-water surveillance for 1989

    International Nuclear Information System (INIS)

    Evans, J.C.; Bryce, R.W.; Bates, D.J.; Kemner, M.L.

    1990-06-01

    This annual report of ground-water surveillance activities provides discussions and listings of results for ground-water monitoring at the Hanford Site during 1989. The Pacific Northwest Laboratory (PNL) assesses the impacts of Hanford operations on the environment for the US Department of Energy (DOE). The impact Hanford operations has on ground water is evaluated through the Hanford Site Ground-Water Surveillance program. Five hundred and sixty-seven wells were sampled during 1989 for Hanford ground-water monitoring activities. This report contains a listing of analytical results for calendar year (CY) 1989 for species of importance as potential contaminants. 30 refs., 29 figs,. 4 tabs

  8. Software configuration management plan for the Hanford site technical database

    International Nuclear Information System (INIS)

    GRAVES, N.J.

    1999-01-01

    The Hanford Site Technical Database (HSTD) is used as the repository/source for the technical requirements baseline and programmatic data input via the Hanford Site and major Hanford Project Systems Engineering (SE) activities. The Hanford Site SE effort has created an integrated technical baseline for the Hanford Site that supports SE processes at the Site and project levels which is captured in the HSTD. The HSTD has been implemented in Ascent Logic Corporation (ALC) Commercial Off-The-Shelf (COTS) package referred to as the Requirements Driven Design (RDD) software. This Software Configuration Management Plan (SCMP) provides a process and means to control and manage software upgrades to the HSTD system

  9. Hanford Site radioactive hazardous materials packaging directory

    International Nuclear Information System (INIS)

    McCarthy, T.L.

    1995-12-01

    The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations ampersand Development (PO ampersand D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage

  10. Hanford year 2000 Business Continuity Plan

    Energy Technology Data Exchange (ETDEWEB)

    ROGGENKAMP, S.L.

    1999-11-01

    The goal of Department of Energy Richland Operations (DOE-RL) Year 2000 (Y2K) effort is to ensure that the Hanford site successfully continues its mission as we approach and enter the 21th century. The Y2K Business Continuity Planning process provides a structured approach to identify Y2K risks to the site and to mitigate these risks through Y2K Contingency Planning, ''Zero-Day'' Transition Planning and Emergency Preparedness. This document defines the responsibilities, processes and plans for Hanford's Y2K Business Continuity. It identifies proposed business continuity drills, tentative schedule and milestones.

  11. Technical basis for internal dosimetry at Hanford

    International Nuclear Information System (INIS)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1991-07-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs

  12. Technical basis for internal dosimetry at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1991-07-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

  13. Technical basis for internal dosimetry at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1989-04-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

  14. Executive summary, Hanford Site Pollution Prevention Plan

    International Nuclear Information System (INIS)

    1992-08-01

    A pollution prevention plan is an organized, comprehensive, and continual effort to systematically reduce waste generation. The Hanford Site Pollution Prevention Plan is designed to eliminate or minimize pollutant releases to all environmental media from all aspects of Site operations. These efforts offer increased protection of public health and the environment. This plan reflects the goals and policies for pollution prevention at the Hanford Site and represents an ongoing effort to make pollution prevention part of the Site operating philosophy. The plan encompasses hazardous waste only and excludes radioactive waste and radioactive mixed waste

  15. Hanford year 2000 Business Continuity Plan

    International Nuclear Information System (INIS)

    VORNEY, S.V.

    1999-01-01

    The goal of Department of Energy Richland Operations (DOE-RL) Year 2000 (Y2K) effort is to ensure that the Hanford site successfully continues its mission as we approach and enter the 21th century. The Y2K Business Continuity Planning process provides a structured approach to identify Y2K risks to the site and to mitigate these risks through Y2K Contingency Planning, ''Zero-Day'' Transition Planning and Emergency Preparedness. This document defines the responsibilities, processes and plans for Hanford's Y2K Business Continuity. It identifies proposed business continuity drills, tentative schedule and milestones

  16. Hanford Site radioactive hazardous materials packaging directory

    Energy Technology Data Exchange (ETDEWEB)

    McCarthy, T.L.

    1995-12-01

    The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations & Development (PO&D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage.

  17. Hanford Waste Vitrification Plant technology progress

    International Nuclear Information System (INIS)

    Wolfe, B.A.; Scott, J.L.; Allen, C.R.

    1989-10-01

    The Hanford Waste Vitrification Plant (HWVP) is currently being designed to safely process and temporarily store immobilized defense liquid high-level wastes from the Hanford Site. These wastes will be immobilized in a borosilicate glass waste form in the HWVP and stored onsite until a qualified geologic waste repository is ready for permanent disposal. Because of the diversity of wastes to be disposed of, specific technical issues are being addressed so that the plant can be designed and operated to produce a waste form that meets the requirements for permanent disposal in a geologic repository. This paper reports the progress to date in addressing these issues. 2 figs., 3 tabs

  18. Hanford Environmental Dose Reconstruction Project monthly report

    International Nuclear Information System (INIS)

    Finch, S.M.

    1990-12-01

    The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doses that populations could have been have received from nuclear operations at Hanford since 1944. The project is being managed and conducted by the Pacific Northwest Laboratory (PNL) under the direction of an independent Technical Steering Panel (TSP). The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed, from release to impact on humans (dose estimates): source terms; environmental transport; environmental monitoring data; demographics, agriculture, food habits; and environmental pathways and dose estimates. 3 figs., 3 tabs

  19. Technical basis for internal dosimetry at Hanford

    International Nuclear Information System (INIS)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1989-04-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs

  20. Westinghouse Hanford Company environmental surveillance annual report

    International Nuclear Information System (INIS)

    Schmidt, J.W.; Johnson, A.R.; McKinney, S.M.; Perkins, C.J.; Webb, C.R.

    1992-07-01

    This document presents the results of near-facility operational environmental monitoring in 1991 of the 100, 200/600, and 300/400 Areas of the Hanford Site, in south-central Washington State, as performed by Westinghouse Hanford Company. These activities are conducted to assess and to control the impacts of operations on the workers and the local environment and to monitor diffuse sources. Surveillance activities include sampling and analyses of ambient air, surface water, groundwater, sediments, soil, and biota. Also, external radiation measurements and radiological surveys are taken at waste disposal sites, radiologically controlled areas, and roads