Science.gov

Sample records for activities pipeline decommissioning

  1. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false How do I decommission a pipeline in place? 250... Decommissioning Activities Pipeline Decommissioning § 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline...

  2. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false How do I decommission a pipeline in place? 250... Decommissioning Activities Pipeline Decommissioning § 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline...

  3. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false How do I decommission a pipeline in place? 250... Decommissioning Activities Pipeline Decommissioning § 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline...

  4. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false How do I decommission a pipeline in place? 250... Decommissioning Activities Pipeline Decommissioning § 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline...

  5. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  6. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  7. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  8. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false After I decommission a pipeline, what... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit...

  9. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false After I decommission a pipeline, what... OUTER CONTINENTAL SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline,...

  10. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  11. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  12. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false After I decommission a pipeline, what... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit...

  13. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  14. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false When must I remove a pipeline decommissioned in... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor...

  15. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false After I decommission a pipeline, what... Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit a written report...

  16. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false When may I decommission a pipeline in place... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that...

  17. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false After I decommission a pipeline, what... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit...

  18. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When must I remove a pipeline decommissioned in... Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that the...

  19. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    SciTech Connect

    Agnew, Kieran

    2013-07-01

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method

  20. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false How do I decommission a pipeline in place? 250... Pipeline Decommissioning § 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline decommissioning application in triplicate to...

  1. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When may I decommission a pipeline in place... Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline does not constitute a...

  2. 30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources BUREAU OF SAFETY AND ENVIRONMENTAL... SHELF Pipelines and Pipeline Rights-of-Way § 250.1006 How must I decommission and take out of service a DOI pipeline? (a) The requirements for decommissioning pipelines are listed in § 250.1750...

  3. 30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources BUREAU OF SAFETY AND ENVIRONMENTAL... SHELF Pipelines and Pipeline Rights-of-Way § 250.1006 How must I decommission and take out of service a DOI pipeline? (a) The requirements for decommissioning pipelines are listed in § 250.1750...

  4. 30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources BUREAU OF SAFETY AND ENVIRONMENTAL... SHELF Pipelines and Pipeline Rights-of-Way § 250.1006 How must I decommission and take out of service a DOI pipeline? (a) The requirements for decommissioning pipelines are listed in § 250.1750...

  5. 30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... OUTER CONTINENTAL SHELF Pipelines and Pipeline Rights-of-Way § 250.1006 How must I decommission and take out of service a DOI pipeline? (a) The requirements for decommissioning pipelines are listed in §...

  6. 30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE OIL AND GAS AND SULPHUR OPERATIONS IN THE OUTER CONTINENTAL SHELF Pipelines and Pipeline Rights-of-Way § 250.1006 How must I decommission and take out of service a DOI...

  7. 30 CFR 250.1752 - How do I remove a pipeline?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false How do I remove a pipeline? 250.1752 Section... Decommissioning Activities Pipeline Decommissioning § 250.1752 How do I remove a pipeline? Before removing a pipeline, you must: (a) Submit a pipeline removal application in triplicate to the Regional Supervisor...

  8. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    SciTech Connect

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-15

    The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.

  9. 30 CFR 250.1752 - How do I remove a pipeline?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false How do I remove a pipeline? 250.1752 Section... GAS AND SULPHUR OPERATIONS IN THE OUTER CONTINENTAL SHELF Decommissioning Activities Pipeline Decommissioning § 250.1752 How do I remove a pipeline? Before removing a pipeline, you must: (a) Submit a...

  10. 77 FR 75198 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-19

    ... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... Format and Content for Post-shutdown Decommissioning Activities Report.'' This guide describes a method...) 1.185, ``Standard Format and Content for Post-shutdown Decommissioning Activities Report,''...

  11. Decontamination and Decommissioning activities photobriefing book FY 1997

    SciTech Connect

    1998-04-01

    The Decontamination and Decommissioning (D and D) Program at Argonne National Laboratory-East (ANL-E) is dedicated to the safe and cost effective D{ampersand}D of surplus nuclear facilities. There is currently a backlog of more than 7,000 contaminated US Department of Energy facilities nationwide. Added to this are 110 licensed commercial nuclear power reactors operated by utilities learning to cope with deregulation and an aging infrastructure that supports the commercial nuclear power industry, as well as medical and other uses of radioactive materials. With this volume it becomes easy to understand the importance of addressing the unique issues and objectives associated with the D{ampersand}D of surplus nuclear facilities. This photobriefing book summarizes the decontamination and decommissioning projects and activities either completed or continuing at the ANL-E site during the year.

  12. 77 FR 15453 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-15

    ..., PHMSA published a notice with request for comments in the Federal Register (76 FR 81013). The notice... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  13. 78 FR 55775 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-11

    ... 23, 2013, (78 FR 23972). PHMSA received one comment in response to that notice. PHMSA is publishing... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  14. 75 FR 4610 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-28

    ... Hazardous Materials Safety Administration (PHMSA) published a notice in the Federal Register (74 FR 61403... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration. ACTION: Notice and request for...

  15. 76 FR 65778 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-24

    ..., PHMSA published a notice with request for comments in the Federal Register (76 FR 45904). The notice... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  16. 77 FR 58622 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-21

    ... comments on this information collection was published on July 5, 2012 (77 FR 39797). No comments were... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  17. 78 FR 57455 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-18

    ... June 14, 2013, (78 FR 36016). PHMSA received one comment in response to that notice. PHMSA is... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  18. 78 FR 16764 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-18

    ... information collection was published on December 13, 2012, (77 FR 74276) under docket number PHMSA-2012- 0302... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  19. 77 FR 74275 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-13

    ... following information collections was published on August 27, 2012, (77 FR 51848) under docket number PHMSA... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  20. 75 FR 13568 - MMS Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-22

    ... Minerals Management Service MMS Information Collection Activity: 1010-0142, Decommissioning Activities...: Notice of extension of an information collection (1010-0142). SUMMARY: To comply with the Paperwork... Elden Street, MS-4024; Herndon, Virginia 20170-4817. Please reference ICR 1010-0142 in your comment...

  1. 78 FR 29772 - Information Collection Activities: Decommissioning Activities, Proposed Collection; Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-21

    ... information; (c) enhance the quality, usefulness, and clarity of the information to be collected; and (d...; 134E1700D2 EEEE500000 ET1SF0000.DAQ000] Information Collection Activities: Decommissioning Activities... collection of information that we will submit to the Office of Management and Budget (OMB) for review...

  2. 78 FR 49553 - Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report AGENCY: Nuclear...) for Three Mile Island, Unit 2 (TMI-2). The PSDAR provides an overview of GPUN's...

  3. 76 FR 81013 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-27

    ... Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit http://www.regulations... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  4. 77 FR 51848 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-27

    ... April 11, 2000 (65 FR 19477) or visit http://www.regulations.gov before submitting any such comments... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  5. 77 FR 74276 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-13

    ... Register published on April 11, 2000 (65 FR 19477) or visit http://www.regulations.gov before submitting... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  6. 76 FR 50539 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-15

    ... notice with request for comments in the Federal Register on June 9, 2011 (76 FR 33808) on an information... TRANSPORTATION Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice...

  7. 78 FR 23972 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-23

    ... Privacy Act Statement in the Federal Register published on April 11, 2000, (65 FR 19477) or visit http... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  8. 75 FR 53733 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-01

    ... Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit http... TRANSPORTATION Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice...

  9. 78 FR 36016 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-14

    ... complete Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  10. 76 FR 33808 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-09

    ... Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit http... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  11. 75 FR 73160 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-29

    ... Register published on April 11, 2000 (65 FR 19477) or visit http://www.regulations.gov before submitting... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

  12. 75 FR 40863 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-14

    ... April 11, 2000 (65 FR 19477) or visit http://www.regulations.gov before submitting any such comments... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  13. 75 FR 76077 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-07

    ... complete Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  14. 76 FR 45904 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-01

    ... complete Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  15. 77 FR 27279 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-09

    ... Privacy Act Statement in the Federal Register published on April 11, 2000, (65 FR 19477) or visit http... TRANSPORTATION Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice...

  16. 77 FR 39797 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-05

    ... April 11, 2000, (65 FR 19477) or visit http://www.regulations.gov before submitting any such comments... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice and...

  17. 75 FR 54363 - BOEMRE Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-07

    ... 22, 2010, we published a Federal Register notice (75 FR 13568) announcing that we would submit this...: 1010-0142, Decommissioning Activities, Extension of a Collection, Submitted for Office of Management... Enforcement (BOEMRE), Interior. ACTION: Notice of extension of an information collection (1010-0142)....

  18. Comparative Evaluation of Cutting Methods of Activated Concrete from Nuclear Power Plant Decommissioning - 13548

    SciTech Connect

    Kim, HakSoo; Chung, SungHwan; Maeng, SungJun

    2013-07-01

    The amount of radioactive wastes from decommissioning of a nuclear power plant varies greatly depending on factors such as type and size of the plant, operation history, decommissioning options, and waste treatment and volume reduction methods. There are many methods to decrease the amount of decommissioning radioactive wastes including minimization of waste generation, waste reclassification through decontamination and cutting methods to remove the contaminated areas. According to OECD/NEA, it is known that the radioactive waste treatment and disposal cost accounts for about 40 percentage of the total decommissioning cost. In Korea, it is needed to reduce amount of decommissioning radioactive waste due to high disposal cost, about $7,000 (as of 2010) per a 200 liter drum for the low- and intermediate-level radioactive waste (LILW). In this paper, cutting methods to minimize the radioactive waste of activated concrete were investigated and associated decommissioning cost impact was assessed. The cutting methods considered are cylindrical and volume reductive cuttings. The study showed that the volume reductive cutting is more cost-effective than the cylindrical cutting. Therefore, the volume reductive cutting method can be effectively applied to the activated bio-shield concrete. (authors)

  19. Summary report of Hanford Site well remediation and decommissioning activities for fiscal year 1994

    SciTech Connect

    Reynolds, K.D.

    1994-12-30

    Remediation and decommissioning of Hanford Site wells has become an integral part of Hanford Site Environmental Restoration (ER) and Resource Conservation and Recovery Act of 1976 (RCRA) groundwater monitoring programs. A well remediation and decommissioning program was funded and implemented in fiscal year (FY) 1993 under the RCRA and Operational Monitoring (ROM) Program. Funding for this work increased in FY 1994. In FY 1994 well decommissioning activities conducted for the ROM program were centered around the 200 West Area; activities for the ER program were centered in the Fitzner/Eberhart Arid Land Ecology (ALE) (Reserve) unit and the Wahluke Slope (North Slope) area. A total of 116 wells and test borings were decommissioned between the two programs during FY 1994. Additionally, five wells were identified as in need of remediation and were successfully brought into compliance with regulatory requirements. As Hanford Site restoration and remediation efforts increase in scope, the well decommissioning program will remain dynamic. The program will aggressively seek to fulfill the needs of the various environmental cleanup and groundwater/vadose monitoring programs. Wells that do not meet regulatory requirements for preservation will continually be identified and remediated or decommissioned accordingly.

  20. Implementation of the six grumbly priorities during decommissioning activities at the Idaho National Engineering Laboratory

    SciTech Connect

    Perry, E.F.; Mikkola, A.W.

    1994-12-31

    Decommissioning work continues to play an important role in the long-term activities of the Idaho National Engineering Laboratory (INEL). Recent completion of the SPERT IV waste tank project marked the 25th facility to be decommissioned at the INEL. These facilities have either been totally removed and the area restored to a natural condition, or the buildings decontaminated and returned to further use, The long-term goal for the INEL decontamination and decommissioning (D&D) program is to complete decommissioning of its surplus facilities in a safe, cost-effective, and environmentally sound manner. The INEL D&D program was established in late 1977 and has remained active since that time. The types of facilities decommissioned to date range from concrete storage pads to complex reactor and fuel-reprocessing facilities. Disassembly techniques have ranged from plasma torches, to headache balls, to linear-shaped high explosives. Late last year, Thomas P. Grumbly, Assistant Secretary for Environmental Management, U.S. Department of Energy (DOE), issued six priorities to guide the implementation of environmental management activities at DOE sites.

  1. Decommissioning handbook

    SciTech Connect

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

  2. Action Memorandum for General Decommissioning Activities under the Idaho Cleanup Project

    SciTech Connect

    S. L. Reno

    2006-10-26

    This Action Memorandum documents the selected alternative to perform general decommissioning activities at the Idaho National Laboratory (INL) under the Idaho Cleanup Project (ICP). Preparation of this Action Memorandum has been performed in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the "Superfund Amendments and Reauthorization Act of 1986", and in accordance with the "National Oil and Hazardous Substances Pollution Contingency Plan". An engineering evaluation/cost analysis (EE/CA) was prepared and released for public comment and evaluated alternatives to accomplish the decommissioning of excess buildings and structures whose missions havve been completed.

  3. 78 FR 38739 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-27

    ..., DG-1272, in the Federal Register on December 19, 2012 (77 FR 75198), for a 60-day public comment... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... (NRC) is issuing Revision 1 of Regulatory Guide (RG) 1.185, ``Standard Format and Content for...

  4. Crossing Active Faults on the Sakhalin II Onshore Pipeline Route: Pipeline Design and Risk Analysis

    SciTech Connect

    Mattiozzi, Pierpaolo; Strom, Alexander

    2008-07-08

    Twin oil (20 and 24 inch) and gas (20 and 48 inch) pipeline systems stretching 800 km are being constructed to connect offshore hydrocarbon deposits from the Sakhalin II concession in the North to an LNG plant and oil export terminal in the South of Sakhalin island. The onshore pipeline route follows a regional fault zone and crosses individual active faults at 19 locations. Sakhalin Energy, Design and Construction companies took significant care to ensure the integrity of the pipelines, should large seismic induced ground movements occur during the Operational life of the facilities. Complex investigations including the identification of the active faults, their precise location, their particular displacement values and assessment of the fault kinematics were carried out to provide input data for unique design solutions. Lateral and reverse offset displacements of 5.5 and 4.5 m respectively were determined as the single-event values for the design level earthquake (DLE) - the 1000-year return period event. Within the constraints of a pipeline route largely fixed, the underground pipeline fault crossing design was developed to define the optimum routing which would minimize stresses and strain using linepipe materials which had been ordered prior to the completion of detailed design, and to specify requirements for pipe trenching shape, materials, drainage system, etc. Detailed Design was performed with due regard to actual topography and to avoid the possibility of the trenches freezing in winter, the implementation of specific drainage solutions and thermal protection measures.

  5. Crossing Active Faults on the Sakhalin II Onshore Pipeline Route: Pipeline Design and Risk Analysis

    NASA Astrophysics Data System (ADS)

    Mattiozzi, Pierpaolo; Strom, Alexander

    2008-07-01

    Twin oil (20 & 24 inch) and gas (20 & 48 inch) pipeline systems stretching 800 km are being constructed to connect offshore hydrocarbon deposits from the Sakhalin II concession in the North to an LNG plant and oil export terminal in the South of Sakhalin island. The onshore pipeline route follows a regional fault zone and crosses individual active faults at 19 locations. Sakhalin Energy, Design and Construction companies took significant care to ensure the integrity of the pipelines, should large seismic induced ground movements occur during the Operational life of the facilities. Complex investigations including the identification of the active faults, their precise location, their particular displacement values and assessment of the fault kinematics were carried out to provide input data for unique design solutions. Lateral and reverse offset displacements of 5.5 and 4.5 m respectively were determined as the single-event values for the design level earthquake (DLE)—the 1000-year return period event. Within the constraints of a pipeline route largely fixed, the underground pipeline fault crossing design was developed to define the optimum routing which would minimize stresses and strain using linepipe materials which had been ordered prior to the completion of detailed design, and to specify requirements for pipe trenching shape, materials, drainage system, etc. Detailed Design was performed with due regard to actual topography and to avoid the possibility of the trenches freezing in winter, the implementation of specific drainage solutions and thermal protection measures.

  6. Cost leveling continues; planned activity drops sharply in US gas pipeline cnstruction

    SciTech Connect

    Morgan, J.M.

    1986-02-01

    Natural gas pipeline construction costs, as measured by the OGJ-Morgan Pipeline cost index for US gas-pipeline construction, barely crept up in the second quarter 1985. Construction activity for lines and compressor stations was down.

  7. Reactor Design and Decommissioning - An Overview of International Activities in Post Fukushima Era1 - 12396

    SciTech Connect

    Devgun, Jas S.; Laraia, Michele; Dinner, Paul

    2012-07-01

    Accidents at the Fukushima Dai-ichi reactors as a result of the devastating earthquake and tsunami of March 11, 2011 have not only dampened the nuclear renaissance but have also initiated a re-examination of the design and safety features for the existing and planned nuclear reactors. Even though failures of some of the key site features at Fukushima can be attributed to events that in the past would have been considered as beyond the design basis, the industry as well as the regulatory authorities are analyzing what features, especially passive features, should be designed into the new reactor designs to minimize the potential for catastrophic failures. It is also recognized that since the design of the Fukushima BWR reactors which were commissioned in 1971, many advanced safety features are now a part of the newer reactor designs. As the recovery efforts at the Fukushima site are still underway, decisions with respect to the dismantlement and decommissioning of the damaged reactors and structures have not yet been finalized. As it was with Three Mile Island, it could take several decades for dismantlement, decommissioning and clean up, and the project poses especially tough challenges. Near-term assessments have been issued by several organizations, including the IAEA, the USNRC and others. Results of such investigations will lead to additional improvements in system and site design measures including strengthening of the anti-tsunami defenses, more defense-in-depth features in reactor design, and better response planning and preparation involving reactor sites. The question also arises what would the effect be on the decommissioning scene worldwide, and what would the effect be on the new reactors when they are eventually retired and dismantled. This paper provides an overview of the US and international activities related to recovery and decommissioning including the decommissioning features in the reactor design process and examines these from a new

  8. Radionuclide characterization of reactor decommissioning waste and neutron-activated metals

    SciTech Connect

    Robertson, D.E.; Thomas, C.W.; Wynhoff, N.L.; Haggard, D.L.

    1993-06-01

    This study is providing the NRC and licensees with a more comprehensive data base for regulatory assessment of the radiological factors associated with reactor decommissioning and disposal of wastes generated during these activities. The objectives of this study are being accomplished during the actual decommissioning of Shippingport Station and the detailed analysis of neutron-activated materials from commercial reactors. The radiological characterization studies of Shippingport decommissioning materials have now been completed, and analyses of dismantled piping and scabbled concrete have shown that neutron activation products, dominated by {sup 60}Co, comprised the residual radionuclide inventory. Waste classification assessment have shown that all decommissioning materials (except reactor pressure vessel internals) could be disposed of as Class A waste. Spent fuel disassembly hardware from the Shippingport Core-3 was analyzed for long-lived activation products. {sup 94}Nb and {sup 63}Ni concentrations in Inconel-X750 and stainless steel components exceeded their Class C limits. Measurements and assessments of {sup 14}C in spent fuel disassembly hardware from three commercial nuclear power stations showed that this radionuclide never exceeded the Class C limit for all components. However, the {sup 63}Ni and {sup 94}Nb concentrations in some of these materials did exceed the Class C limits. These measurements are providing the basis for an assessment of the disposal options for these types of highly radioactive materials. Work is continuing on radiological characterization of spent PWR and BWR control rod assemblies. Three control rods, including a BWR cruciform control rod blade, a PWR control rod cluster assembly, and a PWR burnable poison rod assembly, have been characterized for their long-lived activation product concentrations and distribution by direct assay methods. These spent control rods could all be classified as Class C low-level waste.

  9. Radionuclide characterization of reactor decommissioning waste and neutron-activated metals

    SciTech Connect

    Robertson, D.E.; Thomas, C.W.; Wynhoff, N.L.; Haggard, D.L.

    1993-06-01

    This study is providing the NRC and licensees with a more comprehensive data base for regulatory assessment of the radiological factors associated with reactor decommissioning and disposal of wastes generated during these activities. The objectives of this study are being accomplished during the actual decommissioning of Shippingport Station and the detailed analysis of neutron-activated materials from commercial reactors. The radiological characterization studies of Shippingport decommissioning materials have now been completed, and analyses of dismantled piping and scabbled concrete have shown that neutron activation products, dominated by Co-60, comprised the residual radionuclide inventory. Waste classification assessment have shown that all decommissioning materials (except reactor pressure vessel internals) could be disposed of as Class A waste. Spent fuel disassembly hardware from the Shippingport Core-3 was analyzed for long-lived activation products. Nb-94 and Ni-63 concentrations in Inconel-X750 and stainless steel components exceeded their Class C limits. Measurements and assessments of C-14 in spent fuel disassembly hardware from three commercial nuclear power stations showed that this radionuclide never exceeded the Class C limit for al components. However, the Ni-63 and Nb-94 concentrations in some of these materials did exceed the Class C limits. These measurements are providing the basis for an assessment of the disposal options for these types of highly radioactive materials. Work is continuing on radiological characterization of spent PWR and BWR control rod assemblies. Three control rods, including a BWR cruciform control rod blade, a PWR control rod cluster assembly, and a PWR burnable poison rod assembly, have been characterized for their long-lived activation product concentrations and distribution by direct assay methods. These spent control rods could all be classified as Class C low-level waste. These rods are presently being sampled.

  10. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2007-09-16

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.

  11. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  12. Progress report on decommissioning activities at the Fernald Environmental Management Project (FEMP) site

    SciTech Connect

    1998-07-01

    The Fernald Environmental Management Project (FEMP), is located about 18 miles northwest of Cincinnati, Ohio. Between 1953 and 1989, the facility, then called the Feed Material Production Center or FMPC, produced uranium metal products used in the eventual production of weapons grade material for use by other US Department of Energy (DOE) sites. In 1989, FMPC`s production was suspended by the federal government in order to focus resources on environmental restoration versus defense production. In 1992, Fluor Daniel Fernald assumed responsibility for managing all cleanup activities at the FEMP under contract to the DOE. In 1990, as part of the remediation effort, the site was divided into five operable units based on physical proximity of contaminated areas, similar amounts of types of contamination, or the potential for a similar technology to be used in cleanup activities. This report continues the outline of the decontamination and decommissioning (D and D) activities at the FEMP site Operable Unit 3 (OU3) and provides an update on the status of the decommissioning activities. OU3, the Facilities Closure and Demolition Project, involves the remediation of more than 200 uranium processing facilities. The mission of the project is to remove nuclear materials stored in these buildings, then perform the clean out of the buildings and equipment, and decontaminate and dismantle the facilities.

  13. Decommissioning of Active Ventilation Systems in a Nuclear R and D Facility to Prepare for Building Demolition (Whiteshell Laboratories Decommissioning Project, Canada) - 13073

    SciTech Connect

    Wilcox, Brian; May, Doug; Howlett, Don; Bilinsky, Dennis

    2013-07-01

    Whiteshell Laboratories (WL) is a nuclear research establishment owned by the Canadian government and operated by Atomic Energy of Canada Limited (AECL) since the early 1960's. WL is currently under a decommissioning license and the mandate is to remediate the nuclear legacy liabilities in a safe and cost effective manner. The WL Project is the first major nuclear decommissioning project in Canada. A major initiative underway is to decommission and demolish the main R and D Laboratory complex. The Building 300 R and D complex was constructed to accommodate laboratories and offices which were mainly used for research and development associated with organic-cooled reactors, nuclear fuel waste management, reactor safety, advanced fuel cycles and other applications of nuclear energy. Building 300 is a three storey structure of approximately 16,000 m{sup 2}. In order to proceed with building demolition, the contaminated systems inside the building have to be characterized, removed, and the waste managed. There is a significant focus on volume reduction of radioactive waste for the WL project. The active ventilation system is one of the significant contaminated systems in Building 300 that requires decommissioning and removal. The active ventilation system was designed to manage hazardous fumes and radioactivity from ventilation devices (e.g., fume hoods, snorkels and glove boxes) and to prevent the escape of airborne hazardous material outside of the laboratory boundary in the event of an upset condition. The system includes over 200 ventilation devices and 32 active exhaust fan units and high efficiency particulate air (HEPA) filters. The strategy to remove the ventilation system was to work from the laboratory end back to the fan/filter system. Each ventilation duct was radiologically characterized. Fogging was used to minimize loose contamination. Sections of the duct were removed by various cutting methods and bagged for temporary storage prior to disposition

  14. Pipeline active filter utilizing a booth type multiplier

    NASA Technical Reports Server (NTRS)

    Nathan, Robert (Inventor)

    1987-01-01

    Multiplier units of the modified Booth decoder and carry-save adder/full adder combination are used to implement a pipeline active filter wherein pixel data is processed sequentially, and each pixel need only be accessed once and multiplied by a predetermined number of weights simultaneously, one multiplier unit for each weight. Each multiplier unit uses only one row of carry-save adders, and the results are shifted to less significant multiplier positions and one row of full adders to add the carry to the sum in order to provide the correct binary number for the product Wp. The full adder is also used to add this product Wp to the sum of products .SIGMA.Wp from preceding multiply units. If m.times.m multiplier units are pipelined, the system would be capable of processing a kernel array of m.times.m weighting factors.

  15. 75 FR 77694 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-13

    ... Register on November 26, 2010 (75 FR 72878), titled: ``Pipeline Safety: Updates to Pipeline and Liquefied... complete Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection...

  16. Decommissioning Handbook

    SciTech Connect

    Cusack, J.G.; Dalfonso, P.H.; Lenyk, R.G.

    1994-12-31

    The Decommissioning Handbook provides technical guidance on conducting decommissioning projects. Information presented ranges from planning logic, regulations affecting decommissioning, technology discussion, health and safety requirements, an developing a cost estimate. The major focus of the handbook are the technologies -- decontamination technologies, waste treatment, dismantling/segmenting/demolition, and remote operations. Over 90 technologies are discussed in the handbook providing descriptions, applications, and advantages/disadvantages. The handbook was prepared to provide a compendium of available or potentially available technologies in order to aid the planner in meeting the specific needs of each decommissioning project. Other subjects presented in the Decommissioning Handbook include the decommissioning plan, characterization, final project configuration based planning, environmental protection, and packaging/transportation. These discussions are presented to complement the technologies presented in the handbook.

  17. Decommissioning Handbook

    SciTech Connect

    Not Available

    1994-03-01

    The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

  18. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    SciTech Connect

    Michael Kruzic

    2007-09-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

  19. Completion of the decommissioning of a former active handling building at UKAEA Winfrith

    SciTech Connect

    Brown, N.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2007-07-01

    Since July 2000, NUKEM Limited has been carrying out the full decommissioning of a former Active Handling Building A59 at Winfrith in Dorset under contract from the nuclear site licence holder, UKAEA. Work has generally centred upon clearance and decontamination of the two heavily shielded suites of caves originally used to carry out remote examination of irradiated nuclear fuel elements although a number of other supporting facilities are also involved. This work has proceeded successfully to completion following extensive decontamination of the caves and associated facilities and has been followed by the recent demolition of the main containment building structure. This has permitted a start to be made on the demolition of the two heavily shielded suites of caves which is to be followed by removal of the building slab and restoration of the site. This paper reviews some of the significant tasks undertaken during the past year in preparation for the building and cave line demolition operations. It also reviews the building structure removal and recent progress made with the demolition of the two heavily reinforced concrete cave lines. The procedure used for monitoring the concrete debris from the cave lines has had to be revised during these operations and the reasons for this and a temporary delay in the cave line demolition will be discussed in the context of the remaining sections of the programme. This decommissioning programme has been achieved throughout by the employment of a non-adversarial team working approach between client and contractor. This has been instrumental in developing cost-effective and safe solutions to a range of problems during the programme, demonstrating the worth of adopting this co-operative approach for mutual benefit. (authors)

  20. Money Related Decommissioning and Funding Decision Making

    SciTech Connect

    Goodman, Lynne S.

    2008-01-15

    'Money makes the world go round', as the song says. It definitely influences decommissioning decision-making and financial assurance for future decommissioning. This paper will address two money-related decommissioning topics. The first is the evaluation of whether to continue or to halt decommissioning activities at Fermi 1. The second is maintaining adequacy of financial assurance for future decommissioning of operating plants. Decommissioning costs considerable money and costs are often higher than originally estimated. If costs increase significantly and decommissioning is not well funded, decommissioning activities may be deferred. Several decommissioning projects have been deferred when decision-makers determined future spending is preferable than current spending, or when costs have risen significantly. Decommissioning activity timing is being reevaluated for the Fermi 1 project. Assumptions for waste cost-escalation significantly impact the decision being made this year on the Fermi 1 decommissioning project. They also have a major impact on the estimated costs for decommissioning currently operating plants. Adequately funding full decommissioning during plant operation will ensure that the users who receive the benefit pay the full price of the nuclear-generated electricity. Funding throughout operation also will better ensure that money is available following shutdown to allow decommissioning to be conducted without need for additional funds.

  1. Preliminary decommissioning study reports

    SciTech Connect

    Peretz, F.J.

    1984-09-01

    The Molten Salt Reactor Experiment (MSRE) is one of approximately 76 facilities currently managed by the ORNL Surplus Facilities Management Program (SFMP). This program, as part of the DOE national SFMP, is responsible for the maintenance and surveillance and the final decommissioning of radioactively-contaminated surplus ORNL facilities. A long range planning effort is being conducted that will outline the scope and objectives of the ORNL program and establish decommissioning priorities based on health and safety concerns, budget constraints, and other programmatic constraints. In support of this SFMP planning activity, preliminary engineering assessments are being conducted for each of the ORNL surplus facilities currently managed under the program. These efforts, in general, are designed to: (1) provide an initial assessment of the potential decommissioning alternatives; (2) choose a preferred alternative and provide a justification for that choice, and (3) provide a preliminary description of the decommissioning plan, including cost and schedule estimates. Because of several issues which cannot be evaluated quantitatively at this time, this report on the MSRE does not select a most probable decommissioning mode'' but rather discusses the issues and representative alternatives for disposal of the MSRE fuel salts and decommissioning of the facility. A budget and schedule representative of the types of activities likely to be required is also suggested for preliminary use in the SFMP Long Range Plan.

  2. International Research Reactor Decommissioning Project

    SciTech Connect

    Leopando, Leonardo; Warnecke, Ernst

    2008-01-15

    Many research reactors have been or will be shut down and are candidates for decommissioning. Most of the respective countries neither have a decommissioning policy nor the required expertise and funds to effectively implement a decommissioning project. The IAEA established the Research Reactor Decommissioning Demonstration Project (R{sup 2}D{sup 2}P) to help answer this need. It was agreed to involve the Philippine Research Reactor (PRR-1) as model reactor to demonstrate 'hands-on' experience as it is just starting the decommissioning process. Other facilities may be included in the project as they fit into the scope of R{sup 2}D{sup 2}P and complement to the PRR-1 decommissioning activities. The key outcome of the R{sup 2}D{sup 2}P will be the decommissioning of the PRR-1 reactor. On the way to this final goal the preparation of safety related documents (i.e., decommissioning plan, environmental impact assessment, safety analysis report, health and safety plan, cost estimate, etc.) and the licensing process as well as the actual dismantling activities could provide a model to other countries involved in the project. It is expected that the R{sup 2}D{sup 2}P would initiate activities related to planning and funding of decommissioning activities in the participating countries if that has not yet been done.

  3. 75 FR 49943 - New Agency Information Collection Activity Under OMB Review: Pipeline System Operator Security...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-16

    ... soliciting comments, of the following collection of information on July 29, 2009, 74 FR 37723. The collection... attempt to disrupt pipeline operations or activities that could be precursors to such an attempt. Such... pipeline operations or activities that could be precursors to such an attempt. Number of Respondents:...

  4. Educational understanding of pollution prevention in decontamination and decommissioning/environmental restoration activities

    SciTech Connect

    Betsch, M.D.; Lewis, R.A.

    1995-05-01

    Demolishing outdated structures from the US Department of Energy Hanford Site in Washington, generates large quantities of waste which can be minimized. The Hanford cleanup is one of the world`s largest and most complex environmental restoration efforts. Approximately 280 square miles of ground water and soil are contaminated; there are more than 80 surplus facilities, including nine shut-down nuclear reactors in various stages of decay; and there are 177 underground waste storage tanks containing highly radioactive waste. In all, 1,500 cleanup sites have been identified and the Environmental Restoration Contractor (ERC) is currently responsible for surveillance and maintenance of 170 structures. A two hour orientation training in pollution prevention was developed by the Westinghouse Hanford Company to provide all Decontamination and Decommissioning/Environmental Restoration (D&D/ER) personnel with the knowledge to apply waste minimization principles during their cleanup activities. The ERC Team Pollution Prevention Workshop serves to communicate pollution prevention philosophies and influences the way D&D/ER projects are conducted at the Hanford Site.

  5. A survey of commercially available manipulators, end-effectors, and delivery systems for reactor decommissioning activities

    SciTech Connect

    Henley, D.R.; Litka, T.J.

    1996-05-01

    Numerous nuclear facilities owned by the U.S. Department of Energy (DOE) are under consideration for decommissioning. Currently, there are no standardized, automated, remote systems designed to dismantle and thereby reduce the size of activated reactor components and vessels so that they can be packaged and shipped to disposal sites. Existing dismantling systems usually consist of customized, facility-specific tooling that has been developed to dismantle a specific reactor system. Such systems have a number of drawbacks. Generally, current systems cannot be disassembled, moved, and reused. Developing and deploying the tooling for current systems is expensive and time-consuming. In addition, the amount of manual work is significant because long-handled tools must be used; as a result, personnel are exposed to excessive radiation. A standardized, automated, remote system is therefore needed to deliver the tooling necessary to dismantle nuclear facilities at different locations. Because this system would be reusable, it would produce less waste. The system would also save money because of its universal design, and it would be more reliable than current systems.

  6. Safety enhancement of oil trunk pipeline crossing active faults on Sakhalin Island

    NASA Astrophysics Data System (ADS)

    Tishkina, E.; Antropova, N.; Korotchenko, T.

    2015-11-01

    The article explores the issues concerning safety enhancement of pipeline active fault crossing on Sakhalin Island. Based on the complexity and analysis results, all the faults crossed by pipeline system are classified into five categories - from very simple faults to extremely complex ones. The pipeline fault crossing design is developed in accordance with the fault category. To enhance pipeline safety at fault crossing, a set of methods should be applied: use of pipes of different safety classes and special trench design in accordance with soil permeability characteristics.

  7. 77 FR 46155 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-02

    ... information collection was published in the Federal Register on May 9, 2012, (77 FR 27279) under Docket No... April 11, 2000, (65 FR 19477) or visit http://www.regulations.gov before submitting any such comments... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection...

  8. 75 FR 13807 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-23

    ... Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit http... published in the Federal Register on July 2, 2009 (74 FR 31675) and comments were submitted to Docket No... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information Collection...

  9. 75 FR 30099 - Pipeline Safety: Information Collection Activities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-28

    ... 23, 2010, (75 FR 13807). The agency did not receive any comments. The information collection is... Rulemaking for the One Rule was published in the Federal Register on July 2, 2009, (74 FR 31675) and comments... TRANSPORTATION Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Information...

  10. SU-E-T-534: Level of Residual Radioactivity of Activated Parts of a Decommissioned Cyclotron

    SciTech Connect

    Choi, HHF; Leung, TM; Chiu, TL; Yang, B; Wu, PM; Cheung, KY; Yu, SK

    2015-06-15

    Purpose: CTI cyclotron RDS-111 was used at the Hong Kong Sanatorium and Hospital (HKSH) to produce radiopharmaceuticals and radioactive tracers for diagnostic scans between 1999 and 2007. During the operation, some machine components became radioactive by activation. For the safety of staff, decommissioning took place in 2009, two years after the cyclotron had stopped operation. This study investigates the residual radioactivity and radionuclides found in different cyclotron components in 2014 in compliance with the local regulations in Hong Kong for transfer of radioactive waste. Methods: A representative sample of each part was counted using a high-purity germanium detector (manufacturer: ORTECT) for at least four hours. GammaVision, a multichannel analyzer software, was used to identify the radionuclides found in the cyclotron components, as well as the associated activities. A standard library and a Mariscotti peak search algorithm were used to identify the present radionuclides. Only radionuclides with half-life greater than 180 days were considered. Results: Among the components, the Havar target foil has the highest specific activity ((4.6±0.6)×10{sup 2} Bq/g), with Co-60 being the most prominent ((3.8±0.5)×10{sup 2} Bq/g). The total activity of the target foil, however, is still low due to its small mass of 0.04 g. Radioisotopes Mn-54 (46±6 Bq/g), Na-22 (6.8±0.8 Bq/g), Co-57 (7.3±0.9 Bq/g), and Fe-59 (6.0±0.9 Bq/g) have also been detected in the target foil. The target window holder and the vacuum window register a specific activity of 88.3±0.6 Bq/g and 48.6±0.1 Bq/g, respectively. Other components, such as the collimator, the target tube, the valve body and the beamline, are also found with trace amounts of radionuclides. Conclusion: Even seven years after the cyclotron had stopped operation, some components still exhibited residual radioactivity from activation exceeding the IAEA clearance levels. Special consideration for radiological

  11. Decommissioning an Active Historical Reactor Facility at the Savannah River Site - 13453

    SciTech Connect

    Bergren, Christopher L.; Long, J. Tony; Blankenship, John K.; Adams, Karen M.

    2013-07-01

    action for the In Situ Decommissioning (ISD) of the 105-C Disassembly Basin. ISD consisted of stabilization/isolation of remaining contaminated water, sediment, activated reactor equipment, and scrap metal by filling the DB with underwater non-structural grout to the appropriate (-4.877 meter) grade-level, thence with dry area non-structural grout to the final -10 centimeter level. The roof over the DB was preserved due to its potential historical significance and to prevent the infiltration of precipitation. Forced evaporation was the form of treatment implemented to remove the approximately 9.1 M liters of contaminated basin water. Using specially formulated grouts, irradiated materials and sediment were treated by solidification/isolation thus reducing their mobility, reducing radiation exposure and creating an engineered barrier thereby preventing access to the contaminants. Grouting provided a low permeability barrier to minimize any potential transport of contaminants to the aquifer. Efforts were made to preserve the historical significance of the Reactor in accordance with the National Historic Preservation Act. ISD provides a cost effective means to isolate and contain residual radioactivity from past nuclear operations allowing natural radioactive decay to reduce hazards to manageable levels. This method limits release of radiological contamination to the environment, minimizes radiation exposure to workers, prevents human/animal access to the hazardous substances, and allows for ongoing monitoring of the decommissioned facility. Field construction was initiated in August 2011; evaporator operations commenced January 2012 and ended July 2012 with over 9 M liters of water treated/removed. Over 8,525 cubic meters of grout were placed, completing in August 2012. The project completed with an excellent safety record, on schedule and under budget. (authors)

  12. Site decommissioning management plan

    SciTech Connect

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  13. Regional environmental assessment: Gulf of Mexico pipeline activities

    SciTech Connect

    DeWald, O.E.; Burdette, M.K.; French, C.O.; Beckert, H.

    1983-08-01

    Pipeline installations on the Gulf of Mexico Outer Continental Shelf (OCS) have affected a wide range of living and nonliving environmental variables (i.e., water quality, biologically sensitive areas, and food-web relationships) for the past 30 years. Much of the information included herein pertains to a description of the existing environment for offshore and onshore coastal areas contiguous to the Gulf of Mexico and an analysis of potential pipeline proposals and alternatives.

  14. 78 FR 26057 - Extension of Agency Information Collection Activity Under OMB Review: Pipeline Corporate Security...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-03

    ... SECURITY Transportation Security Administration Extension of Agency Information Collection Activity Under OMB Review: Pipeline Corporate Security Review AGENCY: Transportation Security Administration, DHS. ACTION: 30-day Notice. SUMMARY: This notice announces that the Transportation Security...

  15. Active faults crossing trunk pipeline routes: some important steps to avoid the disaster

    NASA Astrophysics Data System (ADS)

    Besstrashnov, Vladimir; Strom, Alexander

    2010-05-01

    Trunk pipelines that pass through tectonically active areas connecting oil and gas reservoirs with terminals and refineries cross active faults that can produce large earthquakes. Besides strong motion affecting vast areas, these earthquakes are often associated with surface faulting that provides additional hazard to pipelines. To avoid significant economic losses and environmental pollution, pipelines should be designed to sustain both effects (shaking and direct rupturing) without pipe damage and spill. Special studies aimed to provide necessary input data for the designers should be performed in the course of engineering survey. However, our experience on conducting and review of such studies for several oil and gas trunk pipelines in Russia show urgent need of more strict definition of basic conceptions and approaches used for identification and localization of these potentially hazardous tectonic features. Identification of active faults (fault zones) considered as causative faults - sources of strong motion caused by seismic waves that affect dozens kilometers of pipeline route can be done by use of both direct and indirect evidence of Late Pleistocene - Holocene activity of faults and fault zones. Since strong motion parameters can be considered as constant within the near-field zone, which width in case of large earthquake is up to dozens kilometers, accuracy of active fault location is not so critical and ±1-2 km precision provided by use of indirect evidence is acceptable. In contrast, if one have to identify and characterize zones of potential surface rupturing that require special design of the endangered pipeline section, only direct evidence of such activity can provide reliable input data for crossing design with relevant accuracy of fault location, amount and direction of displacement. Only traces of surface faults displacing Late Pleistocene - Holocene sediments and/or geomorphic features are considered as direct evidence of fault activity. Just

  16. STATUS OF THE NRC'S DECOMMISSIONING PROGRAM

    SciTech Connect

    Orlando, D. A.; Camper, L. W.; Buckley, J.

    2002-02-25

    On July 21, 1997, the U.S. Nuclear Regulatory Commission published the final rule on Radiological Criteria for License Termination (the License Termination Rule) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program. It discusses the status of permanently shut-down commercial power reactors, complex decommissioning sites, and sites listed in the Site Decommissioning Management Plan. The paper provides the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including a Standard Review Plan for evaluating plans and information submitted by licensees to support the decommissioning of nuclear facilities and the D and D Screen software for determining the potential doses from residual radioactivity. Finally, it discusses the status of the staff's current efforts to streamline the decommissioning process.

  17. DECOMMISSIONING OF SHIELDED FACILITIES AT WINFRITH USED FOR POST IRRADIATION EXAMINATION OF NUCLEAR FUELS & OTHER ACTIVE ITEMS

    SciTech Connect

    Miller, K.D.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2003-02-27

    This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the postirradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing the progress against these budgets throughout the project. Some final considerations are given to the commercial approaches to be adopted throughout this major project by the decommissioning engineers. Particular emphasis will be given to the selection of equipment and techniques that are effective so that the whole process can be carried out in a cost-effective and timely manner. The paper also provides brief complementary information obtained during the decommissioning of a plutonium-contaminated facility used for a range of semi-experimental purposes in the late 1970s. The main objective here was to remove the alpha contamination in such a manner that the volume of Plutonium Contaminated Materials (P

  18. Task 21 - Development of Systems Engineering Applications for Decontamination and Decommissioning Activities

    SciTech Connect

    Erickson, T.A.

    1998-11-01

    The objectives of this task are to: Develop a model (paper) to estimate the cost and waste generation of cleanup within the Environmental Management (EM) complex; Identify technologies applicable to decontamination and decommissioning (D and D) operations within the EM complex; Develop a database of facility information as linked to project baseline summaries (PBSs). The above objectives are carried out through the following four subtasks: Subtask 1--D and D Model Development, Subtask 2--Technology List; Subtask 3--Facility Database, and Subtask 4--Incorporation into a User Model.

  19. A graded approach to flow and transport modeling to support decommissioning activities at the Savannah river site.

    PubMed

    Dixon, Kenneth L; Lee, Patricia L; Flach, Gregory P

    2008-05-01

    A graded approach to flow and transport modeling has been used as a cost effective solution to evaluating potential groundwater risk in support of Deactivation and Decommissioning activities at the United States Department of Energy's Savannah River Site (SRS) in Aiken, South Carolina. This approach balances modeling complexity with potential risk and has been successfully used at SRS to reduce costs and accelerate schedule without compromising human health or the environment. The approach incorporates both simple spreadsheet calculations (i.e., screening models) and complex numerical modeling to evaluate the threat to human health posed by contaminants leaching from decommissioned concrete building slabs. Simple spreadsheet calculations were used to produce generic slab concentration limits for a suite of radiological and non-radiological contaminants for a chemical separations area at SRS. These limits, which are based upon the United States Environmental Protection Agency Soil Screening Guidance, were used to eliminate most building slabs from further risk assessment, thereby limiting the time and associated cost of the more rigorous assessment to higher risk facilities. Of the more than 58 facilities located in the area, to date only one slab has been found to have a contaminant concentration in excess of the area specific slab limit. For this slab, a more rigorous numerical modeling effort was undertaken which eliminated some of the simplifying and conservative assumptions inherent in the spreadsheet calculations. Results from the more sophisticated numerical model show that the remaining contaminant of concern would not likely impact groundwater above drinking water standards. PMID:18403957

  20. A GRADED APPROACH TO FLOW AND TRANSPORT MODELING TO SUPPORT DECOMMISSIONING ACTIVITIES AT THE SAVANNAH RIVER SITE, AIKEN SC

    SciTech Connect

    Dixon, K; Patricia Lee, P; Gregory Flach, G

    2007-06-07

    A graded approach to flow and transport modeling has been used as a cost effective solution to evaluating potential groundwater risk in support of Deactivation and Decommissioning activities at the United States Department of Energy's Savannah River Site. This approach incorporates both simple spreadsheet calculations and complex numerical modeling to evaluate the threat to human health posed by contaminants leaching from decommissioned concrete building slabs. Simple spread sheet calculations were used to produce generic slab concentration limits for a suite of radiological and non-radiological contaminants for a chemical separations area at Savannah River Site. These limits, which are based upon the United States Environmental Protection Agency Soil Screening guidance, were used to eliminate most building slabs from further risk assessment. Of the more than 58 facilities located in the area, to date only one slab has been found to have a contaminant concentration in excess of the area specific slab limit. For this slab, a more rigorous numerical modeling effort was undertaken reducing the conservatisms inherent in the spreadsheet calculations. Using the more sophisticated numerical model, it was possible to show that the remaining contaminant of concern would not likely impact groundwater above drinking water standards.

  1. PCB regulations and their application to deactivation and decommissioning activities: Technical assistance project

    SciTech Connect

    1996-04-01

    DOE`s economic development plans involve efforts to deactivate and decommission or refurbish site buildings and operational facilities for other uses. Site personnel must decide on disposition of stored materials, which include increasing numbers of excess and/or unwanted oil-filled equipment (e.g., transformers, hydraulic systems, heat transfer systems) and oil-containing `orphaned` drums. Because oil and these items can also contain polychlorinated biphenyls, it is essential that site personnel become aware of the regulations applicable to PCBs (adherence will minimize DOE hazardous material management liabilities). A recent incident at a DOE facility provides a case in point with important lessons to be learned for all sites within the DOE complex.

  2. Radiological survey support activities for the decommissioning of the Ames Laboratory Research Reactor Facility, Ames, Iowa

    SciTech Connect

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1984-09-01

    At the request of the Engineering Support Division of the US Department of Energy-Chicago Operations Office and in accordance with the programmatic overview/certification responsibilities of the Department of Energy Environmental and Safety Engineering Division, the Argonne National Laboratory Radiological Survey Group conducted a series of radiological measurements and tests at the Ames Laboratory Research Reactor located in Ames, Iowa. These measurements and tests were conducted during 1980 and 1981 while the reactor building was being decontaminated and decommissioned for the purpose of returning the building to general use. The results of these evaluations are included in this report. Although the surface contamination within the reactor building could presumably be reduced to negligible levels, the potential for airborne contamination from tritiated water vapor remains. This vapor emmanates from contamination within the concrete of the building and should be monitored until such time as it is reduced to background levels. 2 references, 8 figures, 6 tables.

  3. 30 CFR 250.1752 - How do I remove a pipeline?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false How do I remove a pipeline? 250.1752 Section... Pipeline Decommissioning § 250.1752 How do I remove a pipeline? Before removing a pipeline, you must: (a) Submit a pipeline removal application in triplicate to the Regional Supervisor for approval....

  4. 30 CFR 250.1752 - How do I remove a pipeline?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false How do I remove a pipeline? 250.1752 Section... Pipeline Decommissioning § 250.1752 How do I remove a pipeline? Before removing a pipeline, you must: (a) Submit a pipeline removal application in triplicate to the Regional Supervisor for approval....

  5. 30 CFR 250.1752 - How do I remove a pipeline?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false How do I remove a pipeline? 250.1752 Section... Pipeline Decommissioning § 250.1752 How do I remove a pipeline? Before removing a pipeline, you must: (a) Submit a pipeline removal application in triplicate to the Regional Supervisor for approval....

  6. Crossing Active Faults on the Sakhalin II Onshore Pipeline Route: Analysis Methodology and Basic Design

    SciTech Connect

    Vitali, Luigino; Mattiozzi, Pierpaolo

    2008-07-08

    Twin oil (20 and 24 inch) and gas (20 and 48 inch) pipeline systems stretching 800 km are being constructed to connect offshore hydrocarbon deposits from the Sakhalin II concession in the North to an LNG plant and oil export terminal in the South of Sakhalin island. The onshore pipeline route follows a regional fault zone and crosses individual active faults at 19 locations. Sakhalin Energy, Design and Construction companies took significant care to ensure the integrity of the pipelines, should large seismic induced ground movements occur during the Operational life of the facilities. Complex investigations including the identification of the active faults, their precise location, their particular displacement values and assessment of the fault kinematics were carried out to provide input data for unique design solutions. Lateral and reverse offset displacements of 5.5 and 4.5 m respectively were determined as the single-event values for the design level earthquake (DLE)--the 1000-year return period event. Within the constraints of a pipeline route largely fixed, the underground pipeline fault crossing design was developed to define the optimum routing which would minimize stresses and strain using linepipe materials which had been ordered prior to the completion of detailed design, and to specify requirements for pipe trenching shape, materials, drainage system, etc. This Paper describes the steps followed to formulate the concept of the special trenches and the analytical characteristics of the Model.

  7. Crossing Active Faults on the Sakhalin II Onshore Pipeline Route: Analysis Methodology and Basic Design

    NASA Astrophysics Data System (ADS)

    Vitali, Luigino; Mattiozzi, Pierpaolo

    2008-07-01

    Twin oil (20 & 24 inch) and gas (20 & 48 inch) pipeline systems stretching 800 km are being constructed to connect offshore hydrocarbon deposits from the Sakhalin II concession in the North to an LNG plant and oil export terminal in the South of Sakhalin island. The onshore pipeline route follows a regional fault zone and crosses individual active faults at 19 locations. Sakhalin Energy, Design and Construction companies took significant care to ensure the integrity of the pipelines, should large seismic induced ground movements occur during the Operational life of the facilities. Complex investigations including the identification of the active faults, their precise location, their particular displacement values and assessment of the fault kinematics were carried out to provide input data for unique design solutions. Lateral and reverse offset displacements of 5.5 and 4.5 m respectively were determined as the single-event values for the design level earthquake (DLE)—the 1000-year return period event. Within the constraints of a pipeline route largely fixed, the underground pipeline fault crossing design was developed to define the optimum routing which would minimize stresses and strain using linepipe materials which had been ordered prior to the completion of detailed design, and to specify requirements for pipe trenching shape, materials, drainage system, etc. This Paper describes the steps followed to formulate the concept of the special trenches and the analytical characteristics of the Model.

  8. Scour monitoring system of subsea pipeline using distributed Brillouin optical sensors based on active thermometry

    NASA Astrophysics Data System (ADS)

    Zhao, Xue-Feng; Li, Le; Ba, Qin; Ou, Jin-Ping

    2012-10-01

    A scour monitoring system of subsea pipeline is proposed using distributed Brillouin optical sensors based on active thermometry. The system consists in a thermal cable running parallel to the pipeline, which acquires frequency shift of optical sensors during heating and cooling, directly indicating temperature change. The free spans can be detected through the different behaviors of heat transfer between in-water and in-sediment scenarios. Three features were extracted from temperature time histories including magnitude, spatial continuity and temporal stability. Several experimental tests were conducted using the proposed system. The results substantiate the monitoring technique.

  9. 78 FR 10261 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-13

    ... Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety... Office of Management and Budget (OMB) approval for the revision of the gas distribution annual report... Privacy Act Statement in the Federal Register published on April 11, 2000, (65 FR 19477) or visit...

  10. Successful Geoscience Pipeline Activities for High School and College Students

    NASA Astrophysics Data System (ADS)

    Furman, T.; Fail, C. F.; Adewumi, M.; Bralower, T.; Guertin, L.

    2004-12-01

    The proportion of African-American students in the College of Earth and Mineral Sciences (EMS) at Penn State is 3.3 percent, only slightly lower than the overall University Park campus proportion of 4 percent. Retention rates within EMS are excellent; a recent survey found that EMS ranks highest in student satisfaction overall at the University Park campus. Our goal to increase diversity in EMS disciplines requires us to attract new students to Penn State rather than recruiting from other areas within the institution. We have implemented three programs that appear successful in this regard, and are thus likely to form a viable pipeline from high school through graduate school. These programs operate at a college-wide level and are co-sponsored by AESEDA (Alliance for Earth Science, Engineering and Development in Africa). SEEMS (Summer Experience in EMS) is a partnership with Upward Bound Math and Science, adding 30 hours of directed research to their existing enrichment program. Students identified in 9th grade spend 6 weeks each summer in residence at PSU, where they receive classroom instruction in core academic areas in addition to a group research project led by faculty and graduate students. SEEMS students are likely PSU recruits: all are accepted to college, 85 percent plan to attend college within PA, and all have strong family support for education as well as for careers in EMS. Pre- and post-experience surveys indicate strong positive changes in perception of EMS careers, particularly with regard to levels of intellectual challenge and starting salary. We maintain personal contact with these students and encourage them to attend PSU when they graduate. SROP (Summer Research Opportunity Program) is administered by the Committee on Institutional Cooperation, the academic arm of the Big 10, and provides residential research internships for students from HBCU and MSI campuses. EMS participates in SROP by funding research interns and providing strong individual

  11. Responding To Changes in the Decommissioning Plans for Demolition of a Former Active Handling Building at The United Kingdom Atomic Energy Establishment Winfrith

    SciTech Connect

    Brown, N.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2006-07-01

    The full decommissioning of the former Active Handling Building A59 at Winfrith in Dorset is being carried out by RWE NUKEM Limited under contract from the site owners and nuclear site licence holder, United Kingdom Atomic Energy Authority (UKAEA). Following recent government changes, the United Kingdom's Nuclear Decommissioning Authority (NDA) has now set up contracts with UKAEA for delivery of the site clean-up programme. The building contains two heavily shielded suites of caves originally used to carry out remote examination of irradiated nuclear fuel elements together with other supporting facilities. The original intention was to demolish the caves ahead of the building but after detailed consideration it was concluded that demolition of the building in advance of the caves was more operationally effective. As a result, the original decommissioning plan had to be reworked to reflect these changes. The paper briefly explains how this situation arose and the means by which the problems experienced were overcome by a complete revision to the decommissioning programme. The updated plan has been adopted by UKAEA and work is now proceeding apace to clear the building of redundant items, to complete decontamination of all remaining areas and facilities and to carry out detailed radiological surveys to confirm that the building structure is clean and ready for demolition. Both cave lines have been completely decontaminated to low residual levels of activity and are essentially ready for controlled demolition. This paper describes some of the significant tasks undertaken during the past year with particular reference to the decommissioning techniques that gave the greatest success and the limitations of others originally considered. Some of these processes were aimed at minimising the volume of low level waste (LLW) generated by using standard off-the-shelf equipment to remove contamination from {approx}5 Ton concrete blocks recovered from both cave line structures. A

  12. Scour Monitoring System for Subsea Pipeline Based on Active Thermometry: Numerical and Experimental Studies

    PubMed Central

    Zhao, Xuefeng; Li, Weijie; Song, Gangbing; Zhu, Zuo; Du, Jun

    2013-01-01

    A scour monitoring system for subsea pipeline based on active thermometry is proposed in this paper. The temperature reading of the proposed system is based on a distributed Brillouin optical fiber sensing technique. A thermal cable acts as the main component of the system, which consists of a heating belt, armored optical fibers and heat-shrinkable tubes which run parallel to the pipeline. The scour-induced free span can be monitored through different heat transfer behaviors of in-water and in-sediment scenarios during heating and cooling processes. Two sets of experiments, including exposing different lengths of the upper surface of the pipeline to water and creating free spans of various lengths, were carried out in laboratory. In both cases, the scour condition was immediately detected by the proposed monitoring system, which confirmed the system is robust and very sensitive. Numerical study of the method was also investigated by using the finite element method (FEM) with ANSYS, resulting in reasonable agreement with the test data. This brand new system provides a promising, low cost, highly precise and flexible approach for scour monitoring of subsea pipelines. PMID:23348035

  13. Shippingport Station Decommissioning Project decommissioning plan. Volume XII

    SciTech Connect

    Not Available

    1983-01-01

    Information is presented concerning allowable residual contamination levels in soil for decommissioning the Shippingport reactor site; draft statement of work for the decommissioning operations contractor; the Shippingport Station Decommissioning Project Change Control Board charter; the surplus facilities management program; the Shippingport Station Decommissioning Project charter; DOE-RL/DOE-PNR program management agreement; and draft occupational medical plan for the decommissioning project.

  14. 77 FR 16052 - Information Collection Activities: Pipelines and Pipeline Rights-of-Way; Submitted for Office of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-19

    ... Number: 1014-0016. Abstract: The Outer Continental Shelf (OCS) Lands Act, as amended (43 U.S.C. 1331 et... through the submerged lands of the OCS for pipelines ``* * * for the transportation of oil, natural gas... initial 60-day FR notice and now, BSEE requested and obtained OMB approval via a Notice of Action...

  15. 76 FR 75894 - Information Collection Activities: Pipelines and Pipeline Rights-of-Way; Submitted for Office of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-05

    ... Outer Continental Shelf (OCS) Lands Act, as amended (43 U.S.C. 1331 et seq. and 43 U.S.C. 1801 et seq.... Section 1334(e) authorizes the Secretary to grant ROWs through the submerged lands of the OCS for... pipeline, as constructed, will provide for safe transportation of minerals through the submerged lands...

  16. Measurement of activity distribution using photostimulable phosphor imaging plates in decommissioned 10 MV medical linear accelerator.

    PubMed

    Fujibuchi, Toshioh; Yonai, Shunsuke; Yoshida, Masahiro; Sakae, Takeji; Watanabe, Hiroshi; Abe, Yoshihisa; Itami, Jun

    2014-08-01

    Photonuclear reactions generate neutrons in the head of the linear accelerator. Therefore, some parts of the linear accelerator can become activated. Such activated materials must be handled as radioactive waste. The authors attempted to investigate the distribution of induced radioactivity using photostimulable phosphor imaging plates. Autoradiographs were produced from some parts of the linear accelerator (the target, upper jaw, multileaf collimator and shielding). The levels of induced radioactivity were confirmed to be non-uniform within each part from the autoradiographs. The method was a simple and highly sensitive approach to evaluating the relative degree of activation of the linear accelerators, so that appropriate materials management procedures can be carried out.

  17. 77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-13

    ... Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR 19477) or visit http... Pipeline Systems Incident Report, and Hazardous Liquid Pipeline Systems Accident Report AGENCY: Pipeline... several minor revisions to the hazardous liquid pipeline systems accident report and the gas...

  18. Pilot-scale treatability testing -- Recycle, reuse, and disposal of materials from decontamination and decommissioning activities: Soda blasting demonstration

    SciTech Connect

    1995-08-01

    The US Department of Energy (DOE) is in the process of defining the nature and magnitude of decontamination and decommissioning (D and D) obligations at its sites. With disposal costs rising and available storage facilities decreasing, DOE is exploring and implementing new waste minimizing D and D techniques. Technology demonstrations are being conducted by LMES at a DOE gaseous diffusion processing plant, the K-25 Site, in Oak Ridge, Tennessee. The gaseous diffusion process employed at Oak Ridge separated uranium-235 from uranium ore for use in atomic weapons and commercial reactors. These activities contaminated concrete and other surfaces within the plant with uranium, technetium, and other constituents. The objective of current K-25 D and D research is to make available cost-effective and energy-efficient techniques to advance remediation and waste management methods at the K-25 Site and other DOE sites. To support this objective, O`Brien and Gere tested a decontamination system on K-25 Site concrete and steel surfaces contaminated with radioactive and hazardous waste. A scouring system has been developed that removes fixed hazardous and radioactive surface contamination and minimizes residual waste. This system utilizes an abrasive sodium bicarbonate medium that is projected at contaminated surfaces. It mechanically removes surface contamination while leaving the surface intact. Blasting residuals are captured and dissolved in water and treated using physical/chemical processes. Pilot-scale testing of this soda blasting system and bench and pilot-scale treatment of the generated residuals were conducted from December 1993 to September 1994.

  19. Decontamination & decommissioning focus area

    SciTech Connect

    1996-08-01

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  20. The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities

    SciTech Connect

    Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee

    2007-07-01

    Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

  1. Assessment of derived emission limits for radioactive effluents resulted from the decommissioning activities of the VVR-S nuclear research reactor.

    PubMed

    Tuca, C; Stochioiu, A; Sahagia, M; Gurau, D; Dragusin, M

    2015-10-01

    This paper presents complex studies on establishment of derived emission limits for potential radionuclides emitted as gaseous and liquid effluents, during the decommissioning activities (2nd and 3rd phases) of a nuclear research reactor, cooled and moderated with distilled water, type VVR-S, owned by the IFIN-HH. In the present paper there are described: the analysis methods and equipment used, the methodologies for calculating doses and the Derived Emission Limits (DEL), the experimentally measured activities of the representative radionuclides found in gaseous and liquid effluents resulted from decommissioning activities, as well as the effective derived limits of liquid and gaseous effluents, applying the calculation methodologies, specific to critical categories of exposed subjects. A constraint effective dose limit for a person from the critical group of 50 μSv/year was considered in calculations. From the comparison of the two series of values, measured released activities and DELs, there has been concluded that for the gaseous effluents they comply with the DELs, while in the case of liquid effluents they are higher and consequently they must be treated as liquid radioactive wastes.

  2. Assessment of derived emission limits for radioactive effluents resulted from the decommissioning activities of the VVR-S nuclear research reactor.

    PubMed

    Tuca, C; Stochioiu, A; Sahagia, M; Gurau, D; Dragusin, M

    2015-10-01

    This paper presents complex studies on establishment of derived emission limits for potential radionuclides emitted as gaseous and liquid effluents, during the decommissioning activities (2nd and 3rd phases) of a nuclear research reactor, cooled and moderated with distilled water, type VVR-S, owned by the IFIN-HH. In the present paper there are described: the analysis methods and equipment used, the methodologies for calculating doses and the Derived Emission Limits (DEL), the experimentally measured activities of the representative radionuclides found in gaseous and liquid effluents resulted from decommissioning activities, as well as the effective derived limits of liquid and gaseous effluents, applying the calculation methodologies, specific to critical categories of exposed subjects. A constraint effective dose limit for a person from the critical group of 50 μSv/year was considered in calculations. From the comparison of the two series of values, measured released activities and DELs, there has been concluded that for the gaseous effluents they comply with the DELs, while in the case of liquid effluents they are higher and consequently they must be treated as liquid radioactive wastes. PMID:26162768

  3. Safety of Decommissioning of Nuclear Facilities

    SciTech Connect

    Batandjieva, B.; Warnecke, E.; Coates, R.

    2008-01-15

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

  4. An analytical pipeline to compare and characterise the anthocyanin antioxidant activities of purple sweet potato cultivars.

    PubMed

    Hu, Yijie; Deng, Liqing; Chen, Jinwu; Zhou, Siyu; Liu, Shuang; Fu, Yufan; Yang, Chunxian; Liao, Zhihua; Chen, Min

    2016-03-01

    Purple sweet potato (Ipomoea batatas L.) is rich in anthocyanin pigments, which are valuable constituents of the human diet. Techniques to identify and quantify anthocyanins and their antioxidant potential are desirable for cultivar selection and breeding. In this study, we performed a quantitative and qualitative chemical analysis of 30 purple sweet potato (PSP) cultivars, using various assays to measure reducing power radical-scavenging activities, and linoleic acid autoxidation inhibition activity. Grey relational analysis (GRA) was applied to establish relationships between the antioxidant activities and the chemical fingerprints, in order to identify key bioactive compounds. The results indicated that four peonidin-based anthocyanins and three cyanidin-based anthocyanins make significant contributions to antioxidant activity. We conclude that the analytical pipeline described here represents an effective method to evaluate the antioxidant potential of, and the contributing compounds present in, PSP cultivars. This approach may be used to guide future breeding strategies.

  5. 78 FR 69121 - Information Collection Activities: Open and Nondiscriminatory Access to Oil and Gas Pipelines...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-18

    ... to Oil and Gas Pipelines Under the OCS Lands Act; Proposed Collection; Comment Request ACTION: 60-day... Nondiscriminatory Access to Oil and Gas Pipelines Under the OCS Lands Act. DATES: You must submit comments by... Nondiscriminatory Access to Oil and Gas Pipelines Under the OCS Lands Act. OMB Control Number: 1014-0012....

  6. Decommissioning at AWE

    SciTech Connect

    Biles, K.; Hedges, M.; Campbell, C

    2008-07-01

    AWE (A) has been at the heart of the UK Nuclear deterrent since it was established in the early 1950's. It is a nuclear licensed site and is governed by the United Kingdoms Nuclear Installation Inspectorate (NII). AWE plc on behalf of the Ministry of Defence (MOD) manages the AWE (A) site and all undertakings including decommissioning. Therefore under NII license condition 35 'Decommissioning', AWE plc is accountable to make and implement adequate arrangements for the decommissioning of any plant or process, which may affect safety. The majority of decommissioning projects currently being undertaken are to do with Hazard category 3, 4 or 5 facilities, systems or plant that have reached the end of their operational span and have undergone Post-Operational Clean-Out (POCO). They were either built for the production of fissile components, for supporting the early reactor fuels programmes or for processing facility waste arisings. They either contain redundant contaminated gloveboxes associated process areas, process plant or systems or a combination of all. In parallel with decommissioning project AWE (A) are undertaking investigation into new technologies to aid decommissioning projects; to remove the operative from hands on operations; to develop and implement modifications to existing process and techniques used. AWE (A) is currently going thorough a sustained phase of upgrading its facilities to enhance its scientific capability, with older facilities, systems and plant being replaced, making decommissioning a growth area. It is therefore important to the company to reduce these hazards progressively and safety over the coming years, making decommissioning an important feature of the overall legacy management aspects of AWE PLC's business. This paper outlines the current undertakings and progress of Nuclear decommissioning on the AWE (A) site. (authors)

  7. A Quantitative High-Throughput Screening Data Analysis Pipeline for Activity Profiling.

    PubMed

    Huang, Ruili

    2016-01-01

    The US Tox21 program has developed in vitro assays to test large collections of environmental chemicals in a quantitative high-throughput screening (qHTS) format, using triplicate 15-dose titrations to generate over 50 million data points to date. Counter screens are also employed to minimize interferences from non-target-specific assay artifacts, such as compound auto fluorescence and cytotoxicity. New data analysis approaches are needed to integrate these data and characterize the activities observed from these assays. Here, we describe a complete analysis pipeline that evaluates these qHTS data for technical quality in terms of signal reproducibility. We integrate signals from repeated assay runs, primary readouts, and counter screens to produce a final call on on-target compound activity. PMID:27518629

  8. A Quantitative High-Throughput Screening Data Analysis Pipeline for Activity Profiling.

    PubMed

    Huang, Ruili

    2016-01-01

    The US Tox21 program has developed in vitro assays to test large collections of environmental chemicals in a quantitative high-throughput screening (qHTS) format, using triplicate 15-dose titrations to generate over 50 million data points to date. Counter screens are also employed to minimize interferences from non-target-specific assay artifacts, such as compound auto fluorescence and cytotoxicity. New data analysis approaches are needed to integrate these data and characterize the activities observed from these assays. Here, we describe a complete analysis pipeline that evaluates these qHTS data for technical quality in terms of signal reproducibility. We integrate signals from repeated assay runs, primary readouts, and counter screens to produce a final call on on-target compound activity.

  9. Validation of MCNP NPP Activation Simulations for Decommissioning Studies by Analysis of NPP Neutron Activation Foil Measurement Campaigns

    NASA Astrophysics Data System (ADS)

    Volmert, Ben; Pantelias, Manuel; Mutnuru, R. K.; Neukaeter, Erwin; Bitterli, Beat

    2016-02-01

    In this paper, an overview of the Swiss Nuclear Power Plant (NPP) activation methodology is presented and the work towards its validation by in-situ NPP foil irradiation campaigns is outlined. Nuclear Research and consultancy Group (NRG) in The Netherlands has been given the task of performing the corresponding neutron metrology. For this purpose, small Aluminium boxes containing a set of circular-shaped neutron activation foils have been prepared. After being irradiated for one complete reactor cycle, the sets have been successfully retrieved, followed by gamma-spectrometric measurements of the individual foils at NRG. Along with the individual activities of the foils, the reaction rates and thermal, intermediate and fast neutron fluence rates at the foil locations have been determined. These determinations include appropriate corrections for gamma self-absorption and neutron self-shielding as well as corresponding measurement uncertainties. The comparison of the NPP Monte Carlo calculations with the results of the foil measurements is done by using an individual generic MCNP model functioning as an interface and allowing the simulation of individual foil activation by predetermined neutron spectra. To summarize, the comparison between calculation and measurement serve as a sound validation of the Swiss NPP activation methodology by demonstrating a satisfying agreement between measurement and calculation. Finally, the validation offers a chance for further improvements of the existing NPP models by ensuing calibration and/or modelling optimizations for key components and structures.

  10. Decontamination and Decommissioning Experience at a Sellafield Uranium Purification Plant

    SciTech Connect

    Prosser, J.L.

    2006-07-01

    Built in the 1950's, this plant was originally designed to purify depleted uranyl nitrate solution arising from reprocessing operations at the Primary Separation and Head End Plant (Fig. 1). The facility was used for various purposes throughout its life cycle such as research, development and trial based processes. Test rigs were operated in the building from the 1970's until 1984 to support development of the process and equipment now used at Sellafield's Thermal Oxide Reprocessing Plant (THORP). The extensive decommissioning program for this facility began over 15 years ago. Many challenges have been overcome throughout this program such as decommissioning the four main process cells, which were very highly alpha contaminated. The cells contained vessels and pipeline systems that were contaminated to such levels that workers had to use pressurized suits to enter the cells. Since decommissioning at Sellafield was in its infancy, this project has trialed various decontamination/decommissioning methods and techniques in order to progress the project, and this has provided valuable learning for other decommissioning projects. The project has included characterization, decontamination, dismantling, waste handling, and is now ready for demolition during late 2005, early 2006. This will be the first major facility within the historic Separation Area at Sellafield to be demolished down to base slab level. The lessons learnt from this project will directly benefit numerous decommissioning projects as the cleanup at Sellafield continues. (authors)

  11. 78 FR 38803 - Pipeline Safety: Information Collection Activities, Revisions to Incident and Annual Reports for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-27

    ... Incident Report--Natural and Other Gas Transmission and Gathering Pipeline Systems; PHMSA F 7100.2-1 Annual Report for Calendar Year 20-- Natural and Other Gas Transmission and Gathering Pipeline Systems; PHMSA F 7100.3 Incident Report--Liquefied Natural Gas Facilities; and PHMSA F 7100.3-1 Annual Report...

  12. 75 FR 73117 - New Agency Information Collection Activity Under OMB Review: Pipeline Corporate Security Review

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-29

    ..., 74 FR 42086. The collection encompasses interviews and site visits with pipeline operators regarding...: Pipeline Corporate Security Review AGENCY: Transportation Security Administration, DHS. ACTION: 30-day... Budget (OMB) for review and approval under the Paperwork Reduction Act. The ICR describes the nature...

  13. 76 FR 8401 - Pipeline Safety: Agency Information Collection Activities: Notice of Request for Extension of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-14

    ... collection was published in the Federal Register on December 7, 2010 (75 FR 76077) under Docket No. PHMSA.... SUPPLEMENTARY INFORMATION: Title: Pipeline Safety: Periodic Underwater Inspections. OMB Control Number: 2137... pipeline safety regulations (49 CFR parts 190-199) require operators to conduct appropriate...

  14. 78 FR 41829 - Pipeline Safety: Information Collection Activities, Revision to Annual Report for Hazardous...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-11

    ... the information collection was published on February 6, 2013, (78 FR 8699). PHMSA received one comment..., Revision to Annual Report for Hazardous Liquid Pipeline Systems AGENCY: Pipeline and Hazardous Materials... from hazardous liquid operators' annual reports is an important tool for identifying safety trends...

  15. 78 FR 8699 - Pipeline Safety: Information Collection Activities, Revision to Annual Report for Hazardous...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-06

    ... complete Privacy Act Statement in the Federal Register published on April 11, 2000, (65 FR 19477) or visit..., Revision to Annual Report for Hazardous Liquid Pipeline Systems AGENCY: Pipeline and Hazardous Materials...) invites comments on its intention to revise form PHMSA F 7000-1.1--Annual Report for Hazardous...

  16. Decommissioning of the Iraq former nuclear complex

    SciTech Connect

    Abbas, Mohammed; Helou, Tuama; Ahmead, Bushra; Al-Atia, Mousa; Al-Mubarak, Mowaffak; Danneels, Jeffrey; Cochran, John; Sorenson, Ken; Coates, Roger

    2007-07-01

    Available in abstract form only. Full text of publication follows: A number of sites in Iraq have some degree of radiological contamination and require decommissioning and remediation in order to ensure radiological safety. Many of these sites in Iraq are located at the nuclear research centre at Al Tuwaitha. The International Atomic Energy Agency (IAEA) Board of Governors has approved a project to assist the Government of Iraq in the evaluation and decommissioning of former facilities that used radioactive materials. The project is divided into three phases: Phase 1: collect and analyze all available data and conduct training of the Iraqi staff, Phase 2: develop a decommissioning and remediation plan, and Phase 3: implement field activities relating to decommissioning, remediation and site selection suitable for final disposal of waste. Four working groups have been established to complete the Phase 1 work and significant progress has been made in drafting a new nuclear law which will provide the legal basis for the licensing of the decommissioning of the former nuclear complex. Work is also underway to collect and analysis existing date, to prioritize future activities and to develop a waste management strategy. This will be a long-term and costly project. (authors)

  17. 30 CFR 285.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... an Alternate Use RUE? 285.1019 Section 285.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by...

  18. A Pipeline for Screening Small Molecules with Growth Inhibitory Activity against Burkholderia cenocepacia

    PubMed Central

    Selin, Carrie; Stietz, Maria S.; Blanchard, Jan E.; Hall, Dennis G.; Brown, Eric D.; Cardona, Silvia T.

    2015-01-01

    Infections with the bacteria Burkholderia cepacia complex (Bcc) are very difficult to eradicate in cystic fibrosis patients due the intrinsic resistance of Bcc to most available antibiotics and the emergence of multiple antibiotic resistant strains during antibiotic treatment. In this work, we used a whole-cell based assay to screen a diverse collection of small molecules for growth inhibitors of a relevant strain of Bcc, B. cenocepacia K56-2. The primary screen used bacterial growth in 96-well plate format and identified 206 primary actives among 30,259 compounds. From 100 compounds with no previous record of antibacterial activity secondary screening and data mining selected a total of Bce bioactives that were further analyzed. An experimental pipeline, evaluating in vitro antibacterial and antibiofilm activity, toxicity and in vivo antibacterial activity using C. elegans was used for prioritizing compounds with better chances to be further investigated as potential Bcc antibacterial drugs. This high throughput screen, along with the in vitro and in vivo analysis highlights the utility of this experimental method to quickly identify bioactives as a starting point of antibacterial drug discovery. PMID:26053039

  19. A Pipeline for Screening Small Molecules with Growth Inhibitory Activity against Burkholderia cenocepacia.

    PubMed

    Selin, Carrie; Stietz, Maria S; Blanchard, Jan E; Gehrke, Sebastian S; Bernard, Sylvain; Hall, Dennis G; Brown, Eric D; Cardona, Silvia T

    2015-01-01

    Infections with the bacteria Burkholderia cepacia complex (Bcc) are very difficult to eradicate in cystic fibrosis patients due the intrinsic resistance of Bcc to most available antibiotics and the emergence of multiple antibiotic resistant strains during antibiotic treatment. In this work, we used a whole-cell based assay to screen a diverse collection of small molecules for growth inhibitors of a relevant strain of Bcc, B. cenocepacia K56-2. The primary screen used bacterial growth in 96-well plate format and identified 206 primary actives among 30,259 compounds. From 100 compounds with no previous record of antibacterial activity secondary screening and data mining selected a total of Bce bioactives that were further analyzed. An experimental pipeline, evaluating in vitro antibacterial and antibiofilm activity, toxicity and in vivo antibacterial activity using C. elegans was used for prioritizing compounds with better chances to be further investigated as potential Bcc antibacterial drugs. This high throughput screen, along with the in vitro and in vivo analysis highlights the utility of this experimental method to quickly identify bioactives as a starting point of antibacterial drug discovery. PMID:26053039

  20. Development of improved technology for decommissioning operations

    SciTech Connect

    Allen, R.P.

    1982-07-01

    This paper describes the technology development activities conducted at Pacific Northwest Laboratory under US Department of Energy sponsorship to help ensure the availability of safe, cost-effective and environmentally sound decommissioning technology for radioactively contaminated facilities. These improved decommissioning technologies include techniques for the removal of contaminated concrete surfaces and coatings, adaptation of electropolishing and vibratory finishing decontamination techniques for field decommissioning applications, development of sensitive field instrumentation and methods for the monitoring of large surface areas, techniques for the field sectioning of contaminated components, improved contamination-stabilizing coatings and application methods, and development of a small solidification system for the field solidification of liquid waste. The results of cost/benefit studies for some of these technologies are also reported.

  1. Active incremental Support Vector Machine for oil and gas pipeline defects prediction system using long range ultrasonic transducers.

    PubMed

    Akram, Nik Ahmad; Isa, Dino; Rajkumar, Rajprasad; Lee, Lam Hong

    2014-08-01

    This work proposes a long range ultrasonic transducers technique in conjunction with an active incremental Support Vector Machine (SVM) classification approach that is used for real-time pipeline defects prediction and condition monitoring. Oil and gas pipeline defects are detected using various techniques. One of the most prevalent techniques is the use of "smart pigs" to travel along the pipeline and detect defects using various types of sensors such as magnetic sensors and eddy-current sensors. A critical short coming of "smart pigs" is the inability to monitor continuously and predict the onset of defects. The emergence of permanently installed long range ultrasonics transducers systems enable continuous monitoring to be achieved. The needs for and the challenges of the proposed technique are presented. The experimental results show that the proposed technique achieves comparable classification accuracy as when batch training is used, while the computational time is decreased, using 56 feature data points acquired from a lab-scale pipeline defect generating experimental rig.

  2. Active incremental Support Vector Machine for oil and gas pipeline defects prediction system using long range ultrasonic transducers.

    PubMed

    Akram, Nik Ahmad; Isa, Dino; Rajkumar, Rajprasad; Lee, Lam Hong

    2014-08-01

    This work proposes a long range ultrasonic transducers technique in conjunction with an active incremental Support Vector Machine (SVM) classification approach that is used for real-time pipeline defects prediction and condition monitoring. Oil and gas pipeline defects are detected using various techniques. One of the most prevalent techniques is the use of "smart pigs" to travel along the pipeline and detect defects using various types of sensors such as magnetic sensors and eddy-current sensors. A critical short coming of "smart pigs" is the inability to monitor continuously and predict the onset of defects. The emergence of permanently installed long range ultrasonics transducers systems enable continuous monitoring to be achieved. The needs for and the challenges of the proposed technique are presented. The experimental results show that the proposed technique achieves comparable classification accuracy as when batch training is used, while the computational time is decreased, using 56 feature data points acquired from a lab-scale pipeline defect generating experimental rig. PMID:24792683

  3. 76 FR 6516 - Pipeline Safety: Agency Information Collection Activities: Notice of Request for Extension of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-04

    ... Liquid, and Carbon Dioxide Pipelines and Liquefied Natural Gas Facilities. OMB Control Number: 2137-0578... soliciting comments on this ICR was published in the Federal Register on November 29, 2010 (75 FR...

  4. Pipeline Structural Health Monitoring Using Macro-fiber Composite Active Sensors

    SciTech Connect

    Thien, Andrew B.

    2006-01-10

    The United States economy is heavily dependent upon a vast network of pipeline systems to transport and distribute the nation's energy resources. As this network of pipelines continues to age, monitoring and maintaining its structural integrity remains essential to the nation's energy interests. Numerous pipeline accidents over the past several years have resulted in hundreds of fatalities and billions of dollars in property damages. These accidents show that the current monitoring methods are not sufficient and leave a considerable margin for improvement. To avoid such catastrophes, more thorough methods are needed. As a solution, the research of this thesis proposes a structural health monitoring (SHM) system for pipeline networks. By implementing a SHM system with pipelines, their structural integrity can be continuously monitored, reducing the overall risks and costs associated with current methods. The proposed SHM system relies upon the deployment of macro-fiber composite (MFC) patches for the sensor array. Because MFC patches are flexible and resilient, they can be permanently mounted to the curved surface of a pipeline's main body. From this location, the MFC patches are used to monitor the structural integrity of the entire pipeline. Two damage detection techniques, guided wave and impedance methods, were implemented as part of the proposed SHM system. However, both techniques utilize the same MFC patches. This dual use of the MFC patches enables the proposed SHM system to require only a single sensor array. The presented Lamb wave methods demonstrated the ability to correctly identify and locate the presence of damage in the main body of the pipeline system, including simulated cracks and actual corrosion damage. The presented impedance methods demonstrated the ability to correctly identify and locate the presence of damage in the flanged joints of the pipeline system, including the loosening of bolts on the flanges. In addition to damage to the actual

  5. STANDARD OPERATING PROTOCOLS FOR DECOMMISSIONING

    SciTech Connect

    Foss, D. L.; Stevens, J. L.; Gerdeman, F. W.

    2002-02-25

    Decommissioning projects at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites are conducted under project-specific decision documents, which involve extensive preparation time, public comment periods, and regulatory approvals. Often, the decision documents must be initiated at least one year before commencing the decommissioning project, and they are expensive and time consuming to prepare. The Rocky Flats Environmental Technology Site (RFETS) is a former nuclear weapons production plant at which hazardous substances and wastes were released or disposed during operations. As a result of the releases, RFETS was placed on the National Priorities List in 1989, and is conducting cleanup activities under a federal facilities compliance agreement. Working closely with interested stakeholders and state and federal regulatory agencies, RFETS has developed and implemented an improved process for obtaining the approvals. The key to streamlining the approval process has been the development of sitewide decision documents called Rocky Flats Cleanup Agreement Standard Operating Protocols or ''RSOPs.'' RSOPs have broad applicability, and could be used instead of project-specific documents. Although no two decommissioning projects are exactly the same and they may vary widely in contamination and other hazards, the basic steps taken for cleanup are usually similar. Because of this, using RSOPs is more efficient than preparing a separate project-specific decision documents for each cleanup action. Over the Rocky Flats cleanup life cycle, using RSOPs has the potential to: (1) Save over 5 million dollars and 6 months on the site closure schedule; (2) Eliminate preparing one hundred and twenty project-specific decision documents; and (3) Eliminate writing seventy-five closure description documents for hazardous waste unit closure and corrective actions.

  6. Surveillance and maintenance report on decontamination and decommissioning and remedial action activities at the Oak Ridge Y-12 plant, Oak Ridge, Tennessee. Fiscal year 1996

    SciTech Connect

    King, H.L.; Sollenberger, M.L.; Sparkman, D.E.; Reynolds, R.M.; Wayland, G.S.

    1996-12-01

    The Oak Ridge Y-12 Plant Decontamination and Decommissioning (D&D) and Remedial Action (RA) programs are part of the Environmental Restoration (ER) Division and are funded by the Office of Environmental Management (EM-40). Building 9201-4 (known as Alpha-4), three sites located within Building 9201-3 (the Oil Storage Tank, the Molten Salt Reactor Experiment Fuel Handling Facility, and the Coolant Salt Technology Facility), and Building 9419-1 (the Decontamination Facility) are currently the facilities at the Y-12 Plant included in the D&D program. The RA program provides surveillance and maintenance (S&M) and program management of ER sites at the Y-12 Plant, including selected sites listed in Appendix C of the Federal Facilities Agreement (FFA), sites listed in the Hazardous and Solid Waste Amendment (HSWA) permit Solid Waste Management Unit (SWM-U) list, and sites currently closed or undergoing post-closure activities under the Resource Conservation and Recovery Act of 1976 (RCRA) or the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). This report communicates the status of the program plans and specific S&M activities for the D&D and RA programs.

  7. Annual report of decommissioning and remedial action S&M activities for the Environmental Management Program at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-11-01

    The Oak Ridge National Laboratory (ORNL) Surveillance and Maintenance (S&M) Program performs a variety of activities to ensure that sites and facilities within its responsibility remain in a safe condition and in compliance with applicable regulations. All S&M Program activities during fiscal year (FY) 1997 were accomplished safely, with no health and safety incidents, no lost work days, and no environmental noncompliances. In addition, all activities were performed within schedule thresholds and under budget. Many remedial action (RA) sites and decontamination and decommissioning (D&D) facilities are inspected and maintained by the S&M Program. RA sites encompass approximately 650 acres and 33 D&D facilities, including 4 inactive reactors. During FY 1997, routine, preventative, and emergency maintenance activities were performed as needed at these sites and facilities. Stabilization activities were also performed to reduce risks and reduce future S&M costs. Major activities at the RA sites during FY 1997 included maintaining proper liquid levels in surface impoundments and inactive -liquid low-level waste storage tanks as well as installing a new cover at the tumulus pads in Waste Area Grouping (WAG) 6, planting trees in the First Creek Riparian Corridor, and performing over 900 well inspections. Postremediation monitoring was conducted at the 3001 Canal, Core Hole 8, the WAG 6 Resource Conservation and Recovery caps, and WAG 5 Seeps C and D; groundwater monitoring was performed in WAGs 4, 5, and 6 and at the 3001 Canal Well. At ORNL D&D facilities, significant accomplishments included contaminated lead brick removal, asbestos abatement, contaminated equipment and debris removal, and radiologically contaminated area painting.

  8. INTERNATIONAL DECOMMISSIONING SYMPOSIUM 2000

    SciTech Connect

    M.A. Ebadian, Ph.D.

    2001-01-01

    The purpose of IDS 2000 was to deliver a world-class conference on applicable global environmental issues. The objective of this conference was to publicize environmental progress of individual countries, to provide a forum for technology developer and problem-holder interaction, to facilitate environmental and technology discussions between the commercial and financial communities, and to accommodate information and education exchange between governments, industries, universities, and scientists. The scope of this project included the planning and execution of an international conference on the decommissioning of nuclear facilities, and the providing of a business forum for vendors and participants sufficient to attract service providers, technology developers, and the business and financial communities. These groups, when working together with attendees from regulatory organizations and government decision-maker groups, provide an opportunity to more effectively and efficiently expedite the decommissioning projects.

  9. Lessons Learned from the NASA Plum Brook Reactor Facility Decommissioning

    NASA Technical Reports Server (NTRS)

    2010-01-01

    NASA has been conducting decommissioning activities at its PBRF for the last decade. As a result of all this work there have been several lessons learned both good and bad. This paper presents some of the more exportable lessons.

  10. Optimal policies for aggregate recycling from decommissioned forest roads.

    PubMed

    Thompson, Matthew; Sessions, John

    2008-08-01

    To mitigate the adverse environmental impact of forest roads, especially degradation of endangered salmonid habitat, many public and private land managers in the western United States are actively decommissioning roads where practical and affordable. Road decommissioning is associated with reduced long-term environmental impact. When decommissioning a road, it may be possible to recover some aggregate (crushed rock) from the road surface. Aggregate is used on many low volume forest roads to reduce wheel stresses transferred to the subgrade, reduce erosion, reduce maintenance costs, and improve driver comfort. Previous studies have demonstrated the potential for aggregate to be recovered and used elsewhere on the road network, at a reduced cost compared to purchasing aggregate from a quarry. This article investigates the potential for aggregate recycling to provide an economic incentive to decommission additional roads by reducing transport distance and aggregate procurement costs for other actively used roads. Decommissioning additional roads may, in turn, result in improved aquatic habitat. We present real-world examples of aggregate recycling and discuss the advantages of doing so. Further, we present mixed integer formulations to determine optimal levels of aggregate recycling under economic and environmental objectives. Tested on an example road network, incorporation of aggregate recycling demonstrates substantial cost-savings relative to a baseline scenario without recycling, increasing the likelihood of road decommissioning and reduced habitat degradation. We find that aggregate recycling can result in up to 24% in cost savings (economic objective) and up to 890% in additional length of roads decommissioned (environmental objective).

  11. Optimal Policies for Aggregate Recycling from Decommissioned Forest Roads

    NASA Astrophysics Data System (ADS)

    Thompson, Matthew; Sessions, John

    2008-08-01

    To mitigate the adverse environmental impact of forest roads, especially degradation of endangered salmonid habitat, many public and private land managers in the western United States are actively decommissioning roads where practical and affordable. Road decommissioning is associated with reduced long-term environmental impact. When decommissioning a road, it may be possible to recover some aggregate (crushed rock) from the road surface. Aggregate is used on many low volume forest roads to reduce wheel stresses transferred to the subgrade, reduce erosion, reduce maintenance costs, and improve driver comfort. Previous studies have demonstrated the potential for aggregate to be recovered and used elsewhere on the road network, at a reduced cost compared to purchasing aggregate from a quarry. This article investigates the potential for aggregate recycling to provide an economic incentive to decommission additional roads by reducing transport distance and aggregate procurement costs for other actively used roads. Decommissioning additional roads may, in turn, result in improved aquatic habitat. We present real-world examples of aggregate recycling and discuss the advantages of doing so. Further, we present mixed integer formulations to determine optimal levels of aggregate recycling under economic and environmental objectives. Tested on an example road network, incorporation of aggregate recycling demonstrates substantial cost-savings relative to a baseline scenario without recycling, increasing the likelihood of road decommissioning and reduced habitat degradation. We find that aggregate recycling can result in up to 24% in cost savings (economic objective) and up to 890% in additional length of roads decommissioned (environmental objective).

  12. Optimal policies for aggregate recycling from decommissioned forest roads.

    PubMed

    Thompson, Matthew; Sessions, John

    2008-08-01

    To mitigate the adverse environmental impact of forest roads, especially degradation of endangered salmonid habitat, many public and private land managers in the western United States are actively decommissioning roads where practical and affordable. Road decommissioning is associated with reduced long-term environmental impact. When decommissioning a road, it may be possible to recover some aggregate (crushed rock) from the road surface. Aggregate is used on many low volume forest roads to reduce wheel stresses transferred to the subgrade, reduce erosion, reduce maintenance costs, and improve driver comfort. Previous studies have demonstrated the potential for aggregate to be recovered and used elsewhere on the road network, at a reduced cost compared to purchasing aggregate from a quarry. This article investigates the potential for aggregate recycling to provide an economic incentive to decommission additional roads by reducing transport distance and aggregate procurement costs for other actively used roads. Decommissioning additional roads may, in turn, result in improved aquatic habitat. We present real-world examples of aggregate recycling and discuss the advantages of doing so. Further, we present mixed integer formulations to determine optimal levels of aggregate recycling under economic and environmental objectives. Tested on an example road network, incorporation of aggregate recycling demonstrates substantial cost-savings relative to a baseline scenario without recycling, increasing the likelihood of road decommissioning and reduced habitat degradation. We find that aggregate recycling can result in up to 24% in cost savings (economic objective) and up to 890% in additional length of roads decommissioned (environmental objective). PMID:18481140

  13. RESULTS OF IONSIV® IE-95 STUDIES FOR THE REMOVAL OF RADIOACTIVE CESIUM FROM K-EAST BASIN SPENT NUCLEAR FUEL POOL DURING DECOMMISSIONING ACTIVITIES

    SciTech Connect

    DUNCAN JB; BURKE SP

    2008-07-07

    This report delineates the results obtained from laboratory testing of IONISIV{reg_sign} IE-95 to determine the efficacy of the zeolite for the removal of radioactive cesium from the KE Basin water prior to transport to the Effluent Treatment Facility, as described in RPP-PLAN-36158, IONSIV{reg_sign} IE-95 Studies for the removal of Radioactive Cesium from KE Basin Spent Nuclear Fuel Pool during Decommissioning Activities. The spent nuclear fuel was removed from KE Basin and the remaining sludge was layered with a grout mixture consisting of 26% Lehigh Type I/II portland cement and 74% Boral Mohave type F fly ash with a water-to-cement ratio of 0.43. The first grout pour was added to the basin floor to a depth of approximately 14 in. covering an area of 12,000 square feet. A grout layer was also added to the sludge containers located in the attached Weasel and Technical View pits.

  14. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    SciTech Connect

    Haffner, D.R.; Villelgas, A.J.

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  15. Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

    SciTech Connect

    Dettmers, Dana Lee; Eide, Steven Arvid

    2002-10-01

    An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.

  16. 77 FR 28669 - Pipeline Safety: Information Collection Activities, Excess Flow Valve Census

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-15

    ..., Excess Flow Valve Census AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT..., PHMSA invites comments on a new one-time Information Collection (IC) on Excess Flow Valves (EFVs). PHMSA... Collection on Excess Flow Valves.'' In 1996, PHMSA's predecessor agency, the Research and Special...

  17. 77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-21

    .... SUMMARY: On April 13, 2012, (77 FR 22387) in accordance with the Paperwork Reduction Act of 1995, the... PHMSA published a notice in the Federal Register on April 13, 2012, (77 FR 22387) titled ``Pipeline... proposed revisions were referenced in a Federal Register notice published on April 13, 2012, (77 FR...

  18. Sodium Reactor Experiment decommissioning. Final report

    SciTech Connect

    Carroll, J.W.; Conners, C.C.; Harris, J.M.; Marzec, J.M.; Ureda, B.F.

    1983-08-15

    The Sodium Reactor Experiment (SRE) located at the Rockwell International Field Laboratories northwest of Los Angeles was developed to demonstrate a sodium-cooled, graphite-moderated reactor for civilian use. The reactor reached full power in May 1958 and provided 37 GWh to the Southern California Edison Company grid before it was shut down in 1967. Decommissioning of the SRE began in 1974 with the objective of removing all significant radioactivity from the site and releasing the facility for unrestricted use. Planning documentation was prepared to describe in detail the equipment and techniques development and the decommissioning work scope. A plasma-arc manipulator was developed for remotely dissecting the highly radioactive reactor vessels. Other important developments included techniques for using explosives to cut reactor vessel internal piping, clamps, and brackets; decontaminating porous concrete surfaces; and disposing of massive equipment and structures. The documentation defined the decommissioning in an SRE dismantling plan, in activity requirements for elements of the decommissioning work scope, and in detailed procedures for each major task.

  19. Preservation and Implementation of Decommissioning Lessons Learned in the United States Nuclear Regulatory Commission

    SciTech Connect

    Rodriguez, Rafael L.

    2008-01-15

    Over the past several years, the United States Nuclear Regulatory Commission (NRC) has actively worked to capture and preserve lessons learned from the decommissioning of nuclear facilities. More recently, NRC has involved industry groups, the Organization of Agreement States (OAS), and the Department of Energy (DOE) in the effort to develop approaches to capture, preserve and disseminate decommissioning lessons learned. This paper discusses the accomplishments of the working group, some lessons learned by the NRC in the recent past, and how NRC will incorporate these lessons learned into its regulatory framework. This should help ensure that the design and operation of current and future nuclear facilities will result in less environmental impact and more efficient decommissioning. In summary, the NRC will continue capturing today's experience in decommissioning so that future facilities can take advantage of lessons learned from today's decommissioning projects. NRC, both individually and collectively with industry groups, OAS, and DOE, is aggressively working on the preservation and implementation of decommissioning lessons learned. The joint effort has helped to ensure the lessons from the whole spectrum of decommissioning facilities (i.e., reactor, fuel cycle, and material facilities) are better understood, thus maximizing the amount of knowledge and best practices obtained from decommissioning activities. Anticipated regulatory activities at the NRC will make sure that the knowledge gained from today's decommissioning projects is preserved and implemented to benefit the nuclear facilities that will decommission in the future.

  20. ORNL decontamination and decommissioning program

    SciTech Connect

    Bell, J. P.

    1980-01-01

    A program has been initiated at ORNL to decontaminate and decommission surplus or abandoned nuclear facilities. Program planning and technical studies have been performed by UCC-ND Engineering. A feasibility study for decommissioning the Metal Recovery Facility, a fuel reprocessing pilot plant, has been completed.

  1. Remote Decommissioning Experiences at Sellafield

    SciTech Connect

    Brownridge, M.

    2006-07-01

    British Nuclear Group has demonstrated through delivery of significant decommissioning projects the ability to effectively deploy innovative remote decommissioning technologies and deliver cost effective solutions. This has been achieved through deployment and development of off-the-shelf technologies and design of bespoke equipment. For example, the worlds first fully remotely operated Brokk was successfully deployed to enable fully remote dismantling, packaging and export of waste during the decommissioning of a pilot reprocessing facility. British Nuclear Group has also successfully implemented remote decommissioning systems to enable the decommissioning of significant challenges, including dismantling of a Caesium Extraction Facility, Windscale Pile Chimney and retrieval of Plutonium Contaminated Material (PCM) from storage cells. The challenge for the future is to continue to innovate through utilization of the supply chain and deploy off-the-shelf technologies which have been demonstrated in other industry sectors, thus reducing implementation schedules, cost and maintenance. (authors)

  2. Progress in Decommissioning the Humboldt Bay Power Plant - 13604

    SciTech Connect

    Rod, Kerry; Shelanskey, Steven K.; Kristofzski, John

    2013-07-01

    Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) to Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major work scopes

  3. Comparison of measured and calculated concrete and rebar specific activity during decommissioning of the Dalhousie SLOWPOKE-2 reactor.

    PubMed

    Smith, Philip G; Everall, Dave; Ariani, Imelda; Tsang, Kwok

    2013-07-01

    Following the defuelling and dismantling of the Dalhousie University SLOWPOKE-2 Reactor (DUSR) in 2011, the reactor pool concrete and rebar were sampled to support the unconditional free release of the material such that the facility could be classified for unrestricted use. A detailed MCNP5 model of the critical core assembly was simulated to calculate the thermal, intermediate and fast neutron flux profile below the reactor pool floor. The neutron fluxes were used to calculate the specific activity of significant radionuclides in the concrete and rebar. The calculated specific activity and consequently the calculated neutron fluxes were validated at a number of sample locations. The calculated concrete and rebar specific activity were found to be in good agreement with the measured specific activity at the sample locations. The unrestricted use of the facility was granted through the approval of the licence to abandon the facility in August 2011.

  4. Comparison of measured and calculated concrete and rebar specific activity during decommissioning of the Dalhousie SLOWPOKE-2 reactor.

    PubMed

    Smith, Philip G; Everall, Dave; Ariani, Imelda; Tsang, Kwok

    2013-07-01

    Following the defuelling and dismantling of the Dalhousie University SLOWPOKE-2 Reactor (DUSR) in 2011, the reactor pool concrete and rebar were sampled to support the unconditional free release of the material such that the facility could be classified for unrestricted use. A detailed MCNP5 model of the critical core assembly was simulated to calculate the thermal, intermediate and fast neutron flux profile below the reactor pool floor. The neutron fluxes were used to calculate the specific activity of significant radionuclides in the concrete and rebar. The calculated specific activity and consequently the calculated neutron fluxes were validated at a number of sample locations. The calculated concrete and rebar specific activity were found to be in good agreement with the measured specific activity at the sample locations. The unrestricted use of the facility was granted through the approval of the licence to abandon the facility in August 2011. PMID:23658212

  5. Preliminary decommissioning study reports. Volume 5, Molten Salt Reactor Experiment

    SciTech Connect

    Peretz, F.J.

    1984-09-01

    The Molten Salt Reactor Experiment (MSRE) is one of approximately 76 facilities currently managed by the ORNL Surplus Facilities Management Program (SFMP). This program, as part of the DOE national SFMP, is responsible for the maintenance and surveillance and the final decommissioning of radioactively-contaminated surplus ORNL facilities. A long range planning effort is being conducted that will outline the scope and objectives of the ORNL program and establish decommissioning priorities based on health and safety concerns, budget constraints, and other programmatic constraints. In support of this SFMP planning activity, preliminary engineering assessments are being conducted for each of the ORNL surplus facilities currently managed under the program. These efforts, in general, are designed to: (1) provide an initial assessment of the potential decommissioning alternatives; (2) choose a preferred alternative and provide a justification for that choice, and (3) provide a preliminary description of the decommissioning plan, including cost and schedule estimates. Because of several issues which cannot be evaluated quantitatively at this time, this report on the MSRE does not select a ``most probable decommissioning mode`` but rather discusses the issues and representative alternatives for disposal of the MSRE fuel salts and decommissioning of the facility. A budget and schedule representative of the types of activities likely to be required is also suggested for preliminary use in the SFMP Long Range Plan.

  6. Offshore-platform decommissioning perceptions change

    SciTech Connect

    Twachtman, R.

    1997-12-08

    The oil and gas industry has seen a change in the perceptions about decommissioning offshore facilities. Now, decommissioning projects are being planned ahead of actual field development, and new concepts derived during decommissioning often are used to provide feedback for new development projects. The current trends and concepts applicable to decommissioning can be summarized as: advanced planning; engineered solutions; research and development; reuse; expanded use of offshore reefs; and deepwater disposal. Planning the platform decommissioning ahead of time (at least 2 years before production ceases) is key to a safe, environmentally conscious, and efficient decommissioning project. The paper discusses decommissioning projects, engineered solutions, research and development; reuse of platforms, and deepwater disposal.

  7. A Plutonium Finishing Plant Model for the Cercla Removal Action and Decommissioning Construction Final Report

    SciTech Connect

    Hopkins, A.

    2008-07-01

    The joint policy between the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE) for decommissioning buildings at DOE facilities documents an agreement between the agencies to perform decommissioning activities including demolition under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). The use of removal actions for decommissioning integrates EPA oversight authority, DOE lead agency responsibility, and state authority for decommissioning activities. Once removal actions have been performed under CERCLA, a construction completion report is required to document the completion of the required action. Additionally, a decommissioning report is required under DOE guidance. No direct guidance was found for documenting completion of decommissioning activities and preparing a final report that satisfies the CERCLA requirements and the DOE requirements for decommissioning. Additional guidance was needed for the documentation of construction completion under CERCLA for D and D projects undertaken under the joint policy that addresses the requirements of both agencies. A model for the construction completion report was developed to document construction completion for CERCLA D and D activities performed under the joint EPA/DOE policy at the Plutonium Finishing Plant (PFP). The model documentation report developed at PFP integrates the DOE requirements for establishing decommissioning end-points, documenting end-point completion and preparing a final decommissioning report with the CERCLA requirements to document completion of the action identified in the Action Memorandum (AM). The model includes the required information on health and safety, data management, cost and schedule and end-points completion. (authors)

  8. Decommissioning of the Tokamak Fusion Test Reactor

    SciTech Connect

    E. Perry; J. Chrzanowski; C. Gentile; R. Parsells; K. Rule; R. Strykowsky; M. Viola

    2003-10-28

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D&D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D&D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D&D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget.

  9. Draft principles, policy, and acceptance criteria for decommissioning of U.S. Department of Energy contaminated surplus facilities and summary of international decommissioning programs

    SciTech Connect

    Singh, B.K. |; Gillette, J.; Jackson, J.

    1994-12-01

    Decommissioning activities enable the DOE to reuse all or part of a facility for future activities and reduce hazards to the general public and any future work force. The DOE Office of Environment, Health and Safety has prepared this document, which consists of decommissioning principles and acceptance criteria, in an attempt to establish a policy that is in agreement with the NRC policy. The purpose of this document is to assist individuals involved with decommissioning activities in determining their specific responsibilities as identified in Draft DOE Order 5820.DDD, ``Decommissioning of US Department of Energy Contaminated Surplus Facilities`` (Appendix A). This document is not intended to provide specific decommissioning methodology. The policies and principles of several international decommissioning programs are also summarized. These programs are from the IAEA, the NRC, and several foreign countries expecting to decommission nuclear facilities. They are included here to demonstrate the different policies that are to be followed throughout the world and to allow the reader to become familiar with the state of the art for environment, safety, and health (ES and H) aspects of nuclear decommissioning.

  10. Evaluation of nuclear facility decommissioning projects: summary report. Plum Brook Reactor Facility

    SciTech Connect

    Doerge, D.H.; Miller, R.L.

    1984-02-01

    This document summarizes information concerning the decommissioning of the Plum Brook Reactor Facility, which was placed in a Nuclear Regulatory Commission (NRC) approved safe storage configuration. The data were placed in a computerized information retrieval/manipulation system which permits future utilization of this information in decommissioning of similar facilities. The information is presented both in computer output form and a manually assembled summarization. Complete cost data were not readily available and decommissioning activities did not in all cases conform with current criteria for the SAFSTOR decommissioning mode, therefore no cost comparisons were made.

  11. HEU Measurements of Holdup and Recovered Residue in the Deactivation and Decommissioning Activities of the 321-M Reactor Fuel Fabrication Facility at the Savannah River Site

    SciTech Connect

    DEWBERRY, RAYMOND; SALAYMEH, SALEEM R.; CASELLA, VITO R.; MOORE, FRANK S.

    2005-03-11

    This paper contains a summary of the holdup and material control and accountability (MC&A) assays conducted for the determination of highly enriched uranium (HEU) in the deactivation and decommissioning (D&D) of Building 321-M at the Savannah River Site (SRS). The 321-M facility was the Reactor Fuel Fabrication Facility at SRS and was used to fabricate HEU fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the SRS production reactors. The facility operated for more than 35 years. During this time thousands of uranium-aluminum-alloy (U-Al) production reactor fuel tubes were produced. After the facility ceased operations in 1995, all of the easily accessible U-Al was removed from the building, and only residual amounts remained. The bulk of this residue was located in the equipment that generated and handled small U-Al particles and in the exhaust systems for this equipment (e.g., Chip compactor, casting furnaces, log saw, lathes A & B, cyclone separator, Freon{trademark} cart, riser crusher, ...etc). The D&D project is likely to represent an important example for D&D activities across SRS and across the Department of Energy weapons complex. The Savannah River National Laboratory was tasked to conduct holdup assays to quantify the amount of HEU on all components removed from the facility prior to placing in solid waste containers. The U-235 holdup in any single component of process equipment must not exceed 50 g in order to meet the container limit. This limit was imposed to meet criticality requirements of the low level solid waste storage vaults. Thus the holdup measurements were used as guidance to determine if further decontamination of equipment was needed to ensure that the quantity of U-235 did not exceed the 50 g limit and to ensure that the waste met the Waste Acceptance Criteria (WAC) of the solid waste storage vaults. Since HEU is an accountable nuclear material, the holdup assays and assays of recovered

  12. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    SciTech Connect

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a

  13. Slurry pipelines

    SciTech Connect

    Wasp, E.J.

    1983-11-01

    Slurry pipelines are now transporting metal ores and coal/water suspensions. Their greatest potential is for transporting coal from Western states to power stations in other parts of the country. The physics of slurry transport encompases the principles of fluid dynamics and hydrostatics that were studied by Archimedes, but commercial slurry systems date only since World War II. An overview of their development covers policy debates and technological problems associated with existing and proposed pipeline projects. The author examines the tradeoffs of low sulfur content versus longer distances for transport, and describes the process of preparing coal slurries. 7 figures.

  14. Recession curbs gas pipeline construction costs

    SciTech Connect

    Morgan, J.M.

    1983-01-24

    This paper shows how after 5 yrs. of inflation, gas pipeline construction costs have finally felt the effects of a severe building recession. First quarter (1982) construction activity, compressor equipment and drive units, and high-pressure gas-station piping are discussed. Graphs of OGJ-Morgan composite gas pipeline cost, and gas pipeline cost component indexes are presented.

  15. 30 CFR 585.907 - How will BOEM process my decommissioning application?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Environmental and Safety Management, Inspections, and Facility Assessments for Activities Conducted Under SAPs... your decommissioning application with the decommissioning general concept in your approved SAP, COP, or... revise your SAP, COP, or GAP, and BOEM will begin the appropriate NEPA analysis and other...

  16. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect

    Austin, W.; Brinkley, D.

    2011-10-13

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment

  17. Pipeline Expansions

    EIA Publications

    1999-01-01

    This appendix examines the nature and type of proposed pipeline projects announced or approved for construction during the next several years in the United States. It also includes those projects in Canada and Mexico that tie-in with the U.S. markets or projects.

  18. Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part A, Decontamination and Decommissioning

    SciTech Connect

    Not Available

    1993-09-01

    This report documents activities of decontamination and decommissioning at ORNL. Topics discussed include general problems, waste types, containment, robotics automation and decontamination processes.

  19. Decommissioning of surplus facilities at Los Alamos National Laboratory

    SciTech Connect

    Stout, D.S.

    1995-03-01

    Decommissioning Buildings 3 and 4 South at Technical Area 21, Los Alamos National Laboratory, involves the decontamination, dismantlement, and demolition of two enriched-uranium processing buildings containing process equipment and ductwork holdup. The Laboratory has adopted two successful management strategies to implement this project: Rather than characterize an entire site, upfront, investigators use the ``observational approach,`` in which they collect only enough data to begin decommissioning activities and then determine appropriate procedures for further characterization as the work progresses. Project leaders augment work packages with task hazard analyses to fully define specific tasks and inform workers of hazards; all daily work activities are governed by specific work procedures and hazard analyses.

  20. 77 FR 41107 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-12

    ... Decommissioning Planning Rule (DPR) (June 17, 2011, 76 FR 33512). The DPR applies to the operational phase of a..., ``Decommissioning Planning During Operations'' (December 13, 2011, 76 FR 77431). The NRC received more than 100...; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 Decommissioning Planning...

  1. The Chernobyl NPP decommissioning: Current status and alternatives

    SciTech Connect

    Mikolaitchouk, H.; Steinberg, N.

    1996-08-01

    After the Chernobyl accident of April 26, 1986, many contradictory decisions were taken concerning the Chernobyl nuclear power plant (NPP) future. The principal source of contradictions was a deadline for a final shutdown of the Chernobyl NPP units. Alterations in a political and socioeconomic environment resulted in the latest decision of the Ukrainian Authorities about 2000 as a deadline for a beginning of the Chernobyl NPP decommissioning. The date seems a sound compromise among the parties concerned. However, in order to meet the data a lot of work should be done. First of all, a decommissioning strategy has to be established. The problem is complicated due to both site-specific aspects and an absence of proven solutions for the RBMK-type reactor decommissioning. In the paper the problem of decommissioning option selection is considered taking into account an influence of the following factors: relevant legislative and regulatory requirements; resources required to carry out decommissioning (man-power, equipment, technologies, waste management infrastructure, etc.); radiological and physical status of the plant, including structural integrity and predictable age and weather effects; impact of planned activities at the destroyed unit 4 and within the 30-km exclusion zone of the Chernobyl NPP; planed use of the site; socio-economic considerations.

  2. Parallel pipelining

    SciTech Connect

    Joseph, D.D.; Bai, R.; Liao, T.Y.; Huang, A.; Hu, H.H.

    1995-09-01

    In this paper the authors introduce the idea of parallel pipelining for water lubricated transportation of oil (or other viscous material). A parallel system can have major advantages over a single pipe with respect to the cost of maintenance and continuous operation of the system, to the pressure gradients required to restart a stopped system and to the reduction and even elimination of the fouling of pipe walls in continuous operation. The authors show that the action of capillarity in small pipes is more favorable for restart than in large pipes. In a parallel pipeline system, they estimate the number of small pipes needed to deliver the same oil flux as in one larger pipe as N = (R/r){sup {alpha}}, where r and R are the radii of the small and large pipes, respectively, and {alpha} = 4 or 19/7 when the lubricating water flow is laminar or turbulent.

  3. 76 FR 35511 - Decommissioning Planning

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-17

    ... regulations in 1997 as Subpart E of 10 CFR part 20 (62 FR 39058; July 21, 1997). This set of requirements is... the January 27, 1988 (53 FR 24018), rule on planning for decommissioning require licensees to provide... contamination and the amount of funds set aside and expended on cleanup. (62 FR 39082; July 21, 1997)....

  4. FAMS DECOMMISSIONING END-STATE ALTERNATIVE EVALUATION

    SciTech Connect

    Grimm, B; Stephen Chostner, S; Brenda Green, B

    2006-05-25

    Nuclear Material Management (NMM) completed a comprehensive study at the request of the Department of Energy Savannah River Operations Office (DOE-SR) in 2004 (Reference 11.1). The study evaluated the feasibility of removal and/or mitigation of the Pu-238 source term in the F-Area Material Storage (FAMS) facility during on-going material storage operations. The study recommended different options to remove and/or mitigate the Pu-238 source term depending on its location within the facility. During April 2005, the Department of Energy (DOE) sent a letter of direction (LOD) to Washington Savannah River Company (WSRC) directing WSRC to implement a new program direction that would enable an accelerated shutdown and decommissioning of FAMS (Reference 11.2). Further direction in the LOD stated that effective December 1, 2006 the facility will be transitioned to begin deactivation and decommissioning (D&D) activities. To implement the LOD, Site D&D (SDD) and DOE agreed the planning end-state would be demolition of the FAMS structure to the building slab. SDD developed the D&D strategy, preliminary cost and schedule, and issued the deactivation project plan in December 2005 (Reference 11.3). Due to concerns and questions regarding the FAMS planning end-state and in support of the project's Critical Decision 1, an alternative study was performed to evaluate the various decommissioning end-states and the methods by which those end-states are achieved. This report documents the results of the alternative evaluation which was performed in a structured decision-making process as outlined in the E7 Manual, Procedure 2.15, ''Alternative Studies'' (Reference 11.4).

  5. 78 FR 77484 - Extension of Agency Information Collection Activity Under OMB Review: Pipeline System Operator...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-23

    ... period soliciting comments, of the following collection of information on August 16, 2013, 78 FR 50077... security, it is important for TSA to have contact information for company security managers and knowledge... SECURITY Transportation Security Administration Extension of Agency Information Collection Activity...

  6. The inverse electroencephalography pipeline

    NASA Astrophysics Data System (ADS)

    Weinstein, David Michael

    The inverse electroencephalography (EEG) problem is defined as determining which regions of the brain are active based on remote measurements recorded with scalp EEG electrodes. An accurate solution to this problem would benefit both fundamental neuroscience research and clinical neuroscience applications. However, constructing accurate patient-specific inverse EEG solutions requires complex modeling, simulation, and visualization algorithms, and to date only a few systems have been developed that provide such capabilities. In this dissertation, a computational system for generating and investigating patient-specific inverse EEG solutions is introduced, and the requirements for each stage of this Inverse EEG Pipeline are defined and discussed. While the requirements of many of the stages are satisfied with existing algorithms, others have motivated research into novel modeling and simulation methods. The principal technical results of this work include novel surface-based volume modeling techniques, an efficient construction for the EEG lead field, and the Open Source release of the Inverse EEG Pipeline software for use by the bioelectric field research community. In this work, the Inverse EEG Pipeline is applied to three research problems in neurology: comparing focal and distributed source imaging algorithms; separating measurements into independent activation components for multifocal epilepsy; and localizing the cortical activity that produces the P300 effect in schizophrenia.

  7. Variability in automatic activation as an unobtrusive measure of racial attitudes: a bona fide pipeline?

    PubMed

    Fazio, R H; Jackson, J R; Dunton, B C; Williams, C J

    1995-12-01

    The research examines an unobtrusive measure of racial attitudes based on the evaluations that are automatically activated from memory on the presentation of Black versus White faces. Study 1, which concerned the technique's validity, obtained different attitude estimates for Black and White participants and also revealed that the variability among White participants was predictive of other race-related judgments and behavior. Study 2 concerned the lack of correspondence between the unobtrusive estimates and Modern Racism Scale (MRS) scores. The reactivity of the MRS was demonstrated in Study 3. Study 4 observed an interaction between the unobtrusive estimates and an individual difference in motivation to control prejudiced reactions when predicting MRS scores. The theoretical implications of the findings for consideration of automatic and controlled components of racial prejudice are discussed, as is the status of the MRS.

  8. Pipeline issues

    NASA Technical Reports Server (NTRS)

    Eisley, Joe T.

    1990-01-01

    The declining pool of graduates, the lack of rigorous preparation in science and mathematics, and the declining interest in science and engineering careers at the precollege level promises a shortage of technically educated personnel at the college level for industry, government, and the universities in the next several decades. The educational process, which starts out with a large number of students at the elementary level, but with an ever smaller number preparing for science and engineering at each more advanced educational level, is in a state of crisis. These pipeline issues, so called because the educational process is likened to a series of ever smaller constrictions in a pipe, were examined in a workshop at the Space Grant Conference and a summary of the presentations and the results of the discussion, and the conclusions of the workshop participants are reported.

  9. Geothermal pipeline

    SciTech Connect

    1997-08-01

    The Geothermal Pipeline is a progress and development update from the Geothermal Progress Monitor and includes brief descriptions of various geothermal projects around the world. The following topics are covered: The retirement of Geo-Heat Center Director Paul Lienau, announcement of two upcoming geothermal meetings, and a proposed geothermal power plant project in the Medicine Lake/Glass Mountain area of California. Also included is an article about the Bonneville Power Administration`s settlements with two California companies who had agreed to build geothermal power plants on the federal agency`s behalf, geothermal space heating projects and use of geothermal energy for raising red crayfish in Oregon, and some updates on geothermal projects in Minnesota, Pennsylvania, and China.

  10. Decontamination, decommissioning, and vendor advertorial issue, 2005

    SciTech Connect

    Agnihotri, Newal

    2005-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major interviews, articles and reports in this issue include: Increasing momentum, by Gary Taylor, Entergy Nuclear, Inc.; An acceptable investment, by Tom Chrisopher, Areva, Inc.; Fuel recycling for the U.S. and abroad, by Philippe Knoche, Areva, France; We're bullish on nuclear power, by Dan R. Keuter, Entergy Nuclear, Inc.; Ten key actions for decommissioning, by Lawrence E. Boing, Argonne National Laboratory; Safe, efficient and cost-effective decommissioning, by Dr. Claudio Pescatore and Torsten Eng, OECD Nuclear Energy Agency (NEA), France; and, Plant profile: SONGS decommissioning.

  11. Decommissioning of nuclear reactor fuel channels using laser technology

    NASA Astrophysics Data System (ADS)

    Panchenko, Vladislav Y.; Zabelin, Alexandre M.; Slepokon, Yu. I.; Ryahin, V. M.; Kuznetsov, P. P.; Panasyuk, V. F.; Korotchenko, A. V.; Kislov, V. S.; Loktev, S. V.

    2000-07-01

    Decommissioning of nuclear reactors using laser remote dismounting and welding was experimentally proved at a nuclear reactor of Kursk Nuclear Power Plant. The main reason of laser beam application in this case is the marked decrease of radioactive exposure of the service personnel. The use of a high-power laser beam provided for laser cutting and welding processes realization at a distance up to 35 m between the laser and the workstation placed behind a radiation shield. By application of laser cutting gas and dust contamination is ten-fold decreased. Some results of decommissioning application of a stationary laser workstation based upon a 5 kW fast-transverse-flow discharge CW CO2 laser TL-5M installed at a nuclear reactor site are presented. A special high-beam- quality model of the laser was developed to satisfy the needs of decommissioning. Laser cutting process was applied to decommissioning of fuel channels (FC) of RBMK-1000 reactor, after their extractor from the reactor active zone during the procedure of channels replacement.

  12. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    SciTech Connect

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  13. 30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources..., Inspections, and Facility Assessments for Activities Conducted Under SAPs, COPs and GAPs Decommissioning... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within...

  14. 30 CFR 285.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... facility subject to an Alternate Use RUE? 285.1018 Section 285.1018 Mineral Resources BUREAU OF OCEAN...- and Marine-Related Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1018 Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a)...

  15. 30 CFR 585.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... issued under 30 CFR part 250 will remain responsible for decommissioning obligations that accrued before... facility subject to an Alternate Use RUE? 585.1018 Section 585.1018 Mineral Resources BUREAU OF OCEAN... Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 585.1018 Who is...

  16. 30 CFR 585.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... issued under 30 CFR part 250 will remain responsible for decommissioning obligations that accrued before... facility subject to an Alternate Use RUE? 585.1018 Section 585.1018 Mineral Resources BUREAU OF OCEAN... Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 585.1018 Who is...

  17. 30 CFR 585.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... issued under 30 CFR part 250 will remain responsible for decommissioning obligations that accrued before... facility subject to an Alternate Use RUE? 585.1018 Section 585.1018 Mineral Resources BUREAU OF OCEAN... Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 585.1018 Who is...

  18. Asset Decommissioning Risk Metrics for Floating Structures in the Gulf of Mexico.

    PubMed

    Kaiser, Mark J

    2015-08-01

    Public companies in the United States are required to report standardized values of their proved reserves and asset retirement obligations on an annual basis. When compared, these two measures provide an aggregate indicator of corporate decommissioning risk but, because of their consolidated nature, cannot readily be decomposed at a more granular level. The purpose of this article is to introduce a decommissioning risk metric defined in terms of the ratio of the expected value of an asset's reserves to its expected cost of decommissioning. Asset decommissioning risk (ADR) is more difficult to compute than a consolidated corporate risk measure, but can be used to quantify the decommissioning risk of structures and to perform regional comparisons, and also provides market signals of future decommissioning activity. We formalize two risk metrics for decommissioning and apply the ADR metric to the deepwater Gulf of Mexico (GOM) floater inventory. Deepwater oil and gas structures are expensive to construct, and at the end of their useful life, will be expensive to decommission. The value of proved reserves for the 42 floating structures in the GOM circa January 2013 is estimated to range between $37 and $80 billion for future oil prices between 60 and 120 $/bbl, which is about 10 to 20 times greater than the estimated $4.3 billion to decommission the inventory. Eni's Allegheny and MC Offshore's Jolliet tension leg platforms have ADR metrics less than one and are approaching the end of their useful life. Application of the proposed metrics in the regulatory review of supplemental bonding requirements in the U.S. Outer Continental Shelf is suggested to complement the current suite of financial metrics employed.

  19. Asset Decommissioning Risk Metrics for Floating Structures in the Gulf of Mexico.

    PubMed

    Kaiser, Mark J

    2015-08-01

    Public companies in the United States are required to report standardized values of their proved reserves and asset retirement obligations on an annual basis. When compared, these two measures provide an aggregate indicator of corporate decommissioning risk but, because of their consolidated nature, cannot readily be decomposed at a more granular level. The purpose of this article is to introduce a decommissioning risk metric defined in terms of the ratio of the expected value of an asset's reserves to its expected cost of decommissioning. Asset decommissioning risk (ADR) is more difficult to compute than a consolidated corporate risk measure, but can be used to quantify the decommissioning risk of structures and to perform regional comparisons, and also provides market signals of future decommissioning activity. We formalize two risk metrics for decommissioning and apply the ADR metric to the deepwater Gulf of Mexico (GOM) floater inventory. Deepwater oil and gas structures are expensive to construct, and at the end of their useful life, will be expensive to decommission. The value of proved reserves for the 42 floating structures in the GOM circa January 2013 is estimated to range between $37 and $80 billion for future oil prices between 60 and 120 $/bbl, which is about 10 to 20 times greater than the estimated $4.3 billion to decommission the inventory. Eni's Allegheny and MC Offshore's Jolliet tension leg platforms have ADR metrics less than one and are approaching the end of their useful life. Application of the proposed metrics in the regulatory review of supplemental bonding requirements in the U.S. Outer Continental Shelf is suggested to complement the current suite of financial metrics employed. PMID:25692712

  20. Decommissioning of U.S. uranium production facilities

    SciTech Connect

    Not Available

    1995-02-01

    From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

  1. Education in nuclear decommissioning in the north of Scotland

    SciTech Connect

    Catlow, F.; Reeves, G.M.

    2007-07-01

    This paper describes the work covered and experience gained in the first two years of operation of DERC, a Centre for Decommissioning and Environmental Remediation in the Highlands of Scotland. The Centre is a unique development which was set up to teach nuclear decommissioning as a separate discipline, address the problem of a declining skills base in the field of nuclear technologies and to take advantage of the unique and exceptional innovative, technical and research opportunities offered through the decommissioning of Britain's fast reactor site at Dounreay. The Centre is an offshoot from North Highland College which is a member of UHI, the University in embryo of the Highlands and Islands. The Centre currently supports ten PhD students completing various diverse projects mainly in the field of nuclear environmental remediation. In addition there area number of full and part time MSc students who participate in NTEC (Nuclear Technology Education Consortium) a consortium of British Universities set up specifically to engender interest and skills in nuclear technology at postgraduate level. At undergraduate level, courses are offered in Nuclear Decommissioning and related subjects as part of Electrical and Mechanical degree courses. In addition to our relationship with the United Kingdom Atomic Energy Authority (UKAEA) the Dounreay site licensee, we have links with Rolls-Royce and the Ministry of Defence who also share the Dounreay site and with other stakeholders such as, the UK regulator (HSE/NII), the Scottish Environmental Protection Agency (SEPA), local and international contractors and we liaise with the newly formed Nuclear Decommissioning Authority (NDA), who provide some sponsorship and support. We possess our own equipment and laboratories for taking and analysing soil samples and for conducting environmental surveys. Recently we commissioned an aerial survey of contamination in the locality from natural sources, other background levels such as

  2. Rancho Seco--Decommissioning Update

    SciTech Connect

    Newey, J. M.; Ronningen, E. T.; Snyder, M. W.

    2003-02-26

    The Rancho Seco Nuclear Generating Station ceased operation in June of 1989 and entered an extended period of SAFSTOR to allow funds to accumulate for dismantlement. Incremental dismantlement was begun in 1997 of steam systems and based on the successful completion of work, the Sacramento Municipal Utility District (SMUD) board of directors approved full decommissioning in July 1999. A schedule has been developed for completion of decommissioning by 2008, allowing decommissioning funds to accumulate until they are needed. Systems removal began in the Auxiliary Building in October of 1999 and in the Reactor Building in January of 2000. Systems dismantlement continues in the Reactor Building and should be completed by the end of 2003. System removal is near completion in the Auxiliary Building with removal of the final liquid waste tanks in progress. The spent fuel has been moved to dry storage in an onsite ISFSI, with completion on August 21, 2002. The spent fuel racks are currently being removed from the pool, packaged and shipped, and then the pool will be cleaned. Also in the last year the reactor coolant pumps and primary piping were removed and shipped. Characterization and planning work for the reactor vessel and internals is also in progress with various cut-up and/or disposal options being evaluated. In the year ahead the remaining systems in the Reactor Building will be removed, packaged and sent for disposal, including the pressurizer. Work will be started on embedded and underground piping and the large outdoor tanks. Building survey and decontamination will begin. RFP's for removal of the vessel and internals and the steam generators are planned to fix the cost of those components. If the costs are consistent with current estimates the work will go forward. If they are not, hardened SAFSTOR/entombment may be considered.

  3. 76 FR 3837 - Nuclear Decommissioning Funds; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-21

    ... 23, 2010 (75 FR 80697) relating to deductions for contributions to trusts maintained for decommissioning nuclear power plants. DATES: This correction is effective on January 21, 2011, and is applicable... Internal Revenue Service 26 CFR Part 1 RIN 1545-BF08 Nuclear Decommissioning Funds; Correction...

  4. Decontamination and decommissioning surveillance and maintenance report for FY 1991

    SciTech Connect

    Gunter, David B.; Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01

    The Decontamination and Decommissioning (D D) Program has three distinct phases: (1) surveillance and maintenance (S M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D D is devoted to S M at each of the sites. Our S M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  5. 75 FR 13342 - Pipeline Safety: Workshop on Distribution Pipeline Construction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-19

    ... Statement in the Federal Register published April 11, 2000 (65 FR 19477). Information on Services for... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Workshop on Distribution Pipeline Construction AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice...

  6. The First Decommissioning of a Fusion Reactor Fueled by Deuterium-Tritium

    SciTech Connect

    Charles A. Gentile; Erik Perry; Keith Rule; Michael Williams; Robert Parsells; Michael Viola; James Chrzanowski

    2003-10-28

    The Tokamak Fusion Test Reactor (TFTR) at the Plasma Physics Laboratory of Princeton University (PPPL) was the first fusion reactor fueled by a mixture of deuterium and tritium (D-T) to be decommissioned in the world. The decommissioning was performed over a period of three years and was completed safely, on schedule, and under budget. Provided is an overview of the project and detail of various factors which led to the success of the project. Discussion will cover management of the project, engineering planning before the project started and during the field work as it was being performed, training of workers in the field, the novel adaptation of tools from other industry, and the development of an innovative process for the use of diamond wire to segment the activated/contaminated vacuum vessel. The success of the TFTR decommissioning provides a viable model for the decommissioning of D-T burning fusion devices in the future.

  7. Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada

    SciTech Connect

    Kenny, Stephen

    2008-01-15

    Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development of a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one hundred

  8. Reducing environmental risk associated with laboratory decommissioning and property transfer.

    PubMed

    Dufault, R; Abelquist, E; Crooks, S; Demers, D; DiBerardinis, L; Franklin, T; Horowitz, M; Petullo, C; Sturchio, G

    2000-12-01

    The need for more or less space is a common laboratory problem. Solutions may include renovating existing space, leaving or demolishing old space, or acquiring new space or property for building. All of these options carry potential environmental risk. Such risk can be the result of activities related to the laboratory facility or property (e.g., asbestos, underground storage tanks, lead paint), or the research associated with it (e.g., radioactive, microbiological, and chemical contamination). Regardless of the option chosen to solve the space problem, the potential environmental risk must be mitigated and the laboratory space and/or property must be decommissioned or rendered safe prior to any renovation, demolition, or property transfer activities. Not mitigating the environmental risk through a decommissioning process can incur significant financial liability for any costs associated with future decommissioning cleanup activities. Out of necessity, a functioning system, environmental due diligence auditing, has evolved over time to assess environmental risk and reduce associated financial liability. This system involves a 4-phase approach to identify, document, manage, and clean up areas of environmental concern or liability, including contamination. Environmental due diligence auditing includes a) historical site assessment, b) characterization assessment, c) remedial effort and d) final status survey. General practice standards from the American Society for Testing and Materials are available for conducting the first two phases. However, standards have not yet been developed for conducting the third and final phases of the environmental due diligence auditing process. Individuals involved in laboratory decommissioning work in the biomedical research industry consider this a key weakness.

  9. Reducing environmental risk associated with laboratory decommissioning and property transfer.

    PubMed Central

    Dufault, R; Abelquist, E; Crooks, S; Demers, D; DiBerardinis, L; Franklin, T; Horowitz, M; Petullo, C; Sturchio, G

    2000-01-01

    The need for more or less space is a common laboratory problem. Solutions may include renovating existing space, leaving or demolishing old space, or acquiring new space or property for building. All of these options carry potential environmental risk. Such risk can be the result of activities related to the laboratory facility or property (e.g., asbestos, underground storage tanks, lead paint), or the research associated with it (e.g., radioactive, microbiological, and chemical contamination). Regardless of the option chosen to solve the space problem, the potential environmental risk must be mitigated and the laboratory space and/or property must be decommissioned or rendered safe prior to any renovation, demolition, or property transfer activities. Not mitigating the environmental risk through a decommissioning process can incur significant financial liability for any costs associated with future decommissioning cleanup activities. Out of necessity, a functioning system, environmental due diligence auditing, has evolved over time to assess environmental risk and reduce associated financial liability. This system involves a 4-phase approach to identify, document, manage, and clean up areas of environmental concern or liability, including contamination. Environmental due diligence auditing includes a) historical site assessment, b) characterization assessment, c) remedial effort and d) final status survey. General practice standards from the American Society for Testing and Materials are available for conducting the first two phases. However, standards have not yet been developed for conducting the third and final phases of the environmental due diligence auditing process. Individuals involved in laboratory decommissioning work in the biomedical research industry consider this a key weakness. PMID:11121365

  10. TECHNOLOGY REQUIREMENTS FOR IN SITU DECOMMISSIONING WORKSHOP REPORT

    SciTech Connect

    Jannik, T.; Lee, P.; Gladden, J.; Langton, C.; Serrato, M.; Urland, C.; Reynolds, E.

    2009-06-30

    In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, the Department of Energy's (DOE) Office of Environmental Management (EM) is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-23) initiated efforts to identify the technical barriers and technology development needs for the optimal implementation of ISD. Savannah River National Laboratory (SRNL), as the EM Corporate Laboratory, conducted an ISD Technology Needs Workshop to identify the technology needs at DOE sites. The overall goal of the workshop was to gain a full understanding of the specific ISD technical challenges, the technologies available, and those needing development. The ISD Workshop was held December 9-10, 2008 in Aiken, SC. Experienced decommissioning operations personnel from Richland Operations Office (RL), Idaho National Laboratory (INL) and Savannah River Site (SRS) along with scientists and engineers specific expertise were assembled to identify incremental and 'game changing' solutions to ISD technology challenges. The workshop and follow-up activities yielded 14 technology needs statements and the recommendation that EM-23 prioritize and pursue the following specific technology development and deployment actions. For each action, the recommended technology acquisition mechanisms (competitive solicitation (CS) or direct funding (TCR)) are provided. Activities that are time critical for ISD projects, or require unique capabilities that reside in the DOE Laboratory system will be funded directly to those institutions. Activities that have longer lead times and where the private

  11. Pipeline accident statistics: Base to pipeline rehabilitation

    SciTech Connect

    Chis, T.

    1996-12-31

    The climate in which pipeline companies operate continues to change. Industry failures, related to public safety and environmental concerns, are now front page news. New and proposed regulations such as drug and alcohol testing of employees, instruments internal inspection and standardize oil spill response plans, are modifying the way pipeline companies operate. Paralleling these influences, the market place is also changing. Declining domestic production refinery closures and new specification for refined products are altering the pipe line distribution system. All of these changes are presenting new opportunities and many challenges. In 1995, when Conpet S.A. Ploiesti Formalized Pipeline Integrity Program, the reasons for the program were: What is the location to pipeline rehabilitation? What is failure probability? This paper reviews some aspects of the pipeline accident statistic to the Constanta Division of Conpet S.A. Ploiesti.

  12. TA-2 Water Boiler Reactor Decommissioning Project

    SciTech Connect

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m{sup 3} of low-level solid radioactive waste and 35 m{sup 3} of mixed waste. 15 refs., 25 figs., 3 tabs.

  13. Modelling of nuclear power plant decommissioning financing.

    PubMed

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. PMID:25979740

  14. Modelling of nuclear power plant decommissioning financing.

    PubMed

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW.

  15. Decommissioning the Research Nuclear Reactor Vvr-S Magurele - Analyze, Justification and Selection of Decommissioning Strategy

    NASA Astrophysics Data System (ADS)

    Dragusin, M.; Popa, V.; Boicu, A.; Tuca, C.; Iorga, I.; Mustata, C.

    2004-09-01

    The decommissioning of Research Nuclear Reactor VVR-S Magurele - Bucharest involves the removal of the radioactive and hazardous materials to permit the facility to be released without representing a further risk to human health and the environment [1-3]. A very important aspect of decommissioning is the analyze, justification and selection of the decommissioning strategy. Two strategies: DECON (Immediate Dismantling) and SAFSTOR (Safe Enclosure) are in study (see Table 1)... Note from Publisher: This article contains the abstract and references only.

  16. Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102

    SciTech Connect

    Y Onishi; KP Recknagle; BE Wells

    2000-08-09

    The authors evaluated how well two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102 (AZ-102) and confirmed the adequacy of a three-inch (7.6-cm) pipeline system to transfer the resulting mixed waste slurry to the AP Tank Farm and a planned waste treatment (vitrification) plant on the Hanford Site. Tank AZ-102 contains 854,000 gallons (3,230 m{sup 3}) of supernatant liquid and 95,000 gallons (360 m{sup 3}) of sludge made up of aging waste (or neutralized current acid waste). The study comprises three assessments: waste chemistry, pump jet mixing, and pipeline transfer. The waste chemical modeling assessment indicates that the sludge, consisting of the solids and interstitial solution, and the supernatant liquid are basically in an equilibrium condition. Thus, pump jet mixing would not cause much solids precipitation and dissolution, only 1.5% or less of the total AZ-102 sludge. The pump jet mixing modeling indicates that two 300-hp mixer pumps would mobilize up to about 23 ft (7.0 m) of the sludge nearest the pump but would not erode the waste within seven inches (0.18 m) of the tank bottom. This results in about half of the sludge being uniformly mixed in the tank and the other half being unmixed (not eroded) at the tank bottom.

  17. INTERNAL REPAIR OF PIPELINES

    SciTech Connect

    Bill Bruce; Nancy Porter; George Ritter; Matt Boring; Mark Lozev; Ian Harris; Bill Mohr; Dennis Harwig; Robin Gordon; Chris Neary; Mike Sullivan

    2005-07-20

    liners, indicating that this type of liner is only marginally effective at restoring the pressure containing capabilities of pipelines. Failure pressures for larger diameter pipe repaired with a semi-circular patch of carbon fiber-reinforced composite lines were also marginally greater than that of a pipe section with un-repaired simulated damage without a liner. These results indicate that fiber reinforced composite liners have the potential to increase the burst pressure of pipe sections with external damage Carbon fiber based liners are viewed as more promising than glass fiber based liners because of the potential for more closely matching the mechanical properties of steel. Pipe repaired with weld deposition failed at pressures lower than that of un-repaired pipe in both the virgin and damaged conditions, indicating that this repair technology is less effective at restoring the pressure containing capability of pipe than a carbon fiber-reinforced liner repair. Physical testing indicates that carbon fiber-reinforced liner repair is the most promising technology evaluated to-date. In lieu of a field installation on an abandoned pipeline, a preliminary nondestructive testing protocol is being developed to determine the success or failure of the fiber-reinforced liner pipeline repairs. Optimization and validation activities for carbon-fiber repair methods are ongoing.

  18. Crude oil treatment leads to shift of bacterial communities in soils from the deep active layer and upper permafrost along the China-Russia Crude Oil Pipeline route.

    PubMed

    Yang, Sizhong; Wen, Xi; Zhao, Liang; Shi, Yulan; Jin, Huijun

    2014-01-01

    The buried China-Russia Crude Oil Pipeline (CRCOP) across the permafrost-associated cold ecosystem in northeastern China carries a risk of contamination to the deep active layers and upper permafrost in case of accidental rupture of the embedded pipeline or migration of oil spills. As many soil microbes are capable of degrading petroleum, knowledge about the intrinsic degraders and the microbial dynamics in the deep subsurface could extend our understanding of the application of in-situ bioremediation. In this study, an experiment was conducted to investigate the bacterial communities in response to simulated contamination to deep soil samples by using 454 pyrosequencing amplicons. The result showed that bacterial diversity was reduced after 8-weeks contamination. A shift in bacterial community composition was apparent in crude oil-amended soils with Proteobacteria (esp. α-subdivision) being the dominant phylum, together with Actinobacteria and Firmicutes. The contamination led to enrichment of indigenous bacterial taxa like Novosphingobium, Sphingobium, Caulobacter, Phenylobacterium, Alicylobacillus and Arthrobacter, which are generally capable of degrading polycyclic aromatic hydrocarbons (PAHs). The community shift highlighted the resilience of PAH degraders and their potential for in-situ degradation of crude oil under favorable conditions in the deep soils.

  19. Crude Oil Treatment Leads to Shift of Bacterial Communities in Soils from the Deep Active Layer and Upper Permafrost along the China-Russia Crude Oil Pipeline Route

    PubMed Central

    Yang, Sizhong; Wen, Xi; Zhao, Liang; Shi, Yulan; Jin, Huijun

    2014-01-01

    The buried China-Russia Crude Oil Pipeline (CRCOP) across the permafrost-associated cold ecosystem in northeastern China carries a risk of contamination to the deep active layers and upper permafrost in case of accidental rupture of the embedded pipeline or migration of oil spills. As many soil microbes are capable of degrading petroleum, knowledge about the intrinsic degraders and the microbial dynamics in the deep subsurface could extend our understanding of the application of in-situ bioremediation. In this study, an experiment was conducted to investigate the bacterial communities in response to simulated contamination to deep soil samples by using 454 pyrosequencing amplicons. The result showed that bacterial diversity was reduced after 8-weeks contamination. A shift in bacterial community composition was apparent in crude oil-amended soils with Proteobacteria (esp. α-subdivision) being the dominant phylum, together with Actinobacteria and Firmicutes. The contamination led to enrichment of indigenous bacterial taxa like Novosphingobium, Sphingobium, Caulobacter, Phenylobacterium, Alicylobacillus and Arthrobacter, which are generally capable of degrading polycyclic aromatic hydrocarbons (PAHs). The community shift highlighted the resilience of PAH degraders and their potential for in-situ degradation of crude oil under favorable conditions in the deep soils. PMID:24794099

  20. Crude oil treatment leads to shift of bacterial communities in soils from the deep active layer and upper permafrost along the China-Russia Crude Oil Pipeline route.

    PubMed

    Yang, Sizhong; Wen, Xi; Zhao, Liang; Shi, Yulan; Jin, Huijun

    2014-01-01

    The buried China-Russia Crude Oil Pipeline (CRCOP) across the permafrost-associated cold ecosystem in northeastern China carries a risk of contamination to the deep active layers and upper permafrost in case of accidental rupture of the embedded pipeline or migration of oil spills. As many soil microbes are capable of degrading petroleum, knowledge about the intrinsic degraders and the microbial dynamics in the deep subsurface could extend our understanding of the application of in-situ bioremediation. In this study, an experiment was conducted to investigate the bacterial communities in response to simulated contamination to deep soil samples by using 454 pyrosequencing amplicons. The result showed that bacterial diversity was reduced after 8-weeks contamination. A shift in bacterial community composition was apparent in crude oil-amended soils with Proteobacteria (esp. α-subdivision) being the dominant phylum, together with Actinobacteria and Firmicutes. The contamination led to enrichment of indigenous bacterial taxa like Novosphingobium, Sphingobium, Caulobacter, Phenylobacterium, Alicylobacillus and Arthrobacter, which are generally capable of degrading polycyclic aromatic hydrocarbons (PAHs). The community shift highlighted the resilience of PAH degraders and their potential for in-situ degradation of crude oil under favorable conditions in the deep soils. PMID:24794099

  1. Russian nuclear-powered submarine decommissioning

    SciTech Connect

    Bukharin, O.; Handler, J.

    1995-11-01

    Russia is facing technical, economic and organizational difficulties in dismantling its oversized and unsafe fleet of nuclear powered submarines. The inability of Russia to deal effectively with the submarine decommissioning crisis increases the risk of environmental disaster and may hamper the implementation of the START I and START II treaties. This paper discusses the nuclear fleet support infrastructure, the problems of submarine decommissioning, and recommends international cooperation in addressing these problems.

  2. FACILITY DEACTIVATION AND DECOMMISSIONING AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Gilmour, J; William Austin, W; Cathy Sizemore, C

    2007-01-31

    In February 2002, the U.S. Department of Energy initiated actions to expedite Cleanup, focus on significant and early risk reduction, and reduce costs at the Savannah River Site (SRS). In response SRS started on a project focused on completing the decommissioning of inactive facilities in T, D, and M Areas, areas that on the perimeter of the Site, by the end of 2006. In June 2003, the Department of Energy Savannah River Operations Office (DOE-SR), the South Carolina Department of Health and Environmental Control (SCDHEC), and the Environmental Protection Agency, Region 4 (EPA-4) endorsed a Memorandum of Agreement (MOA) concerning cleanup at the Savannah River Site (SRS). The vision of the Agreement is that SRS will reduce its operations footprint to establish a buffer zone at the perimeter if the Site, while the central core area of the Site will be reserved for continuing or future long-term operations. DOE-SR, EPA-4, and SCDHEC agreed that establishing this buffer zone and appropriately sequencing environmental restoration and decommissioning activities can lead to greater efficiency and accelerate completion of entire site areas. This vision is embodied in the concept of Area Completion--which integrated operations, deactivation and decommissioning (D&D), and soils and groundwater cleanup into a time-phased approach to completing all the work necessary to address the Cold War legacy. D&D addresses the ''footprint'' of the building or structure, while the soils and groundwater project addresses any environmental remediation that may be required in the underlying and surrounding soils and groundwater. Since then, {approx}250 facilities have been decommissioned at the SRS, ranging from guard stations to nuclear fuel production facilities.

  3. Waste management for Shippingport Station Decommissioning Project: Extended summary

    SciTech Connect

    Mullee, G.R.; Schulmeister, A.R.

    1987-01-01

    The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP.

  4. ALMA Pipeline: Current Status

    NASA Astrophysics Data System (ADS)

    Shinnaga, H.; Humphreys, E.; Indebetouw, R.; Villard, E.; Kern, J.; Davis, L.; Miura, R. E.; Nakazato, T.; Sugimoto, K.; Kosugi, G.; Akiyama, E.; Muders, D.; Wyrowski, F.; Williams, S.; Lightfoot, J.; Kent, B.; Momjian, E.; Hunter, T.; ALMA Pipeline Team

    2015-12-01

    The ALMA Pipeline is the automated data reduction tool that runs on ALMA data. Current version of the ALMA pipeline produces science quality data products for standard interferometric observing modes up to calibration process. The ALMA Pipeline is comprised of (1) heuristics in the form of Python scripts that select the best processing parameters, and (2) contexts that are given for book-keeping purpose of data processes. The ALMA Pipeline produces a "weblog" that showcases detailed plots for users to judge how each step of calibration processes are treated. The ALMA Interferometric Pipeline was conditionally accepted in March 2014 by processing Cycle 0 and Cycle 1 data sets. From Cycle 2, ALMA Pipeline is used for ALMA data reduction and quality assurance for the projects whose observing modes are supported by the ALMA Pipeline. Pipeline tasks are available based on CASA version 4.2.2, and the first public pipeline release called CASA 4.2.2-pipe has been available since October 2014. One can reduce ALMA data both by CASA tasks as well as by pipeline tasks by using CASA version 4.2.2-pipe.

  5. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    SciTech Connect

    Sullivan, T.

    2014-09-24

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  6. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    SciTech Connect

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  7. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    SciTech Connect

    Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  8. Pipeline padding apparatus

    SciTech Connect

    Osadchuk, M.

    1992-06-09

    This patent describes a pipeline padding assembly for movement on a surface in a forward direction along the side of an excavated pipeline trough while separating fine material from excavated spoil piled on the underlying soil surface and placing the fine material in the pipeline trough. It comprises vehicle means adapted for movement on the surface along the pipeline trough; means for separating spoil into fine material and rough material; means for returning fine material from the separating means into the pipeline trough; means for transferring spoil piled along the pipeline trough to the separator means; a spoil guide positioned in the front of the transferring means and having an open bottom configuration which is open substantially the entire width of the transferring means; at least two spaced guide projections being on the spoil guide; a flat, planar extending ground engaging lower surface on each the guide projection.

  9. Multinode reconfigurable pipeline computer

    NASA Technical Reports Server (NTRS)

    Nosenchuck, Daniel M. (Inventor); Littman, Michael G. (Inventor)

    1989-01-01

    A multinode parallel-processing computer is made up of a plurality of innerconnected, large capacity nodes each including a reconfigurable pipeline of functional units such as Integer Arithmetic Logic Processors, Floating Point Arithmetic Processors, Special Purpose Processors, etc. The reconfigurable pipeline of each node is connected to a multiplane memory by a Memory-ALU switch NETwork (MASNET). The reconfigurable pipeline includes three (3) basic substructures formed from functional units which have been found to be sufficient to perform the bulk of all calculations. The MASNET controls the flow of signals from the memory planes to the reconfigurable pipeline and vice versa. the nodes are connectable together by an internode data router (hyperspace router) so as to form a hypercube configuration. The capability of the nodes to conditionally configure the pipeline at each tick of the clock, without requiring a pipeline flush, permits many powerful algorithms to be implemented directly.

  10. Oceanic pipeline computations

    SciTech Connect

    Marks, A.

    1980-01-01

    yechnical and economic feasibility, design, and construction of oil, gas, and two-phase oceanic pipelines systems are discussed. In addition, formulae, references, examples, and programmable calculator software (Hewlett-Packard-67) are given. The contents include: preliminary pipeline sizing; fluid characteristics; preliminary hydraulics; oceanographis; preliminary corridor selection; route selection; final pipeline design; hydraulic design; wall thickness selection; oceanographic design computations; stress analysis; and construction parameters. (JMT)

  11. Environmental restoration and decontamination & decommissioning safety documentation. Revision 2

    SciTech Connect

    Hansen, J.L.; Frauenholz, L.H.; Kerr, N.R.

    1993-05-18

    This document presents recommendations of a working group designated by the Environmental Restoration and Remediation (ER) and Decontamination and Decommissioning (D&D) subcommittees of the Westinghouse M&O (Management and Operation) Nuclear Facility Safety Committee. A commonalty of approach to safety documentation specific to ER and D&D activities was developed and is summarized below. Allowance for interpretative tolerance and documentation flexibility appropriate to the activity, graded for hazard category, duration, and complexity, was a primary consideration in development of this guidance.

  12. Decontamination & Decommissioning Equipment Tracking System (DDETS)

    SciTech Connect

    Cook, S.

    1994-07-01

    At the request of the Department of Energy (DOE)(EM-50), the Scientific Computing Unit developed a prototype system to track information and data relevant to equipment and tooling removed during decontamination and decommissioning activities. The DDETS proof-of-concept tracking system utilizes a one-dimensional (1D) and two-dimensional (2D) bar coding technology to retain and track information such as identification number, manufacturer, requisition information, and various contaminant information, etc. The information is encoded in a bar code, printed on a label and can be attached to corresponding equipment. The DDETS was developed using a proven relational database management system which allows the addition, modification, printing, and deletion of data. In addition, communication interfaces with bar code printers and bar code readers were developed. Additional features of the system include: (a) Four different reports available for the user (REAPS, transaction, and two inventory), (b) Remote automated inventory tracking capabilities, (c) Remote automated inventory tracking capability (2D bar codes allow equipment to be scanned/tracked without being linked to the DDETS database), (d) Edit, update, delete, and query capabilities, (e) On-line bar code label printing utility (data from 2D bar codes can be scanned directly into the data base simplifying data entry), and (f) Automated data backup utility. Compatibility with the Reportable Excess Automated Property System (REAPS) to upload data from DDETS is planned.

  13. Decontamination and decommissioning of the initial engine test facility and the IET two-inch hot-waste line

    SciTech Connect

    Stoll, F.E.

    1987-04-01

    The Initial Engine Test Decommissioning Project is described in this report. The Initial Engine Test facility was constructed and operated at the National Reactor Testing Station, now known as the Idaho National Engineering Laboratory, to support the Aircraft Nuclear Propulsion Program and the Systems for Nuclear Auxiliary Power Transient test program, circa 1950 through 1960s. Due to the severe nature of these nuclear test programs, a significant amount of radioactive contamination was deposited in various portions of the Initial Engine Test Facility. Characterizations, decision analyses, and plans for decontamination and decommissioning were prepared from 1982 through 1985. Decontamination and decommissioning activities were performed in such a way that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory remains. These decontamination and decommissioning activities began in 1985 and were completed in 1987. 13 figs.

  14. Pipeline transport of biomass.

    PubMed

    Kumar, Amit; Cameron, Jay B; Flynn, Peter C

    2004-01-01

    The cost of transporting wood chips by truck and by pipeline as a water slurry was determined. In a practical application of field delivery by truck of biomass to a pipeline inlet, the pipeline will only be economical at large capacity ( >0.5 million dry t/yr for a one-way pipeline, and >1.25 million dry t/yr for a two-way pipeline that returns the carrier fluid to the pipeline inlet), and at medium to long distances ( >75 km [one-way] and >470 km [two-way] at a capacity of 2 million dry t/yr). Mixed hardwood and softwood chips in western Canada rise in moisture level from about 50% to 67% when transported in water; the loss in lower heating value (LHV) would preclude the use of water slurry pipelines for direct combustion applications. The same chips, when transported in a heavy gas oil, take up as much as 50% oil by weight and result in a fuel that is >30% oil on mass basis and is about two-thirds oil on a thermal basis. Uptake of water by straw during slurry transport is so extreme that it has effectively no LHV. Pipeline-delivered biomass could be used in processes that do not produce contained water as a vapor, such as supercritical water gasification.

  15. Characterisation of radioactive waste products associated with plant decommissioning.

    PubMed

    Sejvar, J; Fero, A H; Gil, C; Hagler, R J; Santiago, J L; Holgado, A; Swenson, R

    2005-01-01

    The inventory of radioactivity that must be considered in the decommissioning of a typical 1000 MWe Spanish pressurised water reactor (PWR) was investigated as part of a generic plant decommissioning study. Analyses based on DORT models (in both R-Z and R-theta geometries) were used with representative plant operating history and core power distribution data in defining the expected neutron environment in regions near the reactor core. The activation analyses were performed by multiplying the DORT scalar fluxes by energy-dependent reaction cross sections (based on ENDF/B-VI data) to generate reaction rates on a per atom basis. The results from the ORIGEN2 computer code were also used for determining the activities associated with certain nuclides where multi-group cross section data were not available. In addition to the bulk material activation of equipment and structures near the reactor, the activated corrosion-product (or 'crud') deposits on system and equipment surfaces were considered. The projected activities associated with these sources were primarily based on plant data and experience from operating PWR plants. PMID:16381771

  16. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 2 2012-04-01 2012-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  17. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 2 2014-04-01 2014-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  18. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 2 2013-04-01 2013-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  19. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 2 2011-04-01 2011-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  20. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  1. Decision framework for platform decommissioning in California.

    PubMed

    Bernstein, Brock B

    2015-10-01

    This article describes the overall decision framework for eventual decisions about decommissioning the 27 operating oil and gas platforms offshore southern California. These platforms will eventually reach the end of their useful lifetimes (estimated between 2015 and 2030, although specific dates have not been determined). Current law and regulations allow for alternative uses in lieu of the complete removal required in existing leases. To prepare for eventual decommissioning, the California Natural Resources Agency initiated an in-depth process to identify and investigate issues surrounding possible decommissioning alternatives. The detailed evaluation of alternatives focused on 2-complete removal and artificial reefing that included partial removal to 85 feet below the waterline. These were selected after a comparison of the technical and economic feasibility of several potential alternatives, availability of a legal framework for implementation, degree of interest from proponents, and relative acceptance by state and federal decision makers. Despite California's history of offshore oil and gas production, only 7 decommissioning projects have been completed and these were all relatively small and close to shore. In contrast, nearly 30% of the California platforms are in water depths (as much as 1200 feet) that exceed any decommissioning project anywhere in the world. Most earlier projects considered an artificial reefing alternative but none were implemented and all platforms were completely removed. Future decisions about decommissioning must grapple with a more complex decision context involving greater technological and logistical challenges and cost, a wider range of viable options, tradeoffs among environmental impacts and benefits, and an intricate maze of laws, regulations, and authorities. The specific engineering differences between complete and partial removal provide an explicit basis for a thorough evaluation of their respective impacts.

  2. Decision framework for platform decommissioning in California.

    PubMed

    Bernstein, Brock B

    2015-10-01

    This article describes the overall decision framework for eventual decisions about decommissioning the 27 operating oil and gas platforms offshore southern California. These platforms will eventually reach the end of their useful lifetimes (estimated between 2015 and 2030, although specific dates have not been determined). Current law and regulations allow for alternative uses in lieu of the complete removal required in existing leases. To prepare for eventual decommissioning, the California Natural Resources Agency initiated an in-depth process to identify and investigate issues surrounding possible decommissioning alternatives. The detailed evaluation of alternatives focused on 2-complete removal and artificial reefing that included partial removal to 85 feet below the waterline. These were selected after a comparison of the technical and economic feasibility of several potential alternatives, availability of a legal framework for implementation, degree of interest from proponents, and relative acceptance by state and federal decision makers. Despite California's history of offshore oil and gas production, only 7 decommissioning projects have been completed and these were all relatively small and close to shore. In contrast, nearly 30% of the California platforms are in water depths (as much as 1200 feet) that exceed any decommissioning project anywhere in the world. Most earlier projects considered an artificial reefing alternative but none were implemented and all platforms were completely removed. Future decisions about decommissioning must grapple with a more complex decision context involving greater technological and logistical challenges and cost, a wider range of viable options, tradeoffs among environmental impacts and benefits, and an intricate maze of laws, regulations, and authorities. The specific engineering differences between complete and partial removal provide an explicit basis for a thorough evaluation of their respective impacts. PMID:26259879

  3. Using Tracer Technology to Characterize Contaminated Pipelines

    SciTech Connect

    Maresca, Joseph, W., Jr., Ph.D.; Bratton, Wesley, L., Ph.D., P.E.; Dickerson, Wilhelmina; Hales, Rochelle

    2005-12-30

    The Pipeline Characterization Using Tracers (PCUT) technique uses conservative and partitioning, reactive or other interactive tracers to remotely determine the amount of contaminant within a run of piping or ductwork. The PCUT system was motivated by a method that has been successfully used to characterize subsurface soil contaminants and is similar in operation to that of a gas chromatography column. By injecting a ?slug? of both conservative and partitioning tracers at one end (or section) of the piping and measuring the time history of the concentration of the tracers at the other end (or another section) of the pipe, the presence, location, and amount of contaminant within the pipe or duct can be determined. The tracers are transported along the pipe or duct by a gas flow field, typically air or nitrogen, which has a velocity that is slow enough so that the partitioning tracer has time to interact with the contaminant before the tracer slug completely passes over the contaminate region. PCUT not only identifies the presence of contamination, it also can locate the contamination along the pipeline and quantify the amount of residual. PCUT can be used in support of deactivation and decommissioning (D&D) of piping and ducts that may have been contaminated with hazardous chemicals such as chlorinated solvents, petroleum products, radioactive materials, or heavy metals, such as mercury.

  4. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-07-01

    Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

  5. Decontamination, decommissioning, and vendor advertorial issue, 2006

    SciTech Connect

    Agnihotri, Newal

    2006-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: NPP Krsko revised decommissioning program, by Vladimir Lokner and Ivica Levanat, APO d.o.o., Croatia, and Nadja Zeleznik and Irena Mele, ARAO, Slovenia; Supporting the renaissance, by Marilyn C. Kray, Exelon Nuclear; Outage world an engineer's delight, by Tom Chrisopher, Areva, NP Inc.; Optimizing refueling outages with R and D, by Ross Marcoot, GE Energy; and, A successful project, by Jim Lash, FirstEnergy.

  6. Decommissioning of a tritium-contaminated laboratory

    SciTech Connect

    Harper, J.R.; Garde, R.

    1981-11-01

    A tritium laboratory facility at the Los Alamos National Laboratory, Los Alamos, New Mexico, was decommissioned in 1979. The project involved dismantling the laboratory equipment and disposing of the equipment and debris at an on-site waste disposal/storage area. The laboratory was constructed in 1953 and was in service for tritium research and fabrication of lithium tritide components until 1974. The major features of the laboratory included some 25 meters of gloveboxes and hoods, associated vacuum lines, utility lines, exhaust ducts, electrodryers, blowers, and laboratory benches. This report presents details on the decommissioning, health physics, waste management, environmental surveillance, and costs for the operation.

  7. The health risks of decommissioning nuclear facilities.

    PubMed

    Dodic-Fikfak, M; Clapp, R; Kriebel, D

    1999-01-01

    The health risks facing workers involved in decommissioning nuclear facilities are a critical concern as the nuclear weapons complex and nuclear power plants begin to be dismantled. In addition to risks from exposure to radioactive materials, there are risks from other common industrial materials like crystalline silica dust and asbestos. We discuss these issues in the context of recent research on the risk of low-level ionizing radiation, the classification of crystalline silica as a carcinogen, and early experience with decommissioning nuclear facilities in the United States. Health and safety advocates will need to be vigilant to prevent worker exposure. PMID:17208791

  8. The health risks of decommissioning nuclear facilities.

    PubMed

    Dodic-Fikfak, M; Clapp, R; Kriebel, D

    1999-01-01

    The health risks facing workers involved in decommissioning nuclear facilities are a critical concern as the nuclear weapons complex and nuclear power plants begin to be dismantled. In addition to risks from exposure to radioactive materials, there are risks from other common industrial materials like crystalline silica dust and asbestos. We discuss these issues in the context of recent research on the risk of low-level ionizing radiation, the classification of crystalline silica as a carcinogen, and early experience with decommissioning nuclear facilities in the United States. Health and safety advocates will need to be vigilant to prevent worker exposure.

  9. Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141

    SciTech Connect

    Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M.; Michal, V.; Vargovcik, L.

    2012-07-01

    The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementation of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design of

  10. INTERNAL REPAIR OF PIPELINES

    SciTech Connect

    Robin Gordon; Bill Bruce; Ian Harris; Dennis Harwig; George Ritter; Bill Mohr; Matt Boring; Nancy Porter; Mike Sullivan; Chris Neary

    2004-12-31

    liners, indicating that this type of liner is only marginally effective at restoring the pressure containing capabilities of pipelines. Failure pressures for larger diameter pipe repaired with a semi-circular patch of carbon fiber-reinforced composite lines were also marginally greater than that of a pipe section with un-repaired simulated damage without a liner. These results indicate that fiber reinforced composite liners have the potential to increase the burst pressure of pipe sections with external damage Carbon fiber based liners are viewed as more promising than glass fiber based liners because of the potential for more closely matching the mechanical properties of steel. Pipe repaired with weld deposition failed at pressures lower than that of un-repaired pipe in both the virgin and damaged conditions, indicating that this repair technology is less effective at restoring the pressure containing capability of pipe than a carbon fiber-reinforced liner repair. Physical testing indicates that carbon fiber-reinforced liner repair is the most promising technology evaluated to-date. The first round of optimization and validation activities for carbon-fiber repairs are complete. Development of a comprehensive test plan for this process is recommended for use in the field trial portion of this program.

  11. 77 FR 31827 - Pipeline Safety: Pipeline Damage Prevention Programs

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-30

    ... Pipeline and Hazardous Materials Safety Administration 49 CFR Parts 196 and 198 RIN 2137-AE43 Pipeline Safety: Pipeline Damage Prevention Programs AGENCY: Pipeline and Hazardous Materials Safety... April 2, 2012, PHMSA published a Notice of Proposed Rulemaking (NPRM) seeking to revise the...

  12. 76 FR 53086 - Pipeline Safety: Safety of Gas Transmission Pipelines

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-25

    ... pipeline operators. In 2003, similar IM regulations were enacted for gas pipelines (68 FR 69778; 12/15/2003...: Safety of Gas Transmission Pipelines AGENCY: Pipeline and Hazardous Materials Safety Administration...). SUMMARY: PHMSA is considering whether changes are needed to the regulations governing the safety of...

  13. Criticality safety aspects of decontamination and decommissioning at defense nuclear facilities

    SciTech Connect

    Croucher, D.W.

    1994-02-01

    Defense nuclear facilities have operated for forty years with a well-defined mission to produce weapons components for the nation. With the end of the cold war, the facilities` missions have changed to one of decontamination and decommissioning. Off-normal operations and use of new procedures, such as will exist during these activities, have often been among the causal factors in previous criticality accidents at process facilities. This paper explores the similarities in causal factors in previous criticality accidents to the conditions existing in current defense nuclear facilities undergoing the transition to decontamination and decommissioning. Practices to reduce the risk to workers, the public, and the environment are recommended.

  14. Pollution from pipelines

    SciTech Connect

    Not Available

    1991-01-01

    During the 1980s, over 3,900 spills from land-based pipelines released nearly 20 million gallons of oil into U.S. waters-almost twice as much as was released by the March 1989 Exxon Valdez oil spill. Although the Department of Transportation is responsible for preventing water pollution from petroleum pipelines, GAO found that it has not established a program to prevent such pollution. DOT has instead delegated this responsibility to the Coast Guard, which has a program to stop water pollution from ships, but not from pipelines. This paper reports that, in the absence of any federal program to prevent water pollution from pipelines, both the Coast Guard and the Environmental Protection Agency have taken steps to plan for and respond to oil spills, including those from pipelines, as required by the Clean Water Act. The Coast Guard cannot, however, adequately plan for or ensure a timely response to pipeline spills because it generally is unaware of specific locations and operators of pipelines.

  15. Technical Aspects Regarding the Management of Radioactive Waste from Decommissioning of Nuclear Facilities

    SciTech Connect

    Dragolici, F.; Turcanu, C. N.; Rotarescu, G.; Paunica, I.

    2003-02-25

    The proper application of the nuclear techniques and technologies in Romania started in 1957, once with the commissioning of the Research Reactor VVR-S from IFIN-HH-Magurele. During the last 45 years, appear thousands of nuclear application units with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used different nuclear facilities containing radioactive sources and generating a great variety of radioactive waste during the decommissioning after the operation lifetime is accomplished. A new aspect appears by the planning of VVR-S Research Reactor decommissioning which will be a new source of radioactive waste generated by decontamination, disassembling and demolition activities. By construction and exploitation of the Radioactive Waste Treatment Plant (STDR)--Magurele and the National Repository for Low and Intermediate Radioactive Waste (DNDR)--Baita, Bihor county, in Romania was solved the management of radioactive wastes arising from operation and decommissioning of small nuclear facilities, being assured the protection of the people and environment. The present paper makes a review of the present technical status of the Romanian waste management facilities, especially raising on treatment capabilities of ''problem'' wastes such as Ra-266, Pu-238, Am-241 Co-60, Co-57, Sr-90, Cs-137 sealed sources from industrial, research and medical applications. Also, contain a preliminary estimation of quantities and types of wastes, which would result during the decommissioning project of the VVR-S Research Reactor from IFIN-HH giving attention to some special category of wastes like aluminum, graphite and equipment, components and structures that became radioactive through neutron activation. After analyzing the technical and scientific potential of STDR and DNDR to handle big amounts of wastes resulting from the decommissioning of VVR-S Research Reactor and small nuclear facilities, the necessity of

  16. 75 FR 80697 - Nuclear Decommissioning Funds

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-23

    ...This document contains final regulations under section 468A of the Internal Revenue Code relating to deductions for contributions to trusts maintained for decommissioning nuclear power plants. These final regulations affect taxpayers that own an interest in a nuclear power plant and reflect recent statutory changes. The corresponding temporary regulations are...

  17. Halons: The hidden dangers of accelerated decommissioning

    SciTech Connect

    Dalzell, G.A.

    1996-12-31

    Many operators have introduced a decommissioning programme for halon systems following the Montreal Protocol and the cessation of production of 1211 and 1301. Some have already decommissioned all their systems. This paper questions whether rapid decommissioning, particularly when faced with external pressure or a desire to be {open_quotes}seen to be green{close_quotes} does reduce the environmental impact. It examines the lifecycle of the halon in an existing system until it is finally destroyed, used, or lost to the atmosphere. Halon is one of the most difficult gases to contain. It is more prone to leakage than almost any other gas. Fixed systems, which contain the majority of 1301 also have valve arrangements which are designed to open with the minimum of energy input. As a result they are also prone to accidental discharge. This paper examines these aspects and the potential for loss to the atmosphere when decommissioning, transporting, recycling and storing the halon. Controlling leakage and preventing accidental discharges within systems has been addressed in other work.

  18. University of Virginia Reactor Facility Decommissioning Results

    SciTech Connect

    Ervin, P. F.; Lundberg, L. A.; Benneche, P. E.; Mulder, R. U.; Steva, D. P.

    2003-02-24

    The University of Virginia Reactor Facility started accelerated decommissioning in 2002. The facility consists of two licensed reactors, the CAVALIER and the UVAR. This paper will describe the progress in 2002, remaining efforts and the unique organizational structure of the project team.

  19. Decontamination and decommissioning focus area. Technology summary

    SciTech Connect

    1995-06-01

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities.

  20. 78 FR 663 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-04

    ... Federal Regulations is sold by the Superintendent of Documents. #0;Prices of new books are listed in the... complying with the NRC's Decommissioning Planning Rule (DPR) (76 FR 35512; June 17, 2011). The DPR went into... available documents online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html . To begin...

  1. Decontamination and decommissioning of Shippingport commercial reactor

    SciTech Connect

    Schreiber, J.

    1989-11-01

    To a certain degree, the decontamination and decommissioning (D and D) of the Shippingport reactor was a joint venture with Duquesne Light Company. The structures that were to be decommissioned were to be removed to at least three feet below grade. Since the land had been leased from Duquesne Light, there was an agreement with them to return the land to them in a radiologically safe condition. The total enclosure volume for the steam and nuclear containment systems was about 1.3 million cubic feet, more than 80% of which was below ground. Engineering plans for the project were started in July of 1980 and the final environmental impact statement (EIS) was published in May of 1982. The plant itself was shut down in October of 1982 for end-of-life testing and defueling. The engineering services portion of the decommissioning plans was completed in September of 1983. DOE moved onto the site and took over from the Navy in September of 1984. Actual physical decommissioning began after about a year of preparation and was completed about 44 months later in July of 1989. This paper describes the main parts of D and D.

  2. Deepwater pipeline recovery

    SciTech Connect

    McStravick, D.M.; Baugh, B.F.

    1997-07-01

    The paper gives a presentation of the tooling concepts used for the recovery of steel and flexible flowlines in the Gulf of Mexico Shell Tahoe I area in the summer of 1996 in 1,370 ft. of sea water. This offshore operation required a Global Grabber to engage and retrieve 4 1/2-in. steel pipelines, an ROV Pipeline Spear to internally engage the end of the 4 1/2-in. steel pipelines, and a FlexGrip Assembly to wrap and grab 5.566-in. OD flexible pipe. The design of the tooling emphasized the use of API 17D ROV interfaces.

  3. Decontamination and decommissioning of the JANUS reactor at the Argonne National Laboratory-East site

    SciTech Connect

    Fellhauer, C.R.; Garlock, G.A.

    1997-05-01

    Argonne National Laboratory has begun the decontamination and decommissioning (D&D) of the JANUS Reactor Facility. The project is managed by the Technology Development Division`s D&D Program personnel. D&D procedures are performed by sub-contractor personnel. Specific activities involving the removal, size reduction, and packaging of radioactive components and facilities are discussed.

  4. 10 CFR 70.25 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... submitted when this rule becomes effective November 24, 1995. (5) If, in surveys made under 10 CFR 20.1501(a... that would, if left uncorrected, prevent the site from meeting the 10 CFR 20.1402 criteria for... all decommissioning activities; (B) The cost of meeting the 10 CFR 20.1402 criteria for...

  5. 10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ...) If, in surveys made under 10 CFR 20.1501(a), residual radioactivity in the facility and environment... meeting the 10 CFR 20.1402 criteria for unrestricted use, the licensee must submit a decommissioning... activities; (B) The cost of meeting the 10 CFR 20.1402 criteria for unrestricted use, provided that, if...

  6. 10 CFR 70.25 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... submitted when this rule becomes effective November 24, 1995. (5) If, in surveys made under 10 CFR 20.1501(a... that would, if left uncorrected, prevent the site from meeting the 10 CFR 20.1402 criteria for... all decommissioning activities; (B) The cost of meeting the 10 CFR 20.1402 criteria for...

  7. 10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ...) If, in surveys made under 10 CFR 20.1501(a), residual radioactivity in the facility and environment... meeting the 10 CFR 20.1402 criteria for unrestricted use, the licensee must submit a decommissioning... activities; (B) The cost of meeting the 10 CFR 20.1402 criteria for unrestricted use, provided that, if...

  8. THE SCIENCE OF REMEDIATION, ABATEMENT, AND DECOMMISSIONING OF CATASTROPHIC (AND LESSER) EVENTS

    EPA Science Inventory

    This is a brief overview of some of the activities commonly involved in remediation, abatement, and decommissioning of areas affected by significant events whether natural or man-made. Some examples from the EPA's post-Katrina and anthrax responses are used to demonstrate the sc...

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

    SciTech Connect

    Elder, H. K.

    1981-10-01

    .88 million, the annual maintenance and surveillance cost is estimated to be about $0.095 million, and deferred decontamination is estimated to cost about $6.50 million. Therefore, passive SAFSTOR for 10 years is estimated to cost $8.33 million in nondiscounted 1981 dollars. DECON with lagoon waste stabilization is estimated to cost about $4.59 million, with an annual cost of $0.011 million for long-term care. All of these estimates include a 25% contingency. Waste management costs for DECON, including the net cost of disposal of the solvent extraction lagoon wastes by shipping those wastes to a uranium mill for recovery of residual uranium, comprise about 38% of the total decommissioning cost. Disposal of lagoon waste at a commercial low-level waste burial ground is estimated to add $10.01 million to decommissioning costs. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year committed dose equivalent to members of the public from airborne releases during normal decommissioning activities is estimated to 'Je about 4.0 man-rem. Radiation doses to the public from accidents are found to be very low for all phases of decommissioning. Occupational radiation doses from normal decommissioning operations (excluding transport operations) are estimated to be about 79 man-rem for DECON and about 80 man-rem for passive SAFSTOR with 10 years of safe storage. Doses from DECON with lagoon waste stabilization are about the same as for DECON except there is less dose resulting from transportation of radioactive waste. The number of fatalities and serious lost-time injuries not related to radiation is found to be very small for all decommissioning alternatives. Comparison of the cost estimates shows that DECON with lagoon waste stabilization is the least expensive method. However, this alternative does not allow unrestricted release of the site. The cumulative cost of maintenance and surveillance and the

  10. Rnnotator Assembly Pipeline

    SciTech Connect

    Martin, Jeff

    2010-06-03

    Jeff Martin of the DOE Joint Genome Institute discusses a de novo transcriptome assembly pipeline from short RNA-Seq reads on June 3, 2010 at the "Sequencing, Finishing, Analysis in the Future" meeting in Santa Fe, NM

  11. Commanding Constellations (Pipeline Architecture)

    NASA Technical Reports Server (NTRS)

    Ray, Tim; Condron, Jeff

    2003-01-01

    Providing ground command software for constellations of spacecraft is a challenging problem. Reliable command delivery requires a feedback loop; for a constellation there will likely be an independent feedback loop for each constellation member. Each command must be sent via the proper Ground Station, which may change from one contact to the next (and may be different for different members). Dynamic configuration of the ground command software is usually required (e.g. directives to configure each member's feedback loop and assign the appropriate Ground Station). For testing purposes, there must be a way to insert command data at any level in the protocol stack. The Pipeline architecture described in this paper can support all these capabilities with a sequence of software modules (the pipeline), and a single self-identifying message format (for all types of command data and configuration directives). The Pipeline architecture is quite simple, yet it can solve some complex problems. The resulting solutions are conceptually simple, and therefore, reliable. They are also modular, and therefore, easy to distribute and extend. We first used the Pipeline architecture to design a CCSDS (Consultative Committee for Space Data Systems) Ground Telecommand system (to command one spacecraft at a time with a fixed Ground Station interface). This pipeline was later extended to include gateways to any of several Ground Stations. The resulting pipeline was then extended to handle a small constellation of spacecraft. The use of the Pipeline architecture allowed us to easily handle the increasing complexity. This paper will describe the Pipeline architecture, show how it was used to solve each of the above commanding situations, and how it can easily be extended to handle larger constellations.

  12. Colombian export oil pipeline

    SciTech Connect

    Duncan, K. ); Enright, B. )

    1989-06-01

    The authors discuss how bringing crude oil to market often requires extraordinary determination and effort to overcome the obstacles of terrain and time. They describe a pipeline project on a 53-week suicide schedule to get oil across the Colombian Andes. After confronting setbacks, they completed a job that included 304 miles of pipeline, 497 miles of telecommunications and a major offshore terminal in only 47 weeks.

  13. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    SciTech Connect

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs

  14. Decommissioning Cost Estimating Factors And Earned Value Integration

    SciTech Connect

    Sanford, P.C.; Cimmarron, E.

    2008-07-01

    The Rocky Flats 771 Project progressed from the planning stage of decommissioning a plutonium facility, through the strip-out of highly-contaminated equipment, removal of utilities and structural decontamination, and building demolition. Actual cost data was collected from the strip-out activities and compared to original estimates, allowing the development of cost by equipment groupings and types and over time. Separate data was developed from the project control earned value reporting and compared with the equipment data. The paper discusses the analysis to develop the detailed factors for the different equipment types, and the items that need to be considered during characterization of a similar facility when preparing an estimate. The factors are presented based on direct labor requirements by equipment type. The paper also includes actual support costs, and examples of fixed or one-time start-up costs. The integration of the estimate and the earned value system used for the 771 Project is also discussed. The paper covers the development of the earned value system as well as its application to a facility to be decommissioned and an existing work breakdown structure. Lessons learned are provided, including integration with scheduling and craft supervision, measurement approaches, and verification of scope completion. In summary: The work of decommissioning the Rocky Flats 771 Project process equipment was completed in 2003. Early in the planning process, we had difficulty in identifying credible data and implementing processes for estimating and controlling this work. As the project progressed, we were able to collect actual data on the costs of removing plutonium contaminated equipment from various areas over the life of this work and associate those costs with individual pieces of equipment. We also were able to develop and test out a system for measuring the earned value of a decommissioning project based on an evolving estimate. These were elements that

  15. Landscape scale ecological monitoring as part of an EIA of major construction activities: experience at the Turkish section of the BTC crude oil pipeline project.

    PubMed

    Sahin, Sükran; Kurum, Ekrem

    2009-09-01

    Ecological monitoring is a complementary component of the overall environmental management and monitoring program of any Environmental Impact Assessment (EIA) report. The monitoring method should be developed for each project phase and allow for periodic reporting and assessment of compliance with the environmental conditions and requirements of the EIA. Also, this method should incorporate a variance request program since site-specific conditions can affect construction on a daily basis and require time-critical application of alternative construction scenarios or environmental management methods integrated with alternative mitigation measures. Finally, taking full advantage of the latest information and communication technologies can enhance the quality of, and public involvement in, the environmental management program. In this paper, a landscape-scale ecological monitoring method for major construction projects is described using, as a basis, 20 months of experience on the Baku-Tbilisi-Ceyhan (BTC) Crude Oil Pipeline Project, covering Turkish Sections Lot B and Lot C. This analysis presents suggestions for improving ecological monitoring for major construction activities.

  16. Virtual Astronomical Pipelines

    NASA Astrophysics Data System (ADS)

    Dave, R.; Protopapas, P.; Lehner, M.

    2007-10-01

    The sheer magnitude of databases and data rates in new surveys makes it hard to develop pipelines to enable both the analysis of data and the federation of these databases for correlation and followup. There is thus a compelling need to facilitate the creation and management of dynamic workflow pipelines that enable correlating data between separate, parallel streams; changing the workflow in response to an event; using the NVO to obtain additional needed information from databases; and modifying the observing program of a primary survey to follow-up a transient or moving object. This paper describes such a Virtual Astronomical Pipeline (VAP) system which is running in the TAOS project. The software enables components in the pipeline to react to events encapsulated in XML messages, modifying and subsequently routing these messages to multiple other components. This architecture allows for the bootstrapping of components individually in the development process and for dynamic reconfiguration of the pipeline as a response to external and internal events. The software will be extended for future work in combining the results of surveys and followups into a global virtual pipeline.

  17. 30 CFR 285.657 - What must I do upon completion of approved activities under my GAP?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL... your decommissioning application as provided in §§ 285.905 and 285.906. Cable and Pipeline Deviations...

  18. An Aperture Photometry Pipeline for K2 Data

    NASA Astrophysics Data System (ADS)

    Buzasi, Derek L.; Carboneau, Lindsey; Lezcano, Andy; Vydra, Ekaterina

    2016-01-01

    As part of an ongoing research program with undergraduate students at Florida Gulf Coast University, we have constructed an aperture photometry pipeline for K2 data. The pipeline performs dynamic automated aperture mask definition for all targets in the K2 fields, followed by aperture photometry and detrending. Our pipeline is currently used to support a number of projects, including studies of stellar rotation and activity, red giant asteroseismology, gyrochronology, and exoplanet searches. In addition, output is used to support an undergraduate class on exoplanets aimed at a student audience of both majors and non-majors. The pipeline is designed for both batch and single-target use, and is easily extensible to data from other missions, and pipeline output is available to the community. This paper will describe our pipeline and its capabilities and illustrate the quality of the results, drawing on all of the applications for which it is currently used.

  19. NMSS handbook for decommissioning fuel cycle and materials licensees

    SciTech Connect

    Orlando, D.A.; Hogg, R.C.; Ramsey, K.M.

    1997-03-01

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

  20. In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367

    SciTech Connect

    Serrato, Michael G.; Musall, John C.; Bergren, Christopher L.

    2013-07-01

    The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m{sup 3}) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and international

  1. Idaho Robotics Opportunities for K-12 Students: A K-12 Pipeline of Activities Promoting Careers in Science, Engineering, and Technology

    ERIC Educational Resources Information Center

    Ewers, Timothy G.

    2010-01-01

    4-H youth development programs nationwide are responding to the 4-H National Science, Engineering, and Technology (4-H SET) Initiative to involve more youth in Science, Engineering, and Technology activities. The goal is to increase the numbers of youth choosing to pursue SET careers. This article describes a program that is having great success…

  2. The AVR (HTGR) decommissioning project with new strategy

    SciTech Connect

    Sterner, Hakan; Rittscher, Dieter

    2007-07-01

    The 15-MWel prototype pilot reactor AVR is a pebble bed HTGR. It was designed in the late 50's and was connected to the grid end of 1967. After 21 y of successful operation the reactor was shut down end of 1988. In 1994 the first decommissioning license was granted and work with defueling, dismantling and preparation of a Safe Enclosure started. The primary system is contaminated with the fission products Sr{sup 90} and Cs{sup 137} and the activation products are Co{sup 60}, C{sup 14} and H{sup 3}. Due to the large amounts of Sr and Cs bound to graphite dust, the dismantling of systems connected to the pressure vessel is very tedious. In 2003 the AVR company was restructured and the strategy of the decommissioning was changed from safe enclosure to green field, i.e. the complete direct dismantling of all facilities and clean up of the site. The highlight during the dismantling is the removal of the reactor vessel (diameter ca. 7.6 m and length ca. 26 m) in one piece. Before handling the reactor vessel it will be filled with low density cellular concrete. Subsequently the reactor building will be cut open and the reactor vessel (total weight ca. 2100 Mg) lifted out and transported to an interim store. (authors)

  3. DECOMMISSIONING THE BROOKHAVEN NATIONAL LABORATORY BUILDING 830 GAMMA IRRADIATION FACILITY.

    SciTech Connect

    BOWERMAN, B.S.; SULLIVAN, P.T.

    2001-08-13

    The Building 830 Gamma Irradiation Facility (GIF) at Brookhaven National Laboratory (BNL) was decommissioned because its design was not in compliance with current hazardous tank standards and its cobalt-60 sources were approaching the end of their useful life. The facility contained 354 stainless steel encapsulated cobalt-60 sources in a pool, which provided shielding. Total cobalt-60 inventory amounted to 24,000 Curies when the sources were shipped for disposal. The decommissioning project included packaging, transport, and disposal of the sources and dismantling and disposing of all other equipment associated with the facility. Worker exposure was a major concern in planning for the packaging and disposal of the sources. These activities were planned carefully according to ALARA (As Low As Reasonably Achievable) principles. As a result, the actual occupational exposures experienced during the work were within the planned levels. Disposal of the pool water required addressing environmental concerns, since the planned method was to discharge the slightly contaminated water to the BNL sewage treatment plant. After the BNL evaluation procedure for discharge to the sewage treatment plant was revised and reviewed by regulators and BNL's Community Advisory Council, the pool water was discharged to the Building 830 sanitary system. Because the sources were sealed and the pool water contamination levels were low, most of the remaining equipment was not contaminated; therefore disposal was straightforward, as scrap metal and construction debris.

  4. 75 FR 4134 - Pipeline Safety: Leak Detection on Hazardous Liquid Pipelines

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-26

    ... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Leak Detection on Hazardous Liquid Pipelines AGENCY: Pipeline and Hazardous Materials Safety Administration; DOT. ACTION: Notice; Issuance of Advisory Bulletin. SUMMARY: The Pipeline and Hazardous Materials Safety Administration (PHMSA) is...

  5. 77 FR 61825 - Pipeline Safety: Notice of Public Meeting on Pipeline Data

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-11

    ... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Notice of Public Meeting on Pipeline Data AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of public meeting. SUMMARY: PHMSA and the National Association of Pipeline Safety...

  6. Technology, safety and costs of decommissioning a reference pressurized water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    SciTech Connect

    Konzek, G.J.; Smith, R.I.

    1988-07-01

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies on conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference pressurized water reactor (PWR) described in the earlier study; defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs; and completing a study of recent PWR steam generator replacements to determine realistic estimates for time, costs and doses associated with steam generator removal during decommissioning. This report presents the results of recent PNL studies to provide supporting information in four areas concerning decommissioning of the reference PWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; assessing the cost and dose impacts of recent steam generator replacements; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

  7. Gnome site decontamination and decommissioning project

    SciTech Connect

    Orcutt, J.A.; Sorom, E.R.

    1982-08-01

    In July 1977, DOE/Headquarters directed DOE/NV to design a decontamination and decommissioning plan for the Gnome site, 48 kilometers southeast of Carlsbad, New Mexico. The plan incorporated three distinct phases. During Phase I, both aerial and ground radiological surveys were conducted on the site. Radiological decontamination criteria were established, and a decontamination plan was developed based on the radiological survey results. During Phase II, site preparatory and rehabilitation work was completed. The actual land area decontamination was accomplished during Phase III with conventional earthmoving equipment. A gravity water injection system deposited 36,700 metric tons of contaminated soil and salt in the Gnome cavity. After completion of the decontamination and decommissioning operations, the Gnome site was returned to the Bureau of Land Management for unrestricted surface use.

  8. Optimized nuclear plant decommissioning economics through repowering

    SciTech Connect

    Demoss, D.; Charles, R.P.

    1996-11-01

    Nuclear power has provided a significant portion of electricity produced in the US over the last 39 years. Since the first commercial nuclear plant at Shippingport, Pennsylvania, started producing power in 1957, 110 nuclear plants have been placed in service. This accounts for approximately 20% of the US electric power production. In some states the number is much higher: Illinois relies on nuclear power for approximately 70% of its electricity needs. The generation of electricity from nuclear power will start to decrease in the year 2005 due to a number of plants being taken out of service as they reach the end of their design life (EDL). As these nuclear plants approach their design basis life of 40 years, plant owners will be faced with strategic decisions concerning continued operation through license renewal, decommissioning, or repowering. Without license renewal 20 units totaling more than 14 gigawatts will reach EDL by the year 2010. Three basic options are available to nuclear utilities: (1) continued operation through nuclear license renewal beyond EDL; (2) shutdown and decommissioning at EDL; (3) continued operation through nonnuclear repowering. This paper briefly reviews license renewal and decommissioning issues. Its primary focus is on the feasibility of Option 3 by reviewing the conceptual technical requirements for nonnuclear repowering and its associated economics.

  9. Protecting a pipeline

    SciTech Connect

    Gray, D.H ); Garcia-Lopez, M. )

    1994-12-01

    This article describes some of the difficulties in constructing an oil pipeline in Colombia across a forested mountain range that has erosion-prone slopes. Engineers are finding ways to protect the pipeline against slope failures and severe erosion problems while contending with threats of guerrilla attacks. Torrential rainfall, precipitous slopes, unstable soils, unfavorable geology and difficult access make construction of an oil pipeline in Colombia a formidable undertaking. Add the threat of guerrilla attacks, and the project takes on a new dimension. In the country's central uplands, a 76 cm pipeline traverses some of the most daunting and formidable terrain in the world. The right-of-way crosses rugged mountains with vertical elevations ranging from 300 m to 2,000 mm above sea level over a distance of some 30 km. The pipeline snakes up and down steep forested inclines in some spots and crosses streams and faults in others, carrying the country's major export--petroleum--from the Cusiana oil field, located in Colombia's lowland interior, to the coast.

  10. Decommissioning nuclear power plants - the wave of the future

    SciTech Connect

    Griggs, F.S. Jr.

    1994-12-31

    The paper discusses the project controls developed in the decommissioning of a nuclear power plant. Considerations are given to the contaminated piping and equipment that have to be removed and the spent and used fuel that has to be disposed of. The storage issue is of primary concern here. The cost control aspects and the dynamics of decommissioning are discussed. The effects of decommissioning laws on the construction and engineering firms are mentioned. 5 refs.

  11. 30 CFR 285.904 - Can I request a departure from the decommissioning requirements?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... decommissioning requirements? 285.904 Section 285.904 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, REGULATION, AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING... the decommissioning requirements under § 285.103. Decommissioning Applications...

  12. Ekofisk pipelines undergo requalification

    SciTech Connect

    Tangeland, T.G.; Collberg, L.

    1996-09-23

    Requalification of 19 pipelines and 29 risers in the Ekofisk field required new approaches for loads, capacities, and deterioration evaluations and predictions. Requalification is a re-assessment of an installation`s design with changed design parameters so that the facility can continue to operate. In some cases, original design requirements may have been unrealistically conservative. The Ekofisk field experienced seabed subsidence as a result of compaction of the producing formation. A total of 25 pipeline systems with diameters of 6--36 inches now run within the subsidence bowl. The existing pipelines and the risers had to be requalified because of new design conditions. The paper describes Ekofisk subsidence, reasons and regulations for requalification, structural design, materials and corrosion, deterioration mechanisms, subsidence effects, calculation of forces, capacities, accumulated strain, local buckling, and mine lessons learned from the requalification projects.

  13. Recommissioning NPS 30 pipeline

    SciTech Connect

    Saad, Z.A.; O`Rourke, D.J.

    1996-12-31

    This paper will discuss all the steps taken to reclaim an 80 kilometer (50 Mile) NPS 30 pipeline loop, including the project planning, the labor requirements, the techniques utilized to complete the various stages of the project, some of the unique problems encountered, as well as some options that were examined for hydrostatic test leak detection and water treatment. This project was a component of the Trans Mountain, Cdn $30 million, Stage 2 capacity expansion. This component of Stage 2 resulted in an increase of 3,000 m{sup 3}/d (18,909 barrel/d) to the overall pipeline capacity achieving a 36,300 m{sup 3}/d sustainable pipeline pumping capacity (230,000 barrel/d).

  14. 77 FR 19799 - Pipeline Safety: Pipeline Damage Prevention Programs

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-02

    ... the ANPRM on this subject that PHMSA published in the Federal Register on October 29, 2009 (74 FR... April 2, 2012 Part III Department of Transportation Pipeline and Hazardous Materials Safety Administration 49 CFR Parts 196 and 198 Pipeline Safety: Pipeline Damage Prevention Programs; Proposed Rule...

  15. Predictors of Student Persistence in the STEM Pipeline: Activities Outside the Classroom, Parent Aspirations, and Student Self-Beliefs using NELS:88 Data

    NASA Astrophysics Data System (ADS)

    Miller, Joelle A.

    major as students with higher self-beliefs had a decreased odds of choosing a non-STEM major (p<.05, Exp(B)=.988). When all three variables were considered together, self-beliefs were no longer significant (p<.166) but parent aspirations, (p<.0001, Exp(B)=1.034) and activities outside of the classroom (p<.0001, Exp(B)=1.097), both significantly predicted STEM participation. The results of the research inform policy makers in regard to funding decisions and the development of programs, especially ones that occur outside of the school day. The analysis may guide decisions for school administrators on how to influence student retention within the STEM pipeline. The findings add to existing research and provide a better understanding of predictors affecting student persistence in STEM.

  16. Impacts of recent environmental regulations on pipeline systems

    SciTech Connect

    Irion, K.S.

    1995-12-31

    In recent years pipeline facilities have been subjected to an increasing variety of interpretations by state and regional agencies concerning agency jurisdiction over the regulation of environmental activities at breakout tanks, pump stations, and terminals. The focus of agency interpretation is not on the pipelines themselves, but on loading and unloading activities and on auxiliary tankage. Loading and unloading activities can be to truck, railcar or barge. Tanks are used in a variety of pipeline operations. Tanks are used to collect from gathering lines and transport to a refinery. Tanks can be used to gather and offload to a truck, railcar or vessel. Other tanks are receipt for unloading by ship or barge, which is then transferred by pipeline to a refining or distribution facility. Pipelines, like other industries, were regulated solely by a single agency prior to the establishment of the Environmental Protection Agency (EPA). Until recently, pipelines and their connecting tankage were regulated as transportation facilities under the Department of Transportation (DOT). Although the prevention of pollution of surface water by oil and petroleum products is one of the earliest environmental regulations, dating back to 1970, most of the pipeline facilities remained exempt from most environmental regulation by EPA until very recently. Within the last decade, and accelerating within the last five years, pipeline facilities have been increasingly affected by several burgeoning environmental regulations. A summary of the effects and consequences, as well as suggestions for avoiding unnecessary regulation, are presented.

  17. Experimental investigation on the volume reduction of irradiated graphite arising from the decommissioning of KRR-2

    SciTech Connect

    Lee, D.G.; Cho, Y.J.; Yang, H.C.; Lee, K.W.; Jung, C.H.

    2007-07-01

    Graphite has been used as a moderator and reflector of neutrons in more than 100 nuclear power plants as well as many experimental reactors and plutonium production reactors in various countries. Most of the older graphite moderated reactors are already shut down and arc awaiting decommissioning planning and preparation. The graphite waste has different characteristics than other decommissioning waste due to its physical and chemical properties and also because of the presence of tritium and carbon-14. Therefore radioactive graphite dismantling, handling, conditioning and disposal are a common part of the decommissioning activities. A volume reduction of the waste is needed to reduce disposal cost of radioactive waste. However the existing processing technologies are based mostly on the isolation of radioactive graphite from the environment, they are not able to provide for a significant volume reduction. For this reason, the high-temperature thermal treatment process such as an incineration or a pyrolysis is considered as promising technologies, since it provides a substantial volume reduction. Currently, the fluidized bed incineration is considered as efficient technology for the treatment of radioactive graphite waste. In this study, the fluidized bed incineration condition and the radioisotopes behavior were experimentally investigated by using irradiated graphite waste which has arisen from the decommissioning of Korean Research Reactor 2 (KRR-2). (authors)

  18. Technology, safety and costs of decommissioning a reference boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    SciTech Connect

    Konzek, G.J.; Smith, R.I.

    1988-07-01

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies of conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference boiling water reactor (BWR) described in the earlier study; and defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs. This report presents the results of recent PNL studies to provide supporting information in three areas concerning decommissioning of the reference BWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

  19. Decommissioning successes at Rocky Flats Environmental Technology Site

    SciTech Connect

    Crawford, A.C.; Hughes, F.P.; Trice, K.D.; Wolf, H.C.; Wheeler, M.

    1999-07-01

    Building 779, a cluster of 13 buildings located at Rocky Flats Environmental Technology Site (RFETS), was originally constructed in the early 1960s. The building was used to perform research and development associated with the nuclear weapons programs. The primary contaminants were plutonium and uranium, and these contaminants were dispersed throughout the facility. In 1998, Building 779 was selected to be the first plutonium facility at RFETS to be decommissioned. After extensive training, fieldwork was initiated with a single crew of 14 workers. Dismantling of the facility started with the removal and disposition of excess property. Today, thousands of pieces of property have been dispositioned and either recycled or disposed of as radioactive waste. The second facility at RFETS to begin D and D is Building 771. This facility was selected because of its extreme complexity and the desire to accelerate the RFETS closure to 2006. Building 771 is a 200,000-ft{sup 2}, 10-structure, multistory facility with more than 230 glove boxes and 8 miles of plutonium processing piping. Building 771 was used for processing plutonium and actinides between 1953 and 1989. The facility experienced many modifications, substantial variation in operations, and several upsets resulting in radiological contamination over its 40-yr operating history. The most significant event was a major fire in 1957. The 1994 Plutonium Working Group Report on Environmental Safety and Health Vulnerabilities Associated with the Department of Energy's Plutonium Storage determined that Building 771 was the most dangerous building in America. Since the report was issued, a significant quantity of special nuclear material (SNM) has been removed, hydrogen has been vented, and the draining of high- and low-level solutions from tanks has been completed. Although these activities have lowered the risk, numerous complex tasks still remain to take the building to its final end point of a slab. Three major areas of

  20. Infrared thermographic pipeline leak detection systems for pipeline rehabilitation programs

    NASA Astrophysics Data System (ADS)

    Weil, Gary J.

    1995-05-01

    Computerized infrared thermographic pipeline inspection is now a refined and accurate process having been thoroughly proven to be accurate, cost effective, and efficient technology for pipeline rehabilitation programs, during a 10 year development and testing process. The process has been used to test pipelines in chemical plants, water supply systems, steam lines, natural gas pipelines and sewer systems. Its non-contact, non-destructive ability to inspect large areas, from above ground, with 100% coverage and to locate subsurface leaks as well as the additional capability to locate voids and erosion surrounding pipelines, make its testing capabilities unique and highly desirable. This paper details the development of computerized infrared thermographic pipeline testing along with nine case histories illustrating its implementation problems and successes during various rehabilitation programs involving pipelines carrying water, gas, petroleum, and sewage.

  1. Infrared thermographic pipeline leak detection systems for pipeline rehabilitation programs

    NASA Astrophysics Data System (ADS)

    Weil, Gary J.

    1998-03-01

    Computerized infrared thermographic pipeline inspection is now a refined and accurate process having been thoroughly proven to be an accurate, cost effective, and efficient technology for pipeline rehabilitation programs, during a 10 year development and testing process. The process has been used to test pipelines in chemical plants, water supply systems, steam lines, natural gas pipelines and sewer systems. Its non- contact, non-destructive ability to inspect large areas, from above ground, with 100% coverage and to locate subsurface leaks as well as the additional capability to locate voids and erosion areas surrounding pipelines, make its testing capabilities unique and highly desirable. This paper details the development of computerized infrared thermographic pipeline testing along with case histories illustrating its implementation problems and successes during various rehabilitation programs involving pipelines carrying water, gas, petroleum, and sewage.

  2. UQ Pipeline Lorenz Portlet

    SciTech Connect

    2012-08-31

    This is web client software that can help initiate UQ Pipeline jobs on LLNL's LC compute systems and visually shows the status of such jobs in a browser window. The web client interacts with LC's interactive compute nodes using (LLNL) Lorenz REST API to initiate action and obtain status data in JSON format.

  3. Pneumatic freight pipelines

    SciTech Connect

    Weaver, P.B.

    1994-12-31

    There is a great deal of technology and experience in and from the Pneumatic Tube System industry that must be tapped because it is directly and/or indirectly applicable to the Pneumatic Freight Pipeline industry. Otherwise a great deal of time will be spent re-inventing the wheel.

  4. Trans-Alaska pipeline

    SciTech Connect

    Not Available

    1991-07-01

    The Trans-Alaska Pipeline system transports nearly 25 percent of the nation's domestically produced crude oil. Since operations began in 1977, the system has delivered over 8 billion barrels of oil to Port Veldez for shipment. This paper reports that concerns have been raised about whether the system is meeting special engineering design and operations requirements imposed by federal and state regulators. GAO found that the five principal federal and state regulatory agencies have not pursued a systematic, disciplined, and coordinated approach to regulating the Trans-Alaska Pipeline System. Instead, these agencies have relied on the Alyeska Pipeline Service Company, which runs the system, to police itself. It was only after the Exxon Valdez spill and the discovery of corrosion that the regulators began to reevaluate their roles and focus on issues such as whether Alyeska's operating and maintenance procedures meet the pipelines, special engineering design and operating requirements, or whether Alyeska can adequately respond to a large oil spill. In January 1990, the regulators established a joint office to provide more effective oversight of the system. GAO believes that central leadership and a secured funding sources may help ensure that this office provides adequate oversight.

  5. The JWST Calibration Pipeline

    NASA Astrophysics Data System (ADS)

    Chen, Christine; Muzerolle, James; Dixon, William Van Dyke; Izela Diaz, Rosa; Bushouse, Howard A.

    2015-01-01

    The James Webb Space Telescope will launch in 2018 and carry four science instruments that will observe the sky at 0.7 - 29 micron: the Near Infrared Camera (NIRCam), the Near Infrared Imager and Slitless Spectrograph (NIRISS), the Near Infrared Spectrograph (NIRSpec), and the Mid Infrared Instrument (MIRI). The Space Telescope Science Institute (STScI) is currently building a data reduction pipeline that will provide not only basic calibrated data but also higher level science products. All of the JWST detectors will be operated in non-destructive readout mode. Therefore, the first step in the pipeline will be to calculate the slopes of indivudal non-destructive readout ramps or integrations. The next step will be to generate calibrated slope images that are represent the basic calibrated data. The final step will be to combine data taken across multiple integrations and exposure. For the direct imaging and integral field spectroscopy modes, the pipeline will produce calibrated mosaicks. For the coronagraphic modes, the pipeline will produce contrast curves and PSF subtracted images.

  6. Orchestrator Telemetry Processing Pipeline

    NASA Technical Reports Server (NTRS)

    Powell, Mark; Mittman, David; Joswig, Joseph; Crockett, Thomas; Norris, Jeffrey

    2008-01-01

    Orchestrator is a software application infrastructure for telemetry monitoring, logging, processing, and distribution. The architecture has been applied to support operations of a variety of planetary rovers. Built in Java with the Eclipse Rich Client Platform, Orchestrator can run on most commonly used operating systems. The pipeline supports configurable parallel processing that can significantly reduce the time needed to process a large volume of data products. Processors in the pipeline implement a simple Java interface and declare their required input from upstream processors. Orchestrator is programmatically constructed by specifying a list of Java processor classes that are initiated at runtime to form the pipeline. Input dependencies are checked at runtime. Fault tolerance can be configured to attempt continuation of processing in the event of an error or failed input dependency if possible, or to abort further processing when an error is detected. This innovation also provides support for Java Message Service broadcasts of telemetry objects to clients and provides a file system and relational database logging of telemetry. Orchestrator supports remote monitoring and control of the pipeline using browser-based JMX controls and provides several integration paths for pre-compiled legacy data processors. At the time of this reporting, the Orchestrator architecture has been used by four NASA customers to build telemetry pipelines to support field operations. Example applications include high-volume stereo image capture and processing, simultaneous data monitoring and logging from multiple vehicles. Example telemetry processors used in field test operations support include vehicle position, attitude, articulation, GPS location, power, and stereo images.

  7. Offshore pipeline failures. Master's thesis

    SciTech Connect

    Woodson, R.D.

    1990-12-01

    An overview of current concerns in the regulation of offshore pipelines is presented along with tabulated summaries of pipeline failure causes, failure prevention techniques, and pipeline monitoring and early intervention techniques. A database of over 1000 offshore pipeline failures in the Gulf of Mexico Offshore waters has been compiled from combined records of the Department of Transportation Office of pipeline Safety, U.S. Coast Guard National Response Center, and the Department of Interior Minerals Management Service. The data has been analyzed to identify trends and initial recommendations for future data collection have been suggested.

  8. A review of decommissioning considerations for new reactors

    SciTech Connect

    Devgun, J.S.Ph.D.

    2008-07-01

    At a time of 'nuclear renaissance' when the focus is on advanced reactor designs and construction, it is easy to overlook the decommissioning considerations because such a stage in the life of the new reactors will be some sixty years down the road. Yet, one of the lessons learned from major decommissioning projects has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Hence, the time to examine what decommissioning considerations should be taken into account is right from the design stage with regular updates of the decommissioning strategy and plans throughout the life cycle of the reactor. Designing D and D into the new reactor designs is necessary to ensure that the tail end costs of the nuclear power are manageable. Such considerations during the design stage will facilitate a more cost-effective, safe and timely decommissioning of the facility when a reactor is eventually retired. This paper examines the current regulatory and industry design guidance for the new reactors with respect to the decommissioning issues and provides a review of the design considerations that can help optimize the reactor designs for the eventual decommissioning. (authors)

  9. Decommissioning considerations at a time of nuclear renaissance

    SciTech Connect

    Devgun, Jas S.

    2007-07-01

    At a time of renaissance in the nuclear power industry, when it is estimated that anywhere between 60 to 130 new power reactors may be built worldwide over the next 15 years, why should we focus on decommissioning? Yet it is precisely the time to examine what decommissioning considerations should be taken into account as the industry proceeds with developing final designs for new reactors and the construction on the new build begins. One of the lessons learned from decommissioning of existing reactors has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Even though decommissioning may be sixty years down the road from the time they go on line, eventually all reactors will be decommissioned. It is only prudent that new designs be optimized for eventual decommissioning, along with the other major considerations. The overall objective in this regard is that when the time comes for decommissioning, it can be completed in shorter time frames, with minimum generation of radioactive waste, and with better radiological safety. This will ensure that the tail end costs of the power reactors are manageable and that the public confidence in the nuclear power is sustained through the renaissance and beyond. (author)

  10. 78 FR 64028 - Decommissioning of Nuclear Power Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-25

    ... Register on February 14, 2012 (77 FR 8902), for a 60-day public comment period. The public comment period... COMMISSION Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION... regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method...

  11. Decommissioning: Nuclear Power's Missing Link. Worldwatch Paper 69.

    ERIC Educational Resources Information Center

    Pollock, Cynthia

    The processes and associated dilemmas of nuclear power plant decommissioning are reviewed in this publication. Decommissioning involves the clearing up and disposal of a retired nuclear plant and its equipment of such a way as to safeguard the public from the dangers of radioactivity. Related problem areas are identified and include: (1) closure…

  12. 10 CFR 72.130 - Criteria for decommissioning.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for decommissioning. 72.130 Section 72.130 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT... Criteria § 72.130 Criteria for decommissioning. The ISFSI or MRS must be designed for...

  13. The NOAO Pipeline Data Manager

    NASA Astrophysics Data System (ADS)

    Hiriart, R.; Valdes, F.; Pierfederici, F.; Smith, C.; Miller, M.

    2004-07-01

    The Data Manager for NOAO Pipeline system is a set of interrelated components that are being developed to fulfill the pipeline system data needs. It includes: (1) management of calibration files (flat, bias, bad pixel mask and xtalk calibration data.); (2) management of the pipeline stages' configuration parameters; and (3) management of the pipeline processing historic information, for each of the data products generated by the pipeline. The Data Manager components uses a distributed, CORBA based architecture, providing a flexible and extensible object oriented framework, capable of accommodating the present and future pipeline data requirements. The Data Manager communicates with the pipeline modules, with internal and external databases, and with other NOAO systems such as the NOAO Archive and the NOAO Data Transport System.

  14. Decontamination and decommissioning surveillance and maintenance report for FY 1991. Environmental Restoration Program

    SciTech Connect

    Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01

    The Decontamination and Decommissioning (D&D) Program has three distinct phases: (1) surveillance and maintenance (S&M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D&D is devoted to S&M at each of the sites. Our S&M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S&M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  15. The odyssey of marine pharmaceuticals: a current pipeline perspective.

    PubMed

    Mayer, Alejandro M S; Glaser, Keith B; Cuevas, Carmen; Jacobs, Robert S; Kem, William; Little, R Daniel; McIntosh, J Michael; Newman, David J; Potts, Barbara C; Shuster, Dale E

    2010-06-01

    The global marine pharmaceutical pipeline consists of three Food and Drug Administration (FDA) approved drugs, one EU registered drug, 13 natural products (or derivatives thereof) in different phases of the clinical pipeline and a large number of marine chemicals in the preclinical pipeline. In the United States there are three FDA approved marine-derived drugs, namely cytarabine (Cytosar-U((R)), Depocyt((R))), vidarabine (Vira-A((R))) and ziconotide (Prialt((R))). The current clinical pipeline includes 13 marine-derived compounds that are either in Phase I, Phase II or Phase III clinical trials. Several key Phase III studies are ongoing and there are seven marine-derived compounds now in Phase II trials. The preclinical pipeline continues to supply several hundred novel marine compounds every year and those continue to feed the clinical pipeline with potentially valuable compounds. From a global perspective the marine pharmaceutical pipeline remains very active, and now has sufficient momentum to deliver several additional compounds to the marketplace in the near future; this review provides a current view of the pipeline.

  16. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  17. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  18. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

    SciTech Connect

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.; McDuffie, P.N.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review and reevaluation of the 1978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.

  19. Instrumented Pipeline Initiative

    SciTech Connect

    Thomas Piro; Michael Ream

    2010-07-31

    This report summarizes technical progress achieved during the cooperative agreement between Concurrent Technologies Corporation (CTC) and U.S. Department of Energy to address the need for a for low-cost monitoring and inspection sensor system as identified in the Department of Energy (DOE) National Gas Infrastructure Research & Development (R&D) Delivery Reliability Program Roadmap.. The Instrumented Pipeline Initiative (IPI) achieved the objective by researching technologies for the monitoring of pipeline delivery integrity, through a ubiquitous network of sensors and controllers to detect and diagnose incipient defects, leaks, and failures. This report is organized by tasks as detailed in the Statement of Project Objectives (SOPO). The sections all state the objective and approach before detailing results of work.

  20. Sludge pipeline design.

    PubMed

    Slatter, P T

    2001-01-01

    The need for the design engineer to have a sound basis for designing sludge pumping and pipelining plant is becoming more critical. This paper examines both a traditional text-book approach and one of the latest approaches from the literature, and compares them with experimental data. The pipelining problem can be divided into the following main areas; rheological characterisation, laminar, transitional and turbulent flow and each is addressed in turn. Experimental data for a digested sludge tested in large pipes is analysed and compared with the two different theoretical approaches. Discussion is centred on the differences between the two methods and the degree of agreement with the data. It is concluded that the new approach has merit and can be used for practical design.

  1. Pipeline corridors through wetlands

    SciTech Connect

    Zimmerman, R.E.; Wilkey, P.L.; Isaacson, H.R.

    1992-12-01

    This paper presents preliminary findings from six vegetational surveys of gas pipeline rights-of-way (ROW) through wetlands and quantifies the impacts of a 20-year-old pipeline ROW through a boreal forest wetland. Six sites of various ages were surveyed in ecosystems ranging from coastal marsh to forested wetland. At all sites except one, both the number and the percentage of wetland species on the Row approximated or exceeded those in the adjacent natural area. The boreal forest study showed that (1) adjacent natural wetland areas were not altered in type; (2) water sheet flow restriction had been reversed by nature; (3) no nonnative plant species invaded the natural area; (4) three-quarters of the ROW area was a wetland, and (5) the ROW increased diversity.

  2. Pipeline corridors through wetlands

    SciTech Connect

    Zimmerman, R.E.; Wilkey, P.L. ); Isaacson, H.R. )

    1992-01-01

    This paper presents preliminary findings from six vegetational surveys of gas pipeline rights-of-way (ROW) through wetlands and quantifies the impacts of a 20-year-old pipeline ROW through a boreal forest wetland. Six sites of various ages were surveyed in ecosystems ranging from coastal marsh to forested wetland. At all sites except one, both the number and the percentage of wetland species on the Row approximated or exceeded those in the adjacent natural area. The boreal forest study showed that (1) adjacent natural wetland areas were not altered in type; (2) water sheet flow restriction had been reversed by nature; (3) no nonnative plant species invaded the natural area; (4) three-quarters of the ROW area was a wetland, and (5) the ROW increased diversity.

  3. Sludge pipeline design.

    PubMed

    Slatter, P T

    2001-01-01

    The need for the design engineer to have a sound basis for designing sludge pumping and pipelining plant is becoming more critical. This paper examines both a traditional text-book approach and one of the latest approaches from the literature, and compares them with experimental data. The pipelining problem can be divided into the following main areas; rheological characterisation, laminar, transitional and turbulent flow and each is addressed in turn. Experimental data for a digested sludge tested in large pipes is analysed and compared with the two different theoretical approaches. Discussion is centred on the differences between the two methods and the degree of agreement with the data. It is concluded that the new approach has merit and can be used for practical design. PMID:11794641

  4. Leak detection on petroleum pipelines

    SciTech Connect

    Poynter, W.G.

    1995-12-01

    Accident statitics clearly show that pipelines are the safest method for transporting hydrocarbon fluids compared to trucking, rail or marine transportation. Even so, leaks and spills do occasionally happen and can be (1) very costly in terms of product loss and clean up, and (2) hazardous to life, property and the environment. The pipeline industry recognizes its responsibility to be proactive in technological advancements which promote public safety, and many pipeline operators either already have or are planning to install real-time methods for determining when leak occur. The intent is to detect leaks as soon as possible to permit the operator to shut down a pipeline and minimize the amount of stock loss and potential hazard to the public. Some federal and state regulations require some form of leak detection on pipelines which transport hazardous fluids through populated and otherwise sensitive areas. There are three basic methods for monitoring pipeline systems for leaks: (1) EXS (external sensors) which use acoustical devices or hydrocarbon sensors which may be buried with the pipe or placed at critical above ground locations along the path of the pipeline; (2) VIVO (volume in/volume out) which relies on volumetric measurement and comparison of everything which enters a pipeline system with everything that leaves the system; and (3) PPA (Pressure Point Analysis) is a dynamic method for monitoring the energy balance on a pipeline as represented by pressure and velocity readings at various points in the pipeline system. These systems are discussed.

  5. 78 FR 70623 - Pipeline Safety: Meeting of the Gas Pipeline Advisory Committee and the Liquid Pipeline Advisory...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-26

    ... published on April 11, 2000, (65 FR 19477-78) or you may visit http://docketsinfo.dot.gov . Docket: For... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Meeting of the Gas Pipeline Advisory Committee and the Liquid Pipeline Advisory Committee AGENCY: Pipeline and Hazardous...

  6. An analytical approach to γ-ray self-shielding effects for radioactive bodies encountered nuclear decommissioning scenarios.

    PubMed

    Gamage, K A A; Joyce, M J

    2011-10-01

    A novel analytical approach is described that accounts for self-shielding of γ radiation in decommissioning scenarios. The approach is developed with plutonium-239, cobalt-60 and caesium-137 as examples; stainless steel and concrete have been chosen as the media for cobalt-60 and caesium-137, respectively. The analytical methods have been compared MCNPX 2.6.0 simulations. A simple, linear correction factor relates the analytical results and the simulated estimates. This has the potential to greatly simplify the estimation of self-shielding effects in decommissioning activities. PMID:21723136

  7. ALMA Pipeline Heuristics

    NASA Astrophysics Data System (ADS)

    Lightfoot, J.; Wyrowski, F.; Muders, D.; Boone, F.; Davis, L.; Shepherd, D.; Wilson, C.

    2006-07-01

    The ALMA (Atacama Large Millimeter Array) Pipeline Heuristics system is being developed to automatically reduce data taken with the standard observing modes. The goal is to make ALMA user-friendly to astronomers who are not experts in radio interferometry. The Pipeline Heuristics system must capture the expert knowledge required to provide data products that can be used without further processing. Observing modes to be processed by the system include single field interferometry, mosaics and single dish `on-the-fly' maps, and combinations of these modes. The data will be produced by the main ALMA array, the ALMA Compact Array (ACA) and single dish antennas. The Pipeline Heuristics system is being developed as a set of Python scripts. For interferometry these use as data processing engines the CASA/AIPS++ libraries and their bindings as CORBA objects within the ALMA Common Software (ACS). Initial development has used VLA and Plateau de Bure data sets to build and test a heuristic script capable of reducing single field data. In this paper we describe the reduction datapath and the algorithms used at each stage. Test results are presented. The path for future development is outlined.

  8. The MIS Pipeline Toolkit

    NASA Astrophysics Data System (ADS)

    Teuben, Peter J.; Pound, M. W.; Storm, S.; Mundy, L. G.; Salter, D. M.; Lee, K.; Kwon, W.; Fernandez Lopez, M.; Plunkett, A.

    2013-01-01

    A pipeline toolkit was developed to help organizing, reducing and analyzing a large number of near-identical datasets. This is a very general problem, for which many different solutions have been implemented. In this poster we present one such solution that lends itself to users of the Unix command line, using the Unix "make" utility, and adapts itself easily to observational as well as theoretical projects. Two examples are given, one from the CARMA CLASSy survey, and another from a simulated kinematic survey of early galaxy forming disks. The CLASSy survey (discussed in more detail in three accompanying posters) consists of 5 different star forming regions, observed with CARMA, each containing roughly 10-20 datasets in continuum and 3 different molecular lines, that need to be combined in final data cubes and maps. The strength of such a pipeline toolkit shows itself as new data are accumulated, the data reduction steps are improved and easily re-applied to previously taken data. For this we employed a master script that was run nightly, and collaborators submitted improved script and/or pipeline parameters that control these scripts. MIS is freely available for download.

  9. The use of chemical gel for decontamination during decommissioning of nuclear facilities

    NASA Astrophysics Data System (ADS)

    Gurau, Daniela; Deju, Radu

    2015-01-01

    A technical research study was developed for testing the decontamination using chemical gels. The study was realized for different type of samples, systems often encountered in the VVR-S nuclear research reactor from Magurele-Romania. The results obtained in the study have demonstrated that the decontamination gels could be an efficient way to reduce or to eliminate the surface contamination of buildings or equipment's, minimizing the potential for spreading contamination during decommissioning activities.

  10. Decommissioning and Demolition of a Redundant UK Research Facility at AWE Aldermaston - 12453

    SciTech Connect

    Pritchard, Paul

    2012-07-01

    The redundant two-storey brick built research facility on the AWE Site at Aldermaston, UK is in the closing stages of decommissioning and demolition. The facility was used for a variety of purposes up to 1995 predominately involving the use of alpha-emitting isotopes. The two main areas of alpha-based contamination have been decommissioned with the removal of hot -boxes and fume cupboards on the ground floor and HEPA filter units and ventilation equipment on the first floor. Many of these activities were undertaken using both airline fed suits, (supplied via a free standing mobile unit), and full face respirators. Asbestos materials were located and cleared from the first floor by specialist contractor. All sections of active drain running from the building to the site active effluent disposal system were removed early in the program using established techniques with specialist monitoring equipment used to provide confidence in the data required for disposal of the decommissioning debris. In particular a dedicated High Resolution Gamma Spectrometer (radioactive materials scanning unit) was utilized to categorise waste drums and wrapped packages. The building has been decommissioned and the monitoring and sampling of the structure was completed in November 2011 - the results demonstrating that the building was clear of contamination in accordance with UK clearance and exemption requirements. The demolition plan was developed and implemented in December with site excavation of foundations and site clearance currently ongoing in preparation for final site backfill activities and project close. A number of useful lessons have been learnt during the operations and are set out at the rear of the main text. (authors)

  11. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  12. 26 CFR 1.468A-4T - Treatment of nuclear decommissioning fund (temporary).

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Treatment of nuclear decommissioning fund...-4T Treatment of nuclear decommissioning fund (temporary). (a) In general. A nuclear decommissioning... income earned by the assets of the nuclear decommissioning fund. (b) Modified gross income. For...

  13. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  14. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  15. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  16. Incorporation of pollution prevention and waste minimization practices during the decommissioning of Building 310 at Argonne National Laboratory-East

    SciTech Connect

    Mezaraups, J.; Krstich, M.A.; Yerace, P.J.; Gresalfi, M.J.

    1997-10-01

    The decommissioning of radiologically contaminated buildings at Department of Energy (DOE) sites provides a major opportunity to include pollution prevention and waste minimization (P2/WMin) practices to minimize waste using authorized release opportunities, and recycle and reuse (R2) activities on a complex-wide basis. The ``P2/WMin Users Guide for Decommissioning Projects`` (a.k.a. Users Guide or Guide) will be used to incorporate P2/WMin practices into the decommissioning and dismantlement (D and D) of Building 310 retention tanks at Argonne National Laboratory-East (ANL-E). The Building 310 service floor retention-tank facility contains ten isolated retention tanks that served to store excess radioactive liquids generated during process operations. The building consists of three rooms containing three tanks each and a larger room containing one tank. Due to a concern that the deteriorating facility could expose personnel working in the vicinity to radioactive contamination, a decision was made to decommission the building. The Users Guide, a document prepared under the auspices of the Office of Pollution Prevention (EM-77), details a step-by-step approach for incorporating P2/WMin options into a project`s documentation and subsequent decommissioning activities. It is a compilation of lessons learned and strategic P2/WMin initiatives from across the DOE complex. The benefits derived from using P2/WMin initiatives for the D and D of Building 310 include an accelerated decommissioning schedule, reduction in health risk, and the elimination of six release sites from the DOE EM-40 list. The benefits derived from implementation of P2/WMin initiatives into this project include cost savings, reduction in long-term liability, and deployment of technologies without impacting scope or schedule for the project.

  17. DECOMMISSIONING OF A CAESIUM-137 SEALED SOURCE PRODUCTION FACILITY

    SciTech Connect

    Murray, A.; Abbott, H.

    2003-02-27

    Amersham owns a former Caesium-137 sealed source production facility. They commissioned RWE NUKEM to carry out an Option Study to determine a strategy for the management of this facility and then the subsequent decommissioning of it. The decommissioning was carried out in two sequential phases. Firstly robotic decommissioning followed by a phase of manual decommissioning. This paper describes the remote equipment designed built and operated, the robotic and manual decommissioning operations performed, the Safety Management arrangements and summarizes the lessons learned. Using the equipment described the facility was dismantled and decontaminated robotically. Some 2300kg of Intermediate Level Waste containing in the order of 4000Ci were removed robotically from the facility. Ambient dose rates were reduced from 100's of R per hour {gamma} to 100's of mR per hour {gamma}. The Telerobotic System was then removed to allow man access to complete the decommissioning. Manual decommissioning reduced ambient dose rates further to less than 1mR per hour {gamma} and loose contamination levels to less than 0.25Bq/cm2. This allowed access to the facility without respiratory protection.

  18. 27 CFR 19.187 - Pipelines.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2012-04-01 2012-04-01 false Pipelines. 19.187 Section... Package Scale and Pipeline Requirements § 19.187 Pipelines. All pipelines, including flexible hoses, that... TTB officer may approve pipelines that cannot be readily examined if they pose no jeopardy to...

  19. 27 CFR 19.187 - Pipelines.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2011-04-01 2011-04-01 false Pipelines. 19.187 Section... Package Scale and Pipeline Requirements § 19.187 Pipelines. All pipelines, including flexible hoses, that... TTB officer may approve pipelines that cannot be readily examined if they pose no jeopardy to...

  20. 27 CFR 19.187 - Pipelines.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2014-04-01 2014-04-01 false Pipelines. 19.187 Section... Package Scale and Pipeline Requirements § 19.187 Pipelines. All pipelines, including flexible hoses, that... TTB officer may approve pipelines that cannot be readily examined if they pose no jeopardy to...

  1. 27 CFR 19.187 - Pipelines.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2013-04-01 2013-04-01 false Pipelines. 19.187 Section... Package Scale and Pipeline Requirements § 19.187 Pipelines. All pipelines, including flexible hoses, that... TTB officer may approve pipelines that cannot be readily examined if they pose no jeopardy to...

  2. Sensor Network Demonstration for In Situ Decommissioning - 13332

    SciTech Connect

    Lagos, L.; Varona, J.; Awwad, A.; Rivera, J.; McGill, J.

    2013-07-01

    individual sensors would be immobilized during the grout pouring activities, a set of nine sensor racks were designed. The 270 sensors provided by Idaho National Laboratory (INL), Mississippi State University (MSU), University of Houston (UH), and University of South Carolina (USC) were secured to these racks based on predetermined locations. Once sensor racks were installed inside the test cube, connected and debugged, approximately 32 cubic yards of special grout material was used to entomb the sensors. MSU provided and demonstrated four types of fiber loop ring-down (FLR) sensors for detection of water, temperature, cracks, and movement of fluids. INL provided and demonstrated time differenced 3D electrical resistivity tomography (ERT), advanced tensiometers for moisture content, and thermocouples for temperature measurements. University of Houston provided smart aggregate (SA) sensors, which detect crack severity and water presence. An additional UH sensor system demonstrated was a Fiber Bragg Grating (FBG) fiber optic system measuring strain, presence of water, and temperature. USC provided a system which measured acoustic emissions during cracking, as well as temperature and pH sensors. All systems were connected to a Sensor Remote Access System (SRAS) data networking and collection system designed, developed and provided by FIU. The purpose of SRAS was to collect and allow download of the raw sensor data from all the sensor system, as well as allow upload of the processed data and any analysis reports and graphs. All this information was made available to the research teams via the Deactivation and Decommissioning Knowledge Management and Information Tool (D and D KM-IT). As a current research effort, FIU is performing an energy analysis, and transferring several sensor systems to a Photovoltaic (PV) System to continuously monitor energy consumption parameters and overall power demands. Also, One final component of this research is focusing on developing an integrated

  3. Evaluation of decommissioning alternatives for the Pilot Plant Complex, Aberdeen Proving Ground

    SciTech Connect

    Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report presents an evaluation of four decommissioning alternatives for the Pilot Plant Complex (PPC), an inactive chemical weapons research, development, and production facility consisting of nine buildings located in the Edgewood Area of the Aberdeen Proving Ground in Maryland. Decommissioning the PPC involves six steps: (1) assessing existing conditions; (2) dismantling the aboveground portions of the buildings (including the floor slabs, paved roads, and sidewalks within the PPC); (3) reducing the size of the demolition debris and sealing the debris in containers for later testing and evaluation; (4) testing and evaluating the debris; (5) conducting site operation and maintenance activities; and (6) recycling or disposing of the debris with or without prior treatment, as appropriate.

  4. Safety analysis factors for environmental restoration and decontamination and decommissioning

    SciTech Connect

    Ellingson, D.R.

    1993-04-01

    Environmental restoration (ER) and facility decontamination/decommissioning (D&D) operations can be grouped into two general categories. ``Nonstationary cleanup`` or simply ``cleanup`` activities are where the operation must relocate to the site of new contaminated material at the completion of each task (i.e., the operation moves to the contaminated material). ``Stationary production`` or simply ``production`` activities are where the contaminated material is moved to a centralized location (i.e., the contaminated material is moved to the operation) for analysis, sorting, treatment, storage, and disposal. This paper addresses the issue of nonstationary cleanup design. The following are the specific assigned action items: Collect and compile a list of special safety-related ER/D&D design factors, especially ones that don`t follow DOE Order 6430.1A requirements. Develop proposal of what makes sense to recommend to designers; especially consider recommendations for short-term projects. Present proposal at the January meeting. To achieve the action items, applicable US Department of Energy (DOE) design requirements, and cleanup operations and differences from production activities are reviewed and summarized; basic safety requirements influencing design are summarized; and finally, approaches, considerations, and methods for safe, cost-effective design of cleanup activities are discussed.

  5. Decontamination, decommissioning, and vendor advertorial issue, 2008

    SciTech Connect

    Agnihotri, Newal

    2008-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the best TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.

  6. Dust in active galactic nuclei. Mid-infrared T-ReCS/Gemini spectra using the new RedCan pipeline

    NASA Astrophysics Data System (ADS)

    González-Martín, O.; Rodríguez-Espinosa, J. M.; Díaz-Santos, T.; Packham, C.; Alonso-Herrero, A.; Esquej, P.; Ramos Almeida, C.; Mason, R.; Telesco, C.

    2013-05-01

    Context. The unified model of active galactic nuclei (AGN) claims that the properties of AGN depend on the viewing angle of the observer with respect to a toroidal distribution of dust surrounding the nucleus. Both the mid-infrared (MIR) attenuation and continuum luminosity are expected to be related to dust associated with the torus. Therefore, isolating the nuclear component is essential for studying the MIR emission of AGN. Aims: This work is aimed at studying the MIR emission of AGN with the highest spatial resolution available to date, isolating its contribution from extended emission. We would like to address three fundamental questions: (1) how important is the AGN contribution to the MIR spectrum; (2) where dust attenuation arises; and (3) how does spatial resolution affect these issues. Methods: We compiled all the T-ReCS spectra (Gemini Observatory) available in the N-band for 22 AGN: 5 Type-1 and 17 Type-2 AGN. The high angular resolution of the T-ReCS spectra allowed us to probe physical regions of 57 pc (median). We used a novel pipeline called RedCan capable of producing flux- and wavelength-calibrated spectra for the CanariCam (GTC) and T-ReCS (Gemini) instruments. We measured the fine-structure [S IV] at 10.5 μm and the PAH at 11.3 μm line strengths, together with the silicate absorption/emission features. We also compiled Spitzer/IRS spectra to understand how spatial resolution influences the results. We complemented our sample with the results of 19 VISIR/VLT spectra (Paranal Observatory) and 20 nearby, highly obscured AGN (NH > 1.5 × 1024 cm-2) Spitzer spectra. Results: The 11.3 μm PAH feature is only clearly detected in the nuclear spectra of two AGN, while it is more common in the Spitzer data. For those two objects, the AGN emission in NGC 7130 accounts for more than 80% of the MIR continuum at 12 μm, while in the case of NGC 1808 the AGN does not dominate the MIR emission. This is confirmed by the correlation between the MIR and X

  7. Lessons Learned Following the Successful Decommissioning of a Reaction Vessel Containing Lime Sludge and Technetium-99

    SciTech Connect

    Dawson, P. M.; Watson, D. D.; Hylko, J. M.

    2002-02-25

    This paper documents how WESKEM, LLC utilized available source term information, integrated safety management, and associated project controls to safely decommission a reaction vessel and repackage sludge containing various Resource Conservation and Recovery Act constituents and technetium-99 (Tc-99). The decommissioning activities were segmented into five separate stages, allowing the project team to control work related decisions based on their knowledge, experience, expertise, and field observations. The information and experience gained from each previous stage and rehearsals contributed to modifying subsequent entries, further emphasizing the importance of developing hold points and incorporating lessons learned. The hold points and lessons learned, such as performing detailed personal protective equipment (PPE) inspections during sizing and repackaging operations, and using foam-type piping insulation to prevent workers from cutting or puncturing their PPE on sharp edge s or small shards generated during sizing operations, minimized direct contact with the Tc-99. To prevent the spread of contamination, the decommissioning activities were performed inside a containment enclosure connected to negative air machines. After performing over 235 individual entries totaling over 285 project hours, only one first aid was recorded during this five-stage project.

  8. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    SciTech Connect

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-11-09

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  9. ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

    SciTech Connect

    Farfan, E.

    2009-09-30

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  10. 76 FR 70953 - Pipeline Safety: Safety of Gas Transmission Pipelines

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-16

    ... August 25, 2011, (76 FR 53086) PHMSA published in the Federal Register an Advance Notice of Proposed... by email at mike.israni@dot.gov . SUPPLEMENTARY INFORMATION: On August 25, 2011, (76 FR 53086), PHMSA...: Safety of Gas Transmission Pipelines AGENCY: Pipeline and Hazardous Materials Safety...

  11. The bacterial proteogenomic pipeline

    PubMed Central

    2014-01-01

    Background Proteogenomics combines the cutting-edge methods from genomics and proteomics. While it has become cheap to sequence whole genomes, the correct annotation of protein coding regions in the genome is still tedious and error prone. Mass spectrometry on the other hand relies on good characterizations of proteins derived from the genome, but can also be used to help improving the annotation of genomes or find species specific peptides. Additionally, proteomics is widely used to find evidence for differential expression of proteins under different conditions, e.g. growth conditions for bacteria. The concept of proteogenomics is not altogether new, in-house scripts are used by different labs and some special tools for eukaryotic and human analyses are available. Results The Bacterial Proteogenomic Pipeline, which is completely written in Java, alleviates the conducting of proteogenomic analyses of bacteria. From a given genome sequence, a naïve six frame translation is performed and, if desired, a decoy database generated. This database is used to identify MS/MS spectra by common peptide identification algorithms. After combination of the search results and optional flagging for different experimental conditions, the results can be browsed and further inspected. In particular, for each peptide the number of identifications for each condition and the positions in the corresponding protein sequences are shown. Intermediate and final results can be exported into GFF3 format for visualization in common genome browsers. Conclusions To facilitate proteogenomics analyses the Bacterial Proteogenomic Pipeline is a set of comprehensive tools running on common desktop computers, written in Java and thus platform independent. The pipeline allows integrating peptide identifications from various algorithms and emphasizes the visualization of spectral counts from different experimental conditions. PMID:25521444

  12. Biotech pipeline: Bottleneck ahead

    SciTech Connect

    Gibbons, A.

    1991-10-18

    A vast array of new genetically engineered drugs are heading for market - but an FDA backlog is holding them up. Patients may have to wait far longer than the biotech enthusiasts suggest before they reap the benefits of those new drugs. There is little hope the FDA will get the money it needs to do the job. The agency's pipeline is clogged with at least 58 monoclonal antibody-based drugs at all stages of testing to diagnose and treat a wide range of diseases, including a half-dozen cancers, diabetes, and sepsis.

  13. Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

    SciTech Connect

    Salazar, M.; Elder, J.

    1992-08-01

    The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program.

  14. The Decommissioning of the Trino Nuclear Power Plant

    SciTech Connect

    Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

    2002-02-27

    Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise utilizes the full range of

  15. Application of Robotics in Decommissioning and Decontamination - 12536

    SciTech Connect

    Banford, Anthony; Kuo, Jeffrey A.; Bowen, R.A.; Szilagyi, Andrew; Kirk, Paula

    2012-07-01

    Decommissioning and dismantling of nuclear facilities is a significant challenge worldwide and one which is growing in size as more plants reach the end of their operational lives. The strategy chosen for individual projects varies from the hands-on approach with significant manual intervention using traditional demolition equipment at one extreme to bespoke highly engineered robotic solutions at the other. The degree of manual intervention is limited by the hazards and risks involved, and in some plants are unacceptable. Robotic remote engineering is often viewed as more expensive and less reliable than manual approaches, with significant lead times and capital expenditure. However, advances in robotics and automation in other industries offer potential benefits for future decommissioning activities, with the high probability of reducing worker exposure and other safety risks as well as reducing the schedule and costs required to complete these activities. Some nuclear decommissioning tasks and facility environments are so hazardous that they can only be accomplished by exclusive use of robotic and remote intervention. Less hazardous tasks can be accomplished by manual intervention and the use of PPE. However, PPE greatly decreases worker productivity and still exposes the worker to both risk and dose making remote operation preferable to achieve ALARP. Before remote operations can be widely accepted and deployed, there are some economic and technological challenges that must be addressed. These challenges will require long term investment commitments in order for technology to be: - Specifically developed for nuclear applications; - At a sufficient TRL for practical deployment; - Readily available as a COTS. Tremendous opportunities exist to reduce cost and schedule and improve safety in D and D activities through the use of robotic and/or tele-operated systems. - Increasing the level of remote intervention reduces the risk and dose to an operator. Better

  16. Desiccant drying of gas pipelines

    SciTech Connect

    LaCasse, G.A.; Ingvordsen, T.

    1988-09-01

    Prevention of hydrates buildup and corrosion in gas pipelines after hydrostatic testing is increasingly important to those in the gas industry. This paper outlines a dry air method used in Denmark for drying gas pipelines. The psychrometric principles, drying method, and humidity measurements are described.

  17. Alaska Pipeline Insulation

    NASA Technical Reports Server (NTRS)

    1979-01-01

    Crude oil moving through the 800-mile Trans-Alaska Pipeline must be kept at a relatively high temperature, about 180 degrees Fahrenheit, to maintain the fluidity of the oil. In Arctic weather, that demands highly effective insulation. General Electric Co.'s Space Division, Valley Forge, Pennsylvania, provided it with a spinoff product called Therm-O-Trol. Shown being installed on the pipeline, Therm-O-Trol is a metal-bonded polyurethane foam especially formulated for Arctic insulation. A second GE spinoff product, Therm-O-Case, solved a related problem involved in bringing hot crude oil from 2,000-foot-deep wells to the surface without transferring oil heat to the surrounding permafrost soil; heat transfer could melt the frozen terrain and cause dislocations that might destroy expensive well casings. Therm-O-Case is a double-walled oil well casing with multi-layered insulation which provides an effective barrier to heat transfer. Therm-O-Trol and Therm-O-Case are members of a family of insulating products which stemmed from technology developed by GE Space Division in heat transferlthermal control work on Gemini, Apollo and other NASA programs.

  18. The LOFAR Transients Pipeline

    NASA Astrophysics Data System (ADS)

    Swinbank, John D.; Staley, Tim D.; Molenaar, Gijs J.; Rol, Evert; Rowlinson, Antonia; Scheers, Bart; Spreeuw, Hanno; Bell, Martin E.; Broderick, Jess W.; Carbone, Dario; Garsden, Hugh; van der Horst, Alexander J.; Law, Casey J.; Wise, Michael; Breton, Rene P.; Cendes, Yvette; Corbel, Stéphane; Eislöffel, Jochen; Falcke, Heino; Fender, Rob; Grießmeier, Jean-Mathias; Hessels, Jason W. T.; Stappers, Benjamin W.; Stewart, Adam J.; Wijers, Ralph A. M. J.; Wijnands, Rudy; Zarka, Philippe

    2015-06-01

    Current and future astronomical survey facilities provide a remarkably rich opportunity for transient astronomy, combining unprecedented fields of view with high sensitivity and the ability to access previously unexplored wavelength regimes. This is particularly true of LOFAR, a recently-commissioned, low-frequency radio interferometer, based in the Netherlands and with stations across Europe. The identification of and response to transients is one of LOFAR's key science goals. However, the large data volumes which LOFAR produces, combined with the scientific requirement for rapid response, make automation essential. To support this, we have developed the LOFAR Transients Pipeline, or TraP. The TraP ingests multi-frequency image data from LOFAR or other instruments and searches it for transients and variables, providing automatic alerts of significant detections and populating a lightcurve database for further analysis by astronomers. Here, we discuss the scientific goals of the TraP and how it has been designed to meet them. We describe its implementation, including both the algorithms adopted to maximize performance as well as the development methodology used to ensure it is robust and reliable, particularly in the presence of artefacts typical of radio astronomy imaging. Finally, we report on a series of tests of the pipeline carried out using simulated LOFAR observations with a known population of transients.

  19. Scour below submerged skewed pipeline

    NASA Astrophysics Data System (ADS)

    Azamathulla, H. Md.; Yusoff, M. A. M.; Hasan, Z. A.

    2014-02-01

    Local scour below pipelines commonly occurs due to the erosive action of currents and waves. Scour is a major cause for the failure of underwater pipelines which is very important in water resources management. In this study, experiments were conducted to investigate the effect of four different pipeline orientations (30°, 45°, 60° and 90°) across a channel. The data sets of the laboratory measurements were also collected from published works. The temporal variation of local pipelines scour depth was studied to estimate the scour depth. The scour depth below the pipeline was determined using a regression model with five dimensionless parameters. A regression model with a coefficient of determination (R2 = 0.55) and a low root mean square error (RMSE = 0.47) produced fairly good predictions of the relative scour depth. The proposed equation gave satisfactory results when compared with the existing predictors.

  20. Mudslide effects on offshore pipelines

    SciTech Connect

    Swanson, R.C.; Jones, W.T.

    1982-11-01

    In regions of unstable soils such as portions of the Mississippi Delta, occasional pipeline failures during periods of severe weather have been attributed to mudslides. The effects of such downslope soil movements on the deflection and resulting stress in a pipeline have been studied in an attempt to reveal methods of routing or design which would reduce the risk of failure. Results show that the chances of surviving a slide are increased if the pipeline outer diameter is reduced to as small a value as possible, if the pipe wall thickness is increased, and if some slack is available in the line. The chance of survival is greatest if the slide occurs in a direction perpendicular to the pipeline route since the failure mode is primarily one of tension. When the slide crosses the pipeline at other angles of incidence, the chance of survival is significantly lessened.

  1. 75 FR 67807 - Pipeline Safety: Emergency Preparedness Communications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-03

    ... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Emergency Preparedness Communications AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Notice... and hazardous liquid pipeline facilities that they must make their pipeline emergency response...

  2. 75 FR 66425 - Pipeline Safety: Request for Special Permit

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-28

    ... received from Gulf South Pipeline Company, LP, a natural gas pipeline operator, seeking relief from... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Request for Special Permit AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Notice. SUMMARY: Pursuant...

  3. DEACTIVATION AND DECOMMISSIONING ENVIRONMENTAL STRATEGY FOR THE PLUTONIUM FINISHING PLANT COMPLEX, HANFORD NUCLEAR RESERVATION

    SciTech Connect

    Hopkins, A.M.; Heineman, R.; Norton, S.; Miller, M.; Oates, L.

    2003-02-27

    Maintaining compliance with environmental regulatory requirements is a significant priority in successful completion of the Plutonium Finishing Plant (PFP) Nuclear Material Stabilization (NMS) Project. To ensure regulatory compliance throughout the deactivation and decommissioning of the PFP complex, an environmental regulatory strategy was developed. The overall goal of this strategy is to comply with all applicable environmental laws and regulations and/or compliance agreements during PFP stabilization, deactivation, and eventual dismantlement. Significant environmental drivers for the PFP Nuclear Material Stabilization Project include the Tri-Party Agreement; the Resource Conservation and Recovery Act of 1976 (RCRA); the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the National Environmental Policy Act of 1969 (NEPA); the National Historic Preservation Act (NHPA); the Clean Air Act (CAA), and the Clean Water Act (CWA). Recent TPA negotiation s with Ecology and EPA have resulted in milestones that support the use of CERCLA as the primary statutory framework for decommissioning PFP. Milestones have been negotiated to support the preparation of Engineering Evaluations/Cost Analyses for decommissioning major PFP buildings. Specifically, CERCLA EE/CA(s) are anticipated for the following scopes of work: Settling Tank 241-Z-361, the 232-Z Incinerator, , the process facilities (eg, 234-5Z, 242, 236) and the process facility support buildings. These CERCLA EE/CA(s) are for the purpose of analyzing the appropriateness of the slab-on-grade endpoint Additionally, agreement was reached on performing an evaluation of actions necessary to address below-grade structures or other structures remaining after completion of the decommissioning of PFP. Remaining CERCLA actions will be integrated with other Central Plateau activities at the Hanford site.

  4. Fugitive emissions of methane from abandoned, decommissioned oil and gas wells.

    PubMed

    Boothroyd, I M; Almond, S; Qassim, S M; Worrall, F; Davies, R J

    2016-03-15

    This study considered the fugitive emissions of methane (CH4) from former oil and gas exploration and production wells drilled to exploit conventional hydrocarbon reservoirs onshore in the UK. This study selected from the 66% of all onshore wells in the UK which appeared to be properly decommissioned (abandoned) that came from 4 different basins and were between 8 and 79 years old. The soil gas above each well was analysed and assessed relative to a nearby control site of similar land use and soil type. The results showed that of the 102 wells considered 30% had soil gas CH4 at the soil surface that was significantly greater than their respective control. Conversely, 39% of well sites had significant lower surface soil gas CH4 concentrations than their respective control. We interpret elevated soil gas CH4 concentrations to be the result of well integrity failure, but do not know the source of the gas nor the route to the surface. Where elevated CH4 was detected it appears to have occurred within a decade of it being drilled. The flux of CH4 from wells was 364 ± 677 kg CO2eq/well/year with a 27% chance that the well would have a negative flux to the atmosphere independent of well age. This flux is low relative to the activity commonly used on decommissioned well sites (e.g. sheep grazing), however, fluxes from wells that have not been appropriately decommissioned would be expected to be higher.

  5. Renewables-to-reefs? - Decommissioning options for the offshore wind power industry.

    PubMed

    Smyth, Katie; Christie, Nikki; Burdon, Daryl; Atkins, Jonathan P; Barnes, Richard; Elliott, Michael

    2015-01-15

    The offshore wind power industry is relatively new but increasing globally, hence it is important that the whole life-cycle is managed. The construction-operation-decommissioning cycle is likely to take 20-30 years and whilst decommissioning may not be undertaken for many years, its management needs to be addressed in both current and future marine management regimes. This can be defined within a Drivers-Activities-Pressures-State Changes-Impacts (on human Welfare)-Responses framework. This paper considers the main decommissioning options - partial or complete removal of all components. A SWOT analysis shows environmental and economic benefits in partial as opposed to complete removal, especially if habitat created on the structures has conservation or commercial value. Benefits (and repercussions) are defined in terms of losses and gains of ecosystem services and societal benefits. The legal precedents and repercussions of both options are considered in terms of the 10-tenets of sustainable marine management. Finally a 'renewables-to-reefs' programme is proposed. PMID:25467865

  6. Overview of the 1995 NATO ARW on nuclear submarine decommissioning and related problems

    SciTech Connect

    LeSage, L.G.

    1997-10-01

    The NATO Advanced Research Workshop on Nuclear Submarine Decommissioning and Related Problems was held in Moscow June 19--22, 1995. It was preceded by a visit to the Zvezdotchka Shipyard at Severodvinsk, a repair and maintenance yard for Russian nuclear submarines, for a subgroup of the workshop attendees. Most of the material in this paper is drawn directly form the workshop proceedings. Slightly less than 500 nuclear ships and submarines (the vast majority are submarines) have been constructed by the countries with nuclear navies. This includes approximately 250 by Russia, 195 by the United States, 23 by the United Kingdom, 11 by France and 6 by China. By the year 2000 it is expected that approximately one-half of these nuclear vessels will be removed from service and in various states of decommissioning. A newspaper account in June 1997 indicated that 156 Russian nuclear submarines had been removed from service. In August 1996 it was reported that 55 reactor compartment sections from US nuclear submarines were already in long-term storage at Hanford. Overall the dismantlement of nuclear submarines and the processing, storage and disposal of nuclear fuel, activated components and section of the hulls, and the liquid and solid radioactive and hazardous wastes is an enormous problem. This problem has been exacerbated by the accelerated decommissioning schedule associated with treaty obligations.

  7. Renewables-to-reefs? - Decommissioning options for the offshore wind power industry.

    PubMed

    Smyth, Katie; Christie, Nikki; Burdon, Daryl; Atkins, Jonathan P; Barnes, Richard; Elliott, Michael

    2015-01-15

    The offshore wind power industry is relatively new but increasing globally, hence it is important that the whole life-cycle is managed. The construction-operation-decommissioning cycle is likely to take 20-30 years and whilst decommissioning may not be undertaken for many years, its management needs to be addressed in both current and future marine management regimes. This can be defined within a Drivers-Activities-Pressures-State Changes-Impacts (on human Welfare)-Responses framework. This paper considers the main decommissioning options - partial or complete removal of all components. A SWOT analysis shows environmental and economic benefits in partial as opposed to complete removal, especially if habitat created on the structures has conservation or commercial value. Benefits (and repercussions) are defined in terms of losses and gains of ecosystem services and societal benefits. The legal precedents and repercussions of both options are considered in terms of the 10-tenets of sustainable marine management. Finally a 'renewables-to-reefs' programme is proposed.

  8. Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

    SciTech Connect

    E. Perry; J. Chrzanowski; K. Rule; M. Viola; M. Williams; R. Strykowsky

    1999-11-01

    The Tokamak Fusion Test Reactor (TFTR) is a one-of-a-kind, tritium-fueled fusion research reactor that ceased operation in April 1997. The Decontamination and Decommissioning (D and D) of the TFTR is scheduled to occur over a period of three years beginning in October 1999. This is not a typical Department of Energy D and D Project where a facility is isolated and cleaned up by ''bulldozing'' all facility and hardware systems to a greenfield condition. The mission of TFTR D and D is to: (a) surgically remove items which can be re-used within the DOE complex, (b) remove tritium contaminated and activated systems for disposal, (c) clear the test cell of hardware for future reuse, (d) reclassify the D-site complex as a non-nuclear facility as defined in DOE Order 420.1 (Facility Safety) and (e) provide data on the D and D of a large magnetic fusion facility. The 100 cubic meter volume of the donut-shaped reactor makes it the second largest fusion reactor in the world. The record-breaking deuterium-tritium experiments performed on TFTR resulted in contaminating the vacuum vessel with tritium and activating the materials with 14 Mev neutrons. The total tritium content within the vessel is in excess of 7,000 Curies while dose rates approach 75 mRem/hr. These radiological hazards along with the size and shape of the Tokamak present a unique and challenging task for dismantling.

  9. HANFORD DECOMMISSIONING UPDATE 09/2007

    SciTech Connect

    GERBER, M.S.

    2007-08-20

    Fluor Hanford's K Basins Closure (KBC) Project tallied three major accomplishments at the U.S. Department of Energy's (DOE's) Hanford Site in Southeastern Washington State this past summer. The Project finished emptying the aging K East Basin of both sludge and the last pieces of scrap spent nuclear fuel. It also Completed vacuuming the bulk of the sludge in the K West Basin into underwater containers. The 54-year-old concrete basins once held more than four million pounds of spent nuclear fuel and sit less than 400 yards from the Columbia River. Each basin holds more than a million gallons of radioactive water. In 2004, Fluor finished removing all the spent nuclear fuel from the K Basins. Nearly 50 cubic meters of sludge remained--a combination of dirt, sand, small pieces of corroded uranium fuel and fuel cladding, corrosion products from racks and canisters, ion-exchange resin beads, polychlorinated biphenyls, and fission products that had formed during the decades that the spent nuclear fuel was stored underwater. Capturing the sludge into underwater containers in the K East Basin took more than two years, and vacuuming the much smaller volume of sludge into containers in the K West Basin required seven months. Workers stood on grating above the basin water and vacuumed the sludge through long, heavy hoses. The work was complicated by murky water and contaminated solid waste (debris). Pumping was paused several times to safely remove and package debris that totaled more than 370 tons. In October 2006, Fluor Hanford workers began pumping the sludge captured in the K East Basin containers out through a specially designed pipeline to underwater containers in the K West Basin, about a half mile away. They used a heavy but flexible, double-walled ''hose-in-hose'' system. Pumping work progressed slowly at first, but ramped up in spring 2007 and was completed on May 31. Just a week before sludge transfers finished, the KBC Project removed the last few small pieces of

  10. Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361

    SciTech Connect

    Moshonas Cole, Katherine; Dinner, Julia; Grey, Mike; Daniska, Vladimir

    2013-07-01

    The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

  11. Pipeline issues shape southern FSU oil, gas development

    SciTech Connect

    1995-05-22

    To future production from southern republics of the former Soviet Union (FSU), construction and revitalization of pipelines are as important as the supply of capital. Export capacity will limit production and slow development activity in the region until new pipelines are in place. Plenty of pipeline proposals have come forward. The problem is politics, which for every proposal so far complicates routing or financing or both. Russia has made clear its intention to use pipeline route decisions to retain influence in the region. As a source of external pressure, it is not alone. Iran and Turkey also have made strong bids for the southern FSU`s oil and gas transport business. Diplomacy thus will say as much as commerce does about how transportation issues are settled and how quickly the southern republics move toward their potentials to produce oil and gas. The paper discusses possible routes and the problems with them, the most likely proposal, and future oil flows.

  12. An overview of U.S. decommissioning experience -- A basic introduction

    SciTech Connect

    Boing, L.E.

    1998-03-09

    This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community.

  13. Progress and experiences from the decommissioning of the Eurochemic reprocessing plant

    SciTech Connect

    Gills, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.

    2007-07-01

    Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels. The remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions restored. The Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. The main building is a large concrete structure, comprising a surface area of 55,000 m{sup 2}, concrete volume 12,500 m{sup 3}, and 1,500 Mg of metal components. The building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the dismantling of the ventilation system. Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and automatic positioning systems are successfully applied. In view of the final demolition of the main process building, the main process building is divided into three parts - each part is isolated from the others. In the middle of 2008, after the removal of the NDA-IPAN/GEA installation, the eastern part will be demolished. The paper presents a status overview of the decommissioning and decontamination activities at the main process building of the former Eurochemic reprocessing plant on the nuclear site of Dessel in Belgium. The specific BELGOPROCESS approach will be highlighted, in which the decommissioning activities are carried out on an industrial scale with special emphasis on cost minimisation, the use of technology on an industrial representative scale and the specific alpha contamination of equipment and building surfaces, requiring that the decommissioning work is done with adequate protective clothing

  14. Maglev crude oil pipeline

    NASA Technical Reports Server (NTRS)

    Knolle, Ernst G.

    1994-01-01

    This maglev crude oil pipeline consists of two conduits guiding an endless stream of long containers. One conduit carries loaded containers and the other empty returns. The containers are levitated by permanent magnets in repulsion and propelled by stationary linear induction motors. The containers are linked to each other in a manner that allows them, while in continuous motion, to be folded into side by side position at loading and unloading points. This folding causes a speed reduction in proportion to the ratio of container diameter to container length. While in side by side position, containers are opened at their ends to be filled or emptied. Container size and speed are elected to produce a desired carrying capacity.

  15. Maglev crude oil pipeline

    NASA Astrophysics Data System (ADS)

    Knolle, Ernst G.

    1994-05-01

    This maglev crude oil pipeline consists of two conduits guiding an endless stream of long containers. One conduit carries loaded containers and the other empty returns. The containers are levitated by permanent magnets in repulsion and propelled by stationary linear induction motors. The containers are linked to each other in a manner that allows them, while in continuous motion, to be folded into side by side position at loading and unloading points. This folding causes a speed reduction in proportion to the ratio of container diameter to container length. While in side by side position, containers are opened at their ends to be filled or emptied. Container size and speed are elected to produce a desired carrying capacity.

  16. INTERNAL REPAIR OF PIPELINES

    SciTech Connect

    Robin Gordon; Bill Bruce; Ian Harris; Dennis Harwig; George Ritter; Bill Mohr; Matt Boring; Nancy Porter; Mike Sullivan; Chris Neary

    2004-08-17

    The two broad categories of fiber-reinforced composite liner repair and deposited weld metal repair technologies were reviewed and evaluated for potential application for internal repair of gas transmission pipelines. Both are used to some extent for other applications and could be further developed for internal, local, structural repair of gas transmission pipelines. Principal conclusions from a survey of natural gas transmission industry pipeline operators can be summarized in terms of the following performance requirements for internal repair: (1) Use of internal repair is most attractive for river crossings, under other bodies of water, in difficult soil conditions, under highways, under congested intersections, and under railway. (2) Internal pipe repair offers a strong potential advantage to the high cost of horizontal direct drilling when a new bore must be created to solve a leak or other problem. (3) Typical travel distances can be divided into three distinct groups: up to 305 m (1,000 ft.); between 305 m and 610 m (1,000 ft. and 2,000 ft.); and beyond 914 m (3,000 ft.). All three groups require pig-based systems. A despooled umbilical system would suffice for the first two groups which represents 81% of survey respondents. The third group would require an onboard self-contained power unit for propulsion and welding/liner repair energy needs. (4) The most common size range for 80% to 90% of operators surveyed is 508 mm (20 in.) to 762 mm (30 in.), with 95% using 558.8 mm (22 in.) pipe. Evaluation trials were conducted on pipe sections with simulated corrosion damage repaired with glass fiber-reinforced composite liners, carbon fiber-reinforced composite liners, and weld deposition. Additional un-repaired pipe sections were evaluated in the virgin condition and with simulated damage. Hydrostatic failure pressures for pipe sections repaired with glass fiber-reinforced composite liner were only marginally greater than that of pipe sections without liners

  17. INTERNAL REPAIR OF PIPELINES

    SciTech Connect

    Robin Gordon; Bill Bruce; Ian Harris; Dennis Harwig; Nancy Porter; Mike Sullivan; Chris Neary

    2004-04-12

    The two broad categories of deposited weld metal repair and fiber-reinforced composite liner repair technologies were reviewed for potential application for internal repair of gas transmission pipelines. Both are used to some extent for other applications and could be further developed for internal, local, structural repair of gas transmission pipelines. Preliminary test programs were developed for both deposited weld metal repair and for fiber-reinforced composite liner repair. Evaluation trials have been conducted using a modified fiber-reinforced composite liner provided by RolaTube and pipe sections without liners. All pipe section specimens failed in areas of simulated damage. Pipe sections containing fiber-reinforced composite liners failed at pressures marginally greater than the pipe sections without liners. The next step is to evaluate a liner material with a modulus of elasticity approximately 95% of the modulus of elasticity for steel. Preliminary welding parameters were developed for deposited weld metal repair in preparation of the receipt of Pacific Gas & Electric's internal pipeline welding repair system (that was designed specifically for 559 mm (22 in.) diameter pipe) and the receipt of 559 mm (22 in.) pipe sections from Panhandle Eastern. The next steps are to transfer welding parameters to the PG&E system and to pressure test repaired pipe sections to failure. A survey of pipeline operators was conducted to better understand the needs and performance requirements of the natural gas transmission industry regarding internal repair. Completed surveys contained the following principal conclusions: (1) Use of internal weld repair is most attractive for river crossings, under other bodies of water, in difficult soil conditions, under highways, under congested intersections, and under railway crossings. (2) Internal pipe repair offers a strong potential advantage to the high cost of horizontal direct drilling (HDD) when a new bore must be created to

  18. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report

    SciTech Connect

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  19. Reliability prediction of corroding pipelines

    SciTech Connect

    Strutt, J.E.; Allsopp, K.; Newman, D.; Trille, C.

    1996-12-01

    Recent data collection studies relating to loss of containment of pipeline and risers indicate that corrosion is now the dominant failure mode for steel pipelines in the North Sea area. As the North Sea pipeline infrastructure ages, it is expected that the proportion of pipelines failing by corrosion will increase further and this raises the question of the relationship between probability of pipeline corrosion failure and the reliability of the corrosion control and monitoring systems used by operators to prevent corrosion failures. This paper describes a methodology for predicting the probability of corrosion failure of a specific submarine pipeline or riser system. The paper illustrates how the model can be used to predict the safe life of a pipeline, given knowledge of the underlying corrosion behavior and corrosion control system and how the time to failure can be updated in the light of inspection and monitoring results enabling inspection policy to be evaluated for its impact on risk. The paper also shows how different assumptions concerning the underlying cause of failure influences the estimation of the probability of failure.

  20. Mobile workstation for decontamination and decommissioning operations

    SciTech Connect

    Whittaker, W.L.; Osborn, J.F.; Thompson, B.R.

    1993-10-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D&D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D&D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility.

  1. Interaction between soils and gas pipelines

    NASA Astrophysics Data System (ADS)

    Karpachevskii, L. O.; Goroshevskii, A. V.; Zubkova, T. A.

    2011-03-01

    The interaction between pipelines and soils manifests itself in the soil disturbance in the course of the pipe installation, in the transformation of the water and temperature regimes in the trenches, and in the appearance of corrosion and cracks on the pipe walls. The more contrasting the soil water regime in the pipe-adjacent sections of the trench, the greater the amount of the pipe damage. The damage of the pipe insulation activates the pipe corrosion. The emission of gases (H2S, CH4, CO2, CO, and H2) and the activity of sulfate-reducing bacteria are the main causes of the pipes' destruction. The humus content and the redox potential decrease, and the soil density and concentrations of ferrous compounds increase in the soils of the trench zone. Accidents along pipelines occur most often in the area of serozems and chestnut soils, and this is related to the salinization in the lower soil horizons and to the contrasting soil water regime near the pipe. The number of accidents along the pipelines installed into soddy-podzolic soils is lower.

  2. Summary of stationary and personal air sampling measurements made during a plutonium glovebox decommissioning project.

    SciTech Connect

    Munyon, W. J.; Lee, M. B.

    2002-02-01

    Workplace air sampling was performed during the decommissioning of a previously active plutonium glovebox facility located at Argonne National Laboratory. Personal air samplers (PAS) were used to measure breathing zone activity concentrations of workers engaged in size-reducing contaminated gloveboxes. Stationary air samplers (SAS) were used to measure the work area activity concentrations and test their application in providing representative sampling of breathing zone activity concentrations. The relative response of these samplers (PAS:SAS) was tracked during the course of the decommissioning work, with results yielding favorable agreement to within a factor of {+-}5. A cascade impactor was used to determine the particle size distribution of workplace aerosols. The average activity median aerodynamic diameter (AMAD) was estimated to be 3.0 {mu}m, with a corresponding geometric standard deviation of 2.4. A gas-flow proportional counter was utilized to measure the gross alpha activity collected on both the SAS glass fiber and the PAS cellulose fiber filters. A subset of this filter group was subsequently analyzed using an alpha spectrometer post radiochemical processing and isotopic separation. The quantity of alpha activity measured on the SAS filters was generally within {+-}30% of the alpha spectrometry measurements. However, measurements made of the activity present on the PAS cellulose fiber filters were consistently underestimated using a gas-flow proportional counter, suggesting a small correction factor of 15-20% to account for the absorption of alpha particle emissions.

  3. Summary of stationary and personal air sampling measurements made during a plutonium glovebox decommissioning project.

    PubMed

    Munyon, W J; Lee, M B

    2002-02-01

    Workplace air sampling was performed during the decommissioning of a previously active plutonium glovebox facility located at Argonne National Laboratory. Personal air samplers (PAS) were used to measure breathing zone activity concentrations of workers engaged in size-reducing contaminated gloveboxes. Stationary air samplers (SAS) were used to measure the work area activity concentrations and test their application in providing representative sampling of breathing zone activity concentrations. The relative response of these samplers (PAS:SAS) was tracked during the course of the decommissioning work, with results yielding favorable agreement to within a factor of +/-5. A cascade impactor was used to determine the particle size distribution of workplace aerosols. The average activity median aerodynamic diameter (AMAD) was estimated to be 3.0 microm, with a corresponding geometric standard deviation of 2.4. A gas-flow proportional counter was utilized to measure the gross alpha activity collected on both the SAS glass fiber and the PAS cellulose fiber filters. A subset of this filter group was subsequently analyzed using an alpha spectrometer post radiochemical processing and isotopic separation. The quantity of alpha activity measured on the SAS filters was generally within +/-30% of the alpha spectrometry measurements. However, measurements made of the activity present on the PAS cellulose fiber filters were consistently underestimated using a gas-flow proportional counter, suggesting a small correction factor of 15-20% to account for the absorption of alpha particle emissions.

  4. Natural gas pipeline technology overview.

    SciTech Connect

    Folga, S. M.; Decision and Information Sciences

    2007-11-01

    The United States relies on natural gas for one-quarter of its energy needs. In 2001 alone, the nation consumed 21.5 trillion cubic feet of natural gas. A large portion of natural gas pipeline capacity within the United States is directed from major production areas in Texas and Louisiana, Wyoming, and other states to markets in the western, eastern, and midwestern regions of the country. In the past 10 years, increasing levels of gas from Canada have also been brought into these markets (EIA 2007). The United States has several major natural gas production basins and an extensive natural gas pipeline network, with almost 95% of U.S. natural gas imports coming from Canada. At present, the gas pipeline infrastructure is more developed between Canada and the United States than between Mexico and the United States. Gas flows from Canada to the United States through several major pipelines feeding U.S. markets in the Midwest, Northeast, Pacific Northwest, and California. Some key examples are the Alliance Pipeline, the Northern Border Pipeline, the Maritimes & Northeast Pipeline, the TransCanada Pipeline System, and Westcoast Energy pipelines. Major connections join Texas and northeastern Mexico, with additional connections to Arizona and between California and Baja California, Mexico (INGAA 2007). Of the natural gas consumed in the United States, 85% is produced domestically. Figure 1.1-1 shows the complex North American natural gas network. The pipeline transmission system--the 'interstate highway' for natural gas--consists of 180,000 miles of high-strength steel pipe varying in diameter, normally between 30 and 36 inches in diameter. The primary function of the transmission pipeline company is to move huge amounts of natural gas thousands of miles from producing regions to local natural gas utility delivery points. These delivery points, called 'city gate stations', are usually owned by distribution companies, although some are owned by transmission companies

  5. 27 CFR 24.169 - Pipelines.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2014-04-01 2014-04-01 false Pipelines. 24.169 Section... THE TREASURY ALCOHOL WINE Construction and Equipment § 24.169 Pipelines. Pipelines, including flexible.... The appropriate TTB officer may approve pipelines which cannot be readily examined if no jeopardy...

  6. 27 CFR 24.169 - Pipelines.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2011-04-01 2011-04-01 false Pipelines. 24.169 Section... THE TREASURY LIQUORS WINE Construction and Equipment § 24.169 Pipelines. Pipelines, including flexible.... The appropriate TTB officer may approve pipelines which cannot be readily examined if no jeopardy...

  7. 27 CFR 24.169 - Pipelines.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2013-04-01 2013-04-01 false Pipelines. 24.169 Section... THE TREASURY ALCOHOL WINE Construction and Equipment § 24.169 Pipelines. Pipelines, including flexible.... The appropriate TTB officer may approve pipelines which cannot be readily examined if no jeopardy...

  8. 27 CFR 24.169 - Pipelines.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Pipelines. 24.169 Section... THE TREASURY LIQUORS WINE Construction and Equipment § 24.169 Pipelines. Pipelines, including flexible.... The appropriate TTB officer may approve pipelines which cannot be readily examined if no jeopardy...

  9. 27 CFR 24.169 - Pipelines.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2012-04-01 2012-04-01 false Pipelines. 24.169 Section... THE TREASURY LIQUORS WINE Construction and Equipment § 24.169 Pipelines. Pipelines, including flexible.... The appropriate TTB officer may approve pipelines which cannot be readily examined if no jeopardy...

  10. 1997 annual pipeline directory and equipment guide

    SciTech Connect

    1997-09-01

    This annual guide is divided into the following sections: Equivalent valve tables; Complete 1997 line pipe tables; Engineering and construction services; Crude oil pipeline companies; Slurry companies; Natural gas companies; Gas distribution pipeline companies; Municipal gas systems; Canadian pipeline companies; International pipeline companies; and Company index. The tables list component materials, manufacturers, and service companies.

  11. 77 FR 5472 - Pipeline Safety: Miscellaneous Changes to Pipeline Safety Regulations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-03

    ... amendments to the pipeline safety regulations (76 FR 73570). On January 12, 2012, the Interstate Natural Gas... Pipeline and Hazardous Materials Safety Administration 49 CFR Parts 191, 192 and 195 RIN 2137-AE59 Pipeline Safety: Miscellaneous Changes to Pipeline Safety Regulations AGENCY: Pipeline and Hazardous...

  12. 77 FR 16471 - Pipeline Safety: Implementation of the National Registry of Pipeline and Liquefied Natural Gas...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-21

    ...: Implementation of the National Registry of Pipeline and Liquefied Natural Gas Operators AGENCY: Pipeline and... registry of pipeline and liquefied natural gas operators. This notice provides updates to the information... the Federal Register (75 FR 72878) titled: ``Pipeline Safety: Updates to Pipeline and...

  13. Regional pipeline environmental assessment record: an aggregate analysis of major areas of pipeline concern and impact on the Outer Continental Shelf (Gulf of Mexico)

    SciTech Connect

    Not Available

    1981-03-01

    Oil and gas pipeline activities on the Gulf of Mexico Outer Continental Shelf (OCS) affect a wide range of living and nonliving environmental variables (i.e., water, biologically sensitive areas, and food-web relations). These industrial activities have been increasing steadily over the past 20 years. Much of the information included herein pertains to a description of the existing environment for offshore Louisiana and Texas and an analysis of potential pipeline proposals and alternatives. The document is not as complete as an environmental impact statement (EIS) but it is sufficient in scope to consider the analysis of impacts of the majority of pipeline activities occurring in the northern and western Gulf of Mexico OCS. This report will be useful in evaluating pipeline impacts on the regional environment in the future. Rather than treating each pipeline application extensively, the information included herein will be referenced, thereby reducing the paperwork involved in environmental analysis.

  14. Assessment of strippable coatings for decontamination and decommissioning

    SciTech Connect

    Ebadian, M.A.

    1998-01-01

    Strippable or temporary coatings were developed to assist in the decontamination of the Three Mile Island (TMI-2) reactor. These coatings have become a viable option during the decontamination and decommissioning (D and D) of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. A variety of strippable coatings are available to D and D professionals. However, these products exhibit a wide range of performance criteria and uses. The Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU) was commissioned to perform a 2-year investigation into strippable coatings. This investigation was divided into four parts: (1) identification of commercially available strippable coating products; (2) survey of D and D professionals to determine current uses of these coatings and performance criteria; (3) design and implementation of a non-radiological testing program to evaluate the physical properties of these coatings; and (4) design and implementation of a radiological testing program to determine decontamination factors and effects of exposure to ionizing radiation. Activities during fiscal year 1997 are described.

  15. The Role of the Sellafield Ltd Centres of Expertise in Engaging with the Science, Environment and Technology Supply Chain and University Sector to Support Site Operations and Decommissioning in the UK Nuclear Industry - 13018

    SciTech Connect

    Butcher, Ed; Connor, Donna; Keighley, Debbie

    2013-07-01

    The development and maintenance of the broad range of the highly technical skills required for safe and successful management of nuclear sites is of vital importance during routine operations, decommissioning and waste treatment activities.. In order to maintain a core team of technical experts, across all of the disciplines required for these tasks, the approach which has been taken by the Sellafield Ltd has been the formation of twenty five Centres of Expertise (CoE), each covering key aspects of the technical skills required for nuclear site operations. Links with the Specialist University Departments: The CoE leads are also responsible for establishing formal links with university departments with specialist skills and facilities relevant to their CoE areas. The objective of these links is to allow these very specialist capabilities within the university sector to be more effectively utilized by the nuclear industry, which benefits both sectors. In addition to the utilization of specialist skills, the university links are providing an important introduction to the nuclear industry for students and researchers. This is designed to develop the pipeline of potential staff, who will be required in the future by both the academic and industrial sectors. (authors)

  16. Development of Safety Assessment Code for Decommissioning of Nuclear Facilities

    NASA Astrophysics Data System (ADS)

    Shimada, Taro; Ohshima, Soichiro; Sukegawa, Takenori

    A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR) at Japan Atomic Energy Research Institute (currently JAEA). DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning, and also evaluates the public dose at accidental situations including fire and explosion. As for the public, both the internal and the external doses are calculated by considering inhalation, ingestion, direct radiation from radioactive aerosols and radioactive depositions, and skyshine radiation from waste containers. For external dose for workers, the dose rate from contaminated components and structures to be dismantled is calculated. Internal dose for workers is calculated by considering dismantling conditions, e.g. cutting speed, cutting length of the components and exhaust velocity. Estimation models for dose rate and staying time were verified by comparison with the actual external dose of workers which were acquired during JPDR decommissioning project. DecDose code is expected to contribute the safety assessment for decommissioning of nuclear facilities.

  17. PIPELINES AS COMMUNICATION NETWORK LINKS

    SciTech Connect

    Kelvin T. Erickson; Ann Miller; E. Keith Stanek; C.H. Wu; Shari Dunn-Norman

    2005-03-14

    This report presents the results of an investigation into two methods of using the natural gas pipeline as a communication medium. The work addressed the need to develop secure system monitoring and control techniques between the field and control centers and to robotic devices in the pipeline. In the first method, the pipeline was treated as a microwave waveguide. In the second method, the pipe was treated as a leaky feeder or a multi-ground neutral and the signal was directly injected onto the metal pipe. These methods were tested on existing pipeline loops at UMR and Batelle. The results reported in this report indicate the feasibility of both methods. In addition, a few suitable communication link protocols for this network were analyzed.

  18. Nondestructive characterization of pipeline materials

    NASA Astrophysics Data System (ADS)

    Engle, Brady J.; Smart, Lucinda J.; Bond, Leonard J.

    2015-03-01

    There is a growing need to quantitatively and nondestructively evaluate the strength and toughness properties of pipeline steels, particularly in aging pipeline infrastructure. These strength and toughness properties, namely yield strength, tensile strength, transition temperature, and toughness, are essential for determining the safe operating pressure of the pipelines. For some older pipelines crucial information can be unknown, which makes determining the pressure rating difficult. Current inspection techniques address some of these issues, but they are not comprehensive. This paper will briefly discuss current inspection techniques and relevant literature for relating nondestructive measurements to key strength and toughness properties. A project is in progress to provide new in-trench tools that will give strength properties without the need for sample removal and destructive testing. Preliminary experimental ultrasonic methods and measurements will be presented, including velocity, attenuation, and backscatter measurements.

  19. Historical analysis of US pipeline accidents triggered by natural hazards

    NASA Astrophysics Data System (ADS)

    Girgin, Serkan; Krausmann, Elisabeth

    2015-04-01

    Natural hazards, such as earthquakes, floods, landslides, or lightning, can initiate accidents in oil and gas pipelines with potentially major consequences on the population or the environment due to toxic releases, fires and explosions. Accidents of this type are also referred to as Natech events. Many major accidents highlight the risk associated with natural-hazard impact on pipelines transporting dangerous substances. For instance, in the USA in 1994, flooding of the San Jacinto River caused the rupture of 8 and the undermining of 29 pipelines by the floodwaters. About 5.5 million litres of petroleum and related products were spilled into the river and ignited. As a results, 547 people were injured and significant environmental damage occurred. Post-incident analysis is a valuable tool for better understanding the causes, dynamics and impacts of pipeline Natech accidents in support of future accident prevention and mitigation. Therefore, data on onshore hazardous-liquid pipeline accidents collected by the US Pipeline and Hazardous Materials Safety Administration (PHMSA) was analysed. For this purpose, a database-driven incident data analysis system was developed to aid the rapid review and categorization of PHMSA incident reports. Using an automated data-mining process followed by a peer review of the incident records and supported by natural hazard databases and external information sources, the pipeline Natechs were identified. As a by-product of the data-collection process, the database now includes over 800,000 incidents from all causes in industrial and transportation activities, which are automatically classified in the same way as the PHMSA record. This presentation describes the data collection and reviewing steps conducted during the study, provides information on the developed database and data analysis tools, and reports the findings of a statistical analysis of the identified hazardous liquid pipeline incidents in terms of accident dynamics and

  20. Risk assessment prioritization in the Office of Pipeline Safety

    SciTech Connect

    Wolf, G.J.

    1994-12-31

    The Office of Pipeline Safety (OPS) of the Research and Special Programs Administration (RSPA), US Department of Transportation, is developing and implementing a process of Risk Assessment Prioritization (RAP). The objective of RAP is to use pipeline safety resources to yield the greatest improvement to pipeline safety and protection of the environment without unduly burdening industry, government, or the public. The RAP process involves extensive participation by stakeholders outside of OPS who have interests in pipeline safety and environmental protection. The process will be used to calculate a numeric value as the basis for prioritization of pipeline safety activity, whether by rulemaking or other alternatives, such as compliance emphasis, education, research, information dissemination, and interactive external relations. The RAP process will identify pipeline safety issues and their multiple solutions. A panel of experts will rate each solution for its effect on the probability and consequence of accident occurrence, and the cost to implement the solution. Using the ratings, OPS will calculate a risk reduction value for each solution. Resources will be assigned to implementing the solutions having the highest risk reduction values. OPS management will establish an action plan aimed at implementing solutions having the highest risk reduction value, while continuing action on those solutions mandated by law.

  1. 30 CFR 585.904 - Can I request a departure from the decommissioning requirements?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... decommissioning requirements? 585.904 Section 585.904 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER... requirements under § 585.103. Decommissioning Applications...

  2. 30 CFR 585.904 - Can I request a departure from the decommissioning requirements?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... decommissioning requirements? 585.904 Section 585.904 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER... requirements under § 585.103. Decommissioning Applications...

  3. 30 CFR 585.904 - Can I request a departure from the decommissioning requirements?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... decommissioning requirements? 585.904 Section 585.904 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER... requirements under § 585.103. Decommissioning Applications...

  4. Pipeline of Known Chemical Classes of Antibiotics

    PubMed Central

    d’Urso de Souza Mendes, Cristina; de Souza Antunes, Adelaide Maria

    2013-01-01

    Many approaches are used to discover new antibiotic compounds, one of the most widespread being the chemical modification of known antibiotics. This type of discovery has been so important in the development of new antibiotics that most antibiotics used today belong to the same chemical classes as antibiotics discovered in the 1950s and 1960s. Even though the discovery of new classes of antibiotics is urgently needed, the chemical modification of antibiotics in known classes is still widely used to discover new antibiotics, resulting in a great number of compounds in the discovery and clinical pipeline that belong to existing classes. In this scenario, the present article presents an overview of the R&D pipeline of new antibiotics in known classes of antibiotics, from discovery to clinical trial, in order to map out the technological trends in this type of antibiotic R&D, aiming to identify the chemical classes attracting most interest, their spectrum of activity, and the new subclasses under development. The result of the study shows that the new antibiotics in the pipeline belong to the following chemical classes: quinolones, aminoglycosides, macrolides, oxazolidinones, tetracyclines, pleuromutilins, beta-lactams, lipoglycopeptides, polymyxins and cyclic lipopeptides. PMID:27029317

  5. Technology needs for decommissioning and decontamination

    SciTech Connect

    Bundy, R.D.; Kennerly, J.M.

    1993-12-01

    This report summarizes the current view of the most important decontamination and decommissioning (D & D) technology needs for the US Department of Energy facilities for which the D & D programs are the responsibility of Martin Marietta Energy Systems, Inc. The source of information used in this assessment was a survey of the D & D program managers at each facility. A summary of needs presented in earlier surveys of site needs in approximate priority order was supplied to each site as a starting point to stimulate thinking. This document reflects a brief initial assessment of ongoing needs; these needs will change as plans for D & D are finalized, some of the technical problems are solved through successful development programs, and new ideas for D and D technologies appear. Thus, this assessment should be updated and upgraded periodically, perhaps, annually. This assessment differs from others that have been made in that it directly and solely reflects the perceived need for new technology by key personnel in the D & D programs at the various facilities and does not attempt to consider the likelihood that these technologies can be successfully developed. Thus, this list of technology needs also does not consider the cost, time, and effort required to develop the desired technologies. An R & D program must include studies that have a reasonable chance for success as well as those for which there is a high need. Other studies that considered the cost and probability of successful development as well as the need for new technology are documented. However, the need for new technology may be diluted in such studies; this document focuses only on the need for new technology as currently perceived by those actually charged with accomplishing D & D.

  6. Creating a pipeline rehabilitation plan

    SciTech Connect

    Marshall, W.F.

    1997-05-01

    This paper will highlight the various aspects of planning a pipeline rehabilitation project to maximize used resources. The paper will visit in some detail the aspect of pipeline data collection to make rehabilitation decisions, including intelligent pig data and its use, close interval survey and its use, hydrotest data and its use, etc. This paper will also review the analysis of the hydrotest data, the close interval survey data, and its meaning to the overall rehabilitation design and plan. The paper will also assess the various types of pipeline coatings and methods of recoating and typical and innovative cathodic protection methods. The paper will stress analysis of pipeline structural integrity prior to making rehabilitation decisions. It will review cost estimating for various types of pipeline rehabilitation, and look at various alternatives. Finally, this paper will review typical results from various types of rehabilitation and soil conditions. It will emphasize the need to assess the results of the different rehabilitation methods and detail the future pipeline rehabilitation project decision making. The paper will discuss the use of RAP sheets (rehabilitation analysis profile) for data review and suggest various methods to invest rehabilitation dollars to get the greatest quantity of rehabilitation work done for the least cost.

  7. 76 FR 28326 - Pipeline Safety: National Pipeline Mapping System Data Submissions and Submission Dates for Gas...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-17

    ... provides guidance for Calendar Year 2010 National Pipeline Mapping System (NPMS) submissions. FOR FURTHER...: National Pipeline Mapping System Data Submissions and Submission Dates for Gas Transmission and Gathering Systems and Liquefied Natural Gas Annual Reports AGENCY: Pipeline and Hazardous Materials...

  8. The shielding design process--new plants to decommissioning.

    PubMed

    Jeffries, Graham; Cooper, Andrew; Hobson, John

    2005-01-01

    BNFL have over 25 years experience of designing nuclear plant for the whole-fuel cycle. In the UK, a Nuclear Decommissioning Authority (NDA) is to be set up to ensure that Britain's nuclear legacy is cleaned up safely, securely and cost effectively. The resulting challenges and opportunities for shielding design will be substantial as the shielding design process was originally devised for the design of new plants. Although its underlying principles are equally applicable to decommissioning and remediation of old plants, there are many aspects of detailed application that need to adapt to this radically different operating environment. The paper describes both the common issues and the different challenges of shielding design at different operational phases. Sample applications will be presented of both new plant and decommissioning projects that illustrate not only the robust nature of the processes being used, but also how they lead to cost-effective solutions making a substantive and appropriate contribution to radiological protection goals. PMID:16604700

  9. 77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-15

    ... COMMISSION Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors AGENCY... ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method NRC considers acceptable for use in... Revision 1 of Regulatory Guide 1.184, ``Decommissioning of Nuclear Power Reactors,'' dated July 2000.......

  10. 30 CFR 585.905 - When must I submit my decommissioning application?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... application? 585.905 Section 585.905 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Decommissioning Decommissioning Applications § 585.905 When must I submit my decommissioning application? You...

  11. 30 CFR 585.908 - What must I include in my decommissioning notice?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... notice? 585.908 Section 585.908 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Decommissioning Decommissioning Applications § 585.908 What must I include in my decommissioning notice? (a)...

  12. 30 CFR 585.908 - What must I include in my decommissioning notice?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... notice? 585.908 Section 585.908 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Decommissioning Decommissioning Applications § 585.908 What must I include in my decommissioning notice? (a)...

  13. 30 CFR 585.905 - When must I submit my decommissioning application?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... application? 585.905 Section 585.905 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Decommissioning Decommissioning Applications § 585.905 When must I submit my decommissioning application? You...

  14. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  15. 30 CFR 285.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... an Alternate Use RUE? 285.1019 Section 285.1019 Mineral Resources MINERALS MANAGEMENT SERVICE... Facilities Decommissioning An Alternate Use Rue § 285.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by MMS on a case-by-case basis,...

  16. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  17. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  18. ADVANTAGES, DISADVANTAGES, AND LESSONS LEARNED FROM MULTI-REACTOR DECOMMISSIONING PROJECTS

    SciTech Connect

    Morton, M.R.; Nielson, R.R.; Trevino, R.A.

    2003-02-27

    This paper discusses the Reactor Interim Safe Storage (ISS) Project within the decommissioning projects at the Hanford Site and reviews the lessons learned from performing four large reactor decommissioning projects sequentially. The advantages and disadvantages of this multi-reactor decommissioning project are highlighted.

  19. 30 CFR 250.1703 - What are the general requirements for decommissioning?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false What are the general requirements for decommissioning? 250.1703 Section 250.1703 Mineral Resources BUREAU OF SAFETY AND ENVIRONMENTAL ENFORCEMENT... Manager before decommissioning wells and from the Regional Supervisor before decommissioning platforms...

  20. 30 CFR 250.1703 - What are the general requirements for decommissioning?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false What are the general requirements for decommissioning? 250.1703 Section 250.1703 Mineral Resources BUREAU OF SAFETY AND ENVIRONMENTAL ENFORCEMENT... Manager before decommissioning wells and from the Regional Supervisor before decommissioning platforms...

  1. 26 CFR 1.468A-1T - Nuclear decommissioning costs; general rules (temporary).

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Nuclear decommissioning costs; general rules...-1T Nuclear decommissioning costs; general rules (temporary). (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income...

  2. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  3. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  4. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  5. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  6. A costing model for offshore decommissioning in California.

    PubMed

    Bressler, Andrew; Bernstein, Brock B

    2015-10-01

    California's 27 offshore oil and gas platforms will reach the end of their useful lifetimes sometime in the near future and will require decommissioning. Although existing leases require complete removal of all platforms and associated infrastructure, the underlying laws and regulations have changed in recent years to allow a number of alternative uses after decommissioning. In particular, AB 2503, signed into law in September 2010, provides for a rigs-to-reefs program that allows the state to accept ownership of decommissioned platforms in federal waters. Decisions about whether to remove platforms completely or leave them in place as artificial reefs will depend in part on the relative cost of the 2 options. In this study, we describe the design and use of a mathematical decision model that provides detailed cost estimates of complete and partial removal (to 85 feet below the water line) for California's offshore platforms. The model, PLATFORM, is loaded with Bureau of Safety and Environmental Enforcement (BSEE) and Bureau of Ocean Energy Management (BOEM) costs for complete removal, along with costs for partial removal calculated for this study and estimates of the uncertainty associated with decommissioning cost estimates. PLATFORM allows users to define a wide range of decommissioning and costing scenarios (e.g., number of platforms, choice of heavy lift vessel, shell mound removal, reef enhancement). As a benchmark cost, complete removal of all 27 offshore platforms, grouped into the 7 decommissioning projects defined by the most recent federal cost estimates produced in 2010, would cost an estimated $1.09 billion, whereas partial removal of these platforms, grouped into the same set of projects, would cost $478 million, with avoided costs of $616 million (with minor rounding).

  7. A costing model for offshore decommissioning in California.

    PubMed

    Bressler, Andrew; Bernstein, Brock B

    2015-10-01

    California's 27 offshore oil and gas platforms will reach the end of their useful lifetimes sometime in the near future and will require decommissioning. Although existing leases require complete removal of all platforms and associated infrastructure, the underlying laws and regulations have changed in recent years to allow a number of alternative uses after decommissioning. In particular, AB 2503, signed into law in September 2010, provides for a rigs-to-reefs program that allows the state to accept ownership of decommissioned platforms in federal waters. Decisions about whether to remove platforms completely or leave them in place as artificial reefs will depend in part on the relative cost of the 2 options. In this study, we describe the design and use of a mathematical decision model that provides detailed cost estimates of complete and partial removal (to 85 feet below the water line) for California's offshore platforms. The model, PLATFORM, is loaded with Bureau of Safety and Environmental Enforcement (BSEE) and Bureau of Ocean Energy Management (BOEM) costs for complete removal, along with costs for partial removal calculated for this study and estimates of the uncertainty associated with decommissioning cost estimates. PLATFORM allows users to define a wide range of decommissioning and costing scenarios (e.g., number of platforms, choice of heavy lift vessel, shell mound removal, reef enhancement). As a benchmark cost, complete removal of all 27 offshore platforms, grouped into the 7 decommissioning projects defined by the most recent federal cost estimates produced in 2010, would cost an estimated $1.09 billion, whereas partial removal of these platforms, grouped into the same set of projects, would cost $478 million, with avoided costs of $616 million (with minor rounding). PMID:25914378

  8. Decommissioning procedures for an 11 MeV self-shielded medical cyclotron after 16 years of working time.

    PubMed

    Calandrino, R; del Vecchio, A; Savi, A; Todde, S; Griffoni, V; Brambilla, S; Parisi, R; Simone, G; Fazio, F

    2006-06-01

    The present article describes the decommissioning of a compact, self-shielded, 11 MeV medical cyclotron. A Monte Carlo simulation of the possible nuclear reactions was performed in order to plan the decommissioning activities. In the course of the cyclotron dismantling, cyclotron components, shields, and floor concrete samples were measured. Residual activities were analyzed with a Ge(Li) detector and compared with simulation data. Doses to staff involved in the decommissioning procedure were monitored by individual TL dosimeters. The simulations identified five radioactive nuclides in shields and floor concrete: 55Fe and 45Ca (beta emitters, total specific activity: 2.29 x 10(4) Bq kg) and 152Eu, 154Eu, 60Co (gamma emitters, total specific activity: 1.62 x 10(3) Bq kg-1). Gamma-ray spectrometry confirmed the presence of gamma emitters, corresponding to a total specific activity of 3.40 x 10(2) Bq kg-1. The presence of the radioisotope 124Sb in the lead contained in the shield structure, corresponding to a simulated specific activity of 9.38 x 10(3) Bq kg-1, was experimentally confirmed. The measured dose from external exposure of the involved staff was <20 muSv, in accordance with the expected range of values between 10 and 20 muSv. The measured dose from intake was negligible. Finally, the decommissioning of the 11 MeV cyclotron does not represent a risk for the involved staff, but due to the presence of long-lived radioisotopes, the cyclotron components are to be treated as low level radioactive waste and stored in an authorized storage area. PMID:16691108

  9. Decommissioning of offshore oil and gas facilities: a comparative assessment of different scenarios.

    PubMed

    Ekins, Paul; Vanner, Robin; Firebrace, James

    2006-06-01

    A material and energy flow analysis, with corresponding financial flows, was carried out for different decommissioning scenarios for the different elements of an offshore oil and gas structure. A comparative assessment was made of the non-financial (especially environmental) outcomes of the different scenarios, with the reference scenario being to leave all structures in situ, while other scenarios envisaged leaving them on the seabed or removing them to shore for recycling and disposal. The costs of each scenario, when compared with the reference scenario, give an implicit valuation of the non-financial outcomes (e.g. environmental improvements), should that scenario be adopted by society. The paper concludes that it is not clear that the removal of the topsides and jackets of large steel structures to shore, as currently required by regulations, is environmentally justified; that concrete structures should certainly be left in place; and that leaving footings, cuttings and pipelines in place, with subsequent monitoring, would also be justified unless very large values were placed by society on a clear seabed and trawling access.

  10. Developing your leadership pipeline.

    PubMed

    Conger, Jay A; Fulmer, Robert M

    2003-12-01

    Why do so many newly minted leaders fail so spectacularly? Part of the problem is that in many companies, succession planning is little more than creating a list of high-potential employees and the slots they might fill. It's a mechanical process that's too narrow and hidebound to uncover and correct skill gaps that can derail promising young executives. And it's completely divorced from organizational efforts to transform managers into leaders. Some companies, however, do succeed in building a steady, reliable pipeline of leadership talent by marrying succession planning with leadership development. Eli Lilly, Dow Chemical, Bank of America, and Sonoco Products have created long-term processes for managing the talent roster throughout their organizations--a process Conger and Fulmer call succession management. Drawing on the experiences of these best-practice organizations, the authors outline five rules for establishing a healthy succession management system: Focus on opportunities for development, identify linchpin positions, make the system transparent, measure progress regularly, and be flexible. In Eli Lilly's "action-learning" program, high-potential employees are given a strategic problem to solve so they can learn something of what it takes to be a general manager. The company--and most other best-practice organizations--also relies on Web-based succession management tools to demystify the succession process, and it makes employees themselves responsible for updating the information in their personnel files. Best-practice organizations also track various metrics that reveal whether the right people are moving into the right jobs at the right time, and they assess the strengths and weaknesses not only of individuals but of the entire group. These companies also expect to be tweaking their systems continually, making them easier to use and more responsive to the needs of the organization.

  11. 77 FR 61826 - Pipeline Safety: Communication During Emergency Situations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-11

    ... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Communication During Emergency Situations AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Notice..., hazardous liquid, and liquefied natural gas pipeline facilities that operators should immediately...

  12. 76 FR 26793 - Pipeline Safety: Request for Special Permit

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-09

    ... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Request for Special Permit AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); Department of Transportation (DOT). ACTION: Notice. SUMMARY: Pursuant to the Federal pipeline safety laws, PHMSA is re- publishing this notice...

  13. 75 FR 43612 - Pipeline Safety: Request for Special Permit

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-26

    ... received from Dominion Transmission, Inc., a natural gas pipeline operator, seeking relief from compliance... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Request for Special Permit AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Notice. SUMMARY: Pursuant...

  14. Decommissioning and PIE of the MEGAPIE spallation target

    SciTech Connect

    Latge, C.; Henry, J.; Wohlmuther, M.; Dai, Y.; Gavillet, D.; Hammer, B.; Heinitz, S.; Neuhausen, J.; Schumann, D.; Thomsen, K.; Tuerler, A.; Wagner, W.; Gessi, A.; Guertin, A.; Konstantinovic, M.; Lindau, R.; Maloy, S.; Saito, S.

    2013-07-01

    A key experiment in the Accelerated Driven Systems roadmap, the MEGAwatt PIlot Experiment (MEGAPIE) (1 MW) was initiated in 1999 in order to design and build a liquid lead-bismuth spallation target, then to operate it into the Swiss spallation neutron facility SINQ at Paul Scherrer Institute. The target has been designed, manufactured, and tested during integral tests, before irradiation carried out end of 2006. During irradiation, neutron and thermo hydraulic measurements were performed allowing deep interpretation of the experiment and validation of the models used during design phase. The decommissioning, Post Irradiation Examinations and waste management phases were defined properly. The phases dedicated to cutting, sampling, cleaning, waste management, samples preparation and shipping to various laboratories were performed by PSI teams: all these phases constitute a huge work, which allows now to perform post-irradiation examination (PIE) of structural material, irradiated in relevant conditions. Preliminary results are presented in the paper, they concern chemical characterization. The following radio-nuclides have been identified by γ-spectrometry: {sup 60}Co, {sup 101}Rh, {sup 102}Rh, {sup 108m}Ag, {sup 110m}Ag, {sup 133}Ba, {sup 172}Hf/Lu, {sup 173}Lu, {sup 194}Hg/Au, {sup 195}Au, {sup 207}Bi. For some of these nuclides the activities can be easily evaluated from γ-spectrometry results ({sup 207}Bi, {sup 194}Hg/Au), while other nuclides can only be determined after chemical separations ({sup 108m}Ag, {sup 110m}Ag, {sup 195}Au, {sup 129}I, {sup 36}Cl and α-emitting {sup 208-210}Po). The concentration of {sup 129}I is lower than expected. The chemical analysis already performed on spallation and corrosion products in the lead-bismuth eutectic (LBE) are very relevant for further applications of LBE as a spallation media and more generally as a coolant.

  15. Idaho National Engineering Laboratory decontamination and decommissioning robotics development program

    SciTech Connect

    McKay, M.D.

    1993-04-01

    As part of the Idaho National Engineering Laboratory (INEL) Robotics Technology Development Program (RTDP) Decontamination & Decommissioning (D&D) robotics program, a task was designed to integrate the plasma arc cutting technology being developed under the Waste Facility Operations (WFO) robotics program into D&D cutting applications. The plasma arc cutting technology is based upon the use of a high energy plasma torch to cut metallic objects. Traditionally, D&D workers removing equipment and processes from a facility have used plasma arc cutting to accomplish this task. The worker is required to don a protective suit to shield from the high electromagnetic energy released from the cutting operation. Additionally, the worker is required to don protective clothing to shield against the radioactive materials and contamination. This protective clothing can become restrictive and cumbersome to work in. Because some of the work areas contain high levels of radiation, the worker is not allowed to dwell in the environment for sustained periods of time. To help alleviate some of the burdens required to accomplish this task, reduce or eliminate the safety hazardous to the worker, and reduce the overall cost of remediation, a program was established though the Office of Technology Development (OTD) to design and develop a robotic system capable of performing cutting operations using a plasma arc torch. Several D&D tasks were identified having potential for use of the plasma arc cutting technology. The tasks listed below were chosen to represent common D&D type activities where the plasma arc cutting technology can be applied.

  16. Mobile worksystems for decontamination and decommissioning operations. Final report

    SciTech Connect

    1997-02-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The Phase I effort was based on a robot called the Remote Work Vehicle (RWV) that was previously developed by CMU for use in D&D operations at the Three Mile Island Unit 2 Reactor Building basement. During Phase I of this program, the RWV was rehabilitated and upgraded with contemporary control and user interface technologies and used as a testbed for remote D&D operations. We established a close working relationship with the DOE Robotics Technology Development Program (RTDP). In the second phase, we designed and developed a next generation mobile worksystem, called Rosie, and a semi-automatic task space scene analysis system, called Artisan, using guidance from RTDP. Both systems are designed to work with and complement other RTDP D&D technologies to execute selective equipment removal scenarios in which some part of an apparatus is extricated while minimally disturbing the surrounding objects. RTDP has identified selective equipment removal as a timely D&D mission, one that is particularly relevant during the de-activation and de-inventory stages of facility transitioning as a means to reduce the costs and risks associated with subsequent surveillance and monitoring. In the third phase, we tested and demonstrated core capabilities of Rosie and Artisan; we also implemented modifications and enhancements that improve their relevance to DOE`s facility transitioning mission.

  17. Korea Research Reactor -1 & 2 Decommissioning Project in Korea

    SciTech Connect

    Park, S. K.; Chung, U. S.; Jung, K. J.; Park, J. H.

    2003-02-24

    Korea Research Reactor 1 (KRR-1), the first research reactor in Korea, has been operated since 1962, and the second one, Korea Research Reactor 2 (KRR-2) since 1972. The operation of both of them was phased out in 1995 due to their lifetime and operation of the new and more powerful research reactor, HANARO (High-flux Advanced Neutron Application Reactor; 30MW). Both are TRIGA Pool type reactors in which the cores are small self-contained units sitting in tanks filled with cooling water. The KRR-1 is a TRIGA Mark II, which could operate at a level of up to 250 kW. The second one, the KRR-2 is a TRIGA Mark III, which could operate at a level of up 2,000 kW. The decontamination and decommissioning (D & D) project of these two research reactors, the first D & D project in Korea, was started in January 1997 and will be completed to stage 3 by 2008. The aim of this decommissioning program is to decommission the KRR-1 & 2 reactors and to decontaminate the residual building structure s and the site to release them as unrestricted areas. KAERI (Korea Atomic Energy Research Institute) submitted the decommissioning plan and the environmental impact assessment reports to the Ministry of Science and Technology (MOST) for the license in December 1998, and was approved in November 2000.

  18. Applying laser technology to decommissioning for nuclear power plant

    NASA Astrophysics Data System (ADS)

    Saishu, Sadanori; Abe, Seiji; Inoue, T.

    2000-01-01

    Laser technology has much possibility to accomplish nuclear facility decommissioning effective and the laser application to cutting technique and decontamination technique is considered in Japan. Nuclear Power Engineering Corporation had developed CO laser for cutting technique, and had developed YAG laser for decontamination.

  19. Worldwide Overview of Lessons Learned from Decommissioning Projects

    SciTech Connect

    Laraia, Michele

    2008-01-15

    With an increasing number of radioactive facilities and reactors now reaching the end of their useful life and being taken out of service, there is a growing emphasis worldwide on the safe and efficient decommissioning of such plants. There is a wealth of experience already gained in decommissioning projects for all kinds of nuclear facilities. It is now possible to compare and discuss progress and accomplishments worldwide. In particular, rather than on the factual descriptions of projects, technologies and case histories, it is important to focus on lessons learned: in this way, the return of experience is felt to effectively contribute to progress. Key issues - inevitably based on a subjective ranking - are presented in this paper. Through the exchange of lessons learned, it is possible to achieve full awareness of the need for resources for and constraints of safe and cost-effective decommissioning. What remains now is the identification of specific, remaining issues that may hinder or delay the smooth progress of decommissioning. To this end, lessons learned provide the necessary background information; this paper tries to make extensive use of practical experience gained by the international community.

  20. Recent Trends in the Adequacy of Nuclear Plant Decommissioning Funding

    SciTech Connect

    Williams, D. G.

    2002-02-26

    Concerned about the potential cost and sufficiency of funds to decommission the nation's nuclear power plants, the Congress asked the U.S. General Accounting Office (GAO) to assess the adequacy, as of December 31, 1997, of electric utilities'; funds to eventually decommission their plants. GAO's report (GAO/RCED-99-75) on this issue addressed three alternative assumption scenarios--baseline (most likely), optimistic, and pessimistic; and was issued in May 1999. This paper updates GAO's baseline assessment of fund adequacy in 1997, and extends the analysis through 2000. In 2000, we estimate that the present value cost to decommission the nation's nuclear plants is about $35 billion; utility fund balances are about $29 billion. Both our two measures of funding adequacy for utilities are on average not only much above ideal levels, but also overall have greatly improved since 1997. However, certain utilities still show less than ideal fund balances and annual contributions. We suggest that the range of these results among the individual utilities is a more important policy measure to assess the adequacy of decommissioning funding than is the funding adequacy for the industry as a whole.

  1. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 18 Conservation of Power and Water Resources 1 2012-04-01 2012-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  2. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 18 Conservation of Power and Water Resources 1 2014-04-01 2014-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  3. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  4. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 18 Conservation of Power and Water Resources 1 2013-04-01 2013-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  5. Integration of improved decontamination and characterization technologies in the decommissioning of the CP-5 research reactor

    SciTech Connect

    Bhattacharyya, S. K.; Boing, L. E.

    2000-02-17

    The aging of research reactors worldwide has resulted in a heightened awareness in the international technical decommissioning community of the timeliness to review and address the needs of these research institutes in planning for and eventually performing the decommissioning of these facilities. By using the reactors already undergoing decommissioning as test beds for evaluating enhanced or new/innovative technologies for decommissioning, it is possible that new techniques could be made available for those future research reactor decommissioning projects. Potentially, the new technologies will result in: reduced radiation doses to the work force, larger safety margins in performing decommissioning and cost and schedule savings to the research institutes in performing the decommissioning of these facilities. Testing of these enhanced technologies for decontamination, dismantling, characterization, remote operations and worker protection are critical to furthering advancements in the technical specialty of decommissioning. Furthermore, regulatory acceptance and routine utilization for future research reactor decommissioning will be assured by testing and developing these technologies in realistically contaminated environments prior to use in the research reactors. The decommissioning of the CP-5 Research Reactor is currently in the final phase of dismantlement. In this paper the authors present results of work performed at Argonne National Laboratory (ANL) in the development, testing and deployment of innovative and/or enhanced technologies for the decommissioning of research reactors.

  6. INTERGALACTIC 'PIPELINE' FUNNELS MATTER BETWEEN COLLIDING GALAXIES

    NASA Technical Reports Server (NTRS)

    2002-01-01

    This visible-light picture, taken by NASA's Hubble Space Telescope, reveals an intergalactic 'pipeline' of material flowing between two battered galaxies that bumped into each other about 100 million years ago. The pipeline [the dark string of matter] begins in NGC 1410 [the galaxy at left], crosses over 20,000 light-years of intergalactic space, and wraps around NGC 1409 [the companion galaxy at right] like a ribbon around a package. Although astronomers have taken many stunning pictures of galaxies slamming into each other, this image represents the clearest view of how some interacting galaxies dump material onto their companions. These results are being presented today at the 197th meeting of the American Astronomical Society in San Diego, CA. Astronomers used the Space Telescope Imaging Spectrograph to confirm that the pipeline is a continuous string of material linking both galaxies. Scientists believe that the tussle between these compact galaxies somehow created the pipeline, but they're not certain why NGC 1409 was the one to begin gravitationally siphoning material from its partner. And they don't know where the pipeline begins in NGC 1410. More perplexing to astronomers is that NGC 1409 is seemingly unaware that it is gobbling up a steady flow of material. A stream of matter funneling into the galaxy should have fueled a spate of star birth. But astronomers don't see it. They speculate that the gas flowing into NGC 1409 is too hot to gravitationally collapse and form stars. Astronomers also believe that the pipeline itself may contribute to the star-forming draught. The pipeline, a pencil-thin, 500 light-year-wide string of material, is moving a mere 0.02 solar masses of matter a year. Astronomers estimate that NGC 1409 has consumed only about a million solar masses of gas and dust, which is not enough material to spawn some of the star-forming regions seen in our Milky Way. The low amount means that there may not be enough material to ignite star birth

  7. Considerations, measurements and logistics associated with low-energy cyclotron decommissioning

    NASA Astrophysics Data System (ADS)

    Sunderland, J. J.; Erdahl, C. E.; Bender, B. R.; Sensoy, L.; Watkins, G. L.

    2012-12-01

    The University of Iowa's 20-year-old 17 MeV Scanditronix cyclotron underwent decommissioning in the summer of 2011. To satisfy local, state and federal regulations defining removal, transportation and long-term safe and environmentally secure disposal of the 22 ton activated cyclotron, a series of nuclear spectroscopic measurements were performed to characterize the nature and extent of proton and neutron activation of the 22-ton cyclotron, its associated targets, and the concrete wall that was demolished to remove the old cyclotron. Neutron activation of the concrete wall was minimal and below exempt concentrations resulting in standard landfill disposal. The cyclotron assessment revealed the expected array of short and medium-lived radionuclides. Subsequent calculations suggest that meaningful levels residual activity will have decayed virtually to background after 15 years, with the total residual activity of the entire cyclotron dropping below 37 MBq (1 mCi).

  8. Considerations, measurements and logistics associated with low-energy cyclotron decommissioning

    SciTech Connect

    Sunderland, J. J.; Erdahl, C. E.; Bender, B. R.; Sensoy, L.; Watkins, G. L.

    2012-12-19

    The University of Iowa's 20-year-old 17 MeV Scanditronix cyclotron underwent decommissioning in the summer of 2011. To satisfy local, state and federal regulations defining removal, transportation and long-term safe and environmentally secure disposal of the 22 ton activated cyclotron, a series of nuclear spectroscopic measurements were performed to characterize the nature and extent of proton and neutron activation of the 22-ton cyclotron, its associated targets, and the concrete wall that was demolished to remove the old cyclotron. Neutron activation of the concrete wall was minimal and below exempt concentrations resulting in standard landfill disposal. The cyclotron assessment revealed the expected array of short and medium-lived radionuclides. Subsequent calculations suggest that meaningful levels residual activity will have decayed virtually to background after 15 years, with the total residual activity of the entire cyclotron dropping below 37 MBq (1 mCi).

  9. Method and system for pipeline communication

    DOEpatents

    Richardson; John G.

    2008-01-29

    A pipeline communication system and method includes a pipeline having a surface extending along at least a portion of the length of the pipeline. A conductive bus is formed to and extends along a portion of the surface of the pipeline. The conductive bus includes a first conductive trace and a second conductive trace with the first and second conductive traces being adapted to conformally couple with a pipeline at the surface extending along at least a portion of the length of the pipeline. A transmitter for sending information along the conductive bus on the pipeline is coupled thereto and a receiver for receiving the information from the conductive bus on the pipeline is also couple to the conductive bus.

  10. Characterization of the Hanford 300 area burial grounds. Final report: decontamination and decommissioning

    SciTech Connect

    Phillips, S.J.; Ames, L.L.; Fitzner, R.E.; Gee, G.W.; Sandness, G.A.; Simmons, C.S.

    1980-01-01

    Pacific Northwest Laboratory conducted a series of investigations at the Hanford Site to develop technologies for characterizing and monitoring radioactive waste burial facilities that could be used in determining appropriate decommissioning alternatives. Specific objectives were to develop unique functional geophysics, geochemical, soil physics, numerical modeling, and biological methodologies needed to better characterize and monitor buried radioactive waste disposal sites. To meet these objectives the project was divided into four tasks: Task I, Geophysical Evaluation - Geophysical surveys were taken to locate and define the gross composition of waste materials. Task II, Geochemical Analysis - The interaction of disposed radionuclides with geologic media was analyzed through an integrated radiochemical procedure. Task III, Fluid Transport and Modeling - Computer modeling of water migration in partially saturated groundwater systems was verified with actual data collected at a field test facility used to monitor micrometeorological and geohydrological energy and mass transfer factors. Task IV, Biological Transport - Several biological organisms were evaluated for potential radionuclide uptake and transport. Along with the four tasks, the project included a review of pertinent literature and regulatory issues that might affect the alternatives selected. Surveys were taken of the surrounding area and specific sites and operations. The overall results indicated that the 300 Area Burial Grounds have been adequate in containing radioactive waste. Based on the results of the project, the alternatives identified for decommissioning these sites are exhumation and translocation, entombment, perpetual care, and abandonment. Perpetual care (currently used) appears to be the best decommissioning alternative for these burial grounds at this time. However, another alternative may be selected depending on future waste management policies, plans, or activities.

  11. Adapting Dismantling and Decommissioning Strategies to a Variety of Nuclear Fuel Cycle Facilities - 12237

    SciTech Connect

    Chambon, Frederic; Clement, Gilles

    2012-07-01

    AREVA has accumulated over 20 years of experience in managing and operating fuel cycle facilities Decontamination and Decommissioning (D and D) projects of many different types and a variety of scales, both as facility owner (at La Hague for example) and as prime contractor to external customers such as the French Atomic Energy Commission (at Marcoule). A specific Business Unit was created in 2008 to capitalize on this experience and to concentrate - in one division - the specific skills required to be successful and cost effective in decommissioning projects. Indeed one of the key lessons learned in the past decades is that decommissioning is a significantly different business as compared to normal operations of a nuclear facility. Almost all the functions of a project need to be viewed from a different angle, challenged and adapted consequently in order to optimize costs and schedule. Three examples follow to illustrate the point: Safety management needs to take into account the ever changing configuration of a plant under D and D (a quite new situation for the authorities). Production of waste is significantly different in term of volume, activities, conditioning and disposal path. Technology is important but technical issues are often less critical than good management and planning. Further examples and lessons learned are developed through reviewing the projects experience basis. AREVA has a long and vast experience in the cleanup and dismantling of a number of very large and complex nuclear facilities. This effort focused initially on AREVA's own plants and is expanding now to other customers. The setup of a specific Business Unit in 2008 to takeover this business allowed concentration of the skills and the lessons learned in a dedicated division so as to provide the best means to optimize safety, performance, costs and schedules. Indeed transitioning from operations to D and D of a nuclear facility is a quantum leap. The assistance from specialized teams can

  12. REALTIME MONITORING OF PIPELINES FOR THIRD-PARTY CONTACT

    SciTech Connect

    Gary L. Burkhardt

    2005-12-31

    location. The method can be used with pipelines having active CP systems in place without causing interference with operation of the CP system. The most appropriate use of IACC is monitoring of localized high-consequence areas where there is a significant risk of third-party contact (e.g. construction activity). The method also lends itself to temporary, low-cost installation where there is a short-term need for monitoring.

  13. 76 FR 29333 - Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-20

    ... review DOT's complete Privacy Act Statement in the Federal Register published on April 11, 2000 (65 FR... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical Hazardous Liquid Pipeline Safety Standards Committee...

  14. 78 FR 41496 - Pipeline Safety: Meetings of the Gas and Liquid Pipeline Advisory Committees

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-10

    ..., 2000, (65 FR 19477) or view the Privacy Notice at http://www.regulations.gov before submitting any such... Pipeline and Hazardous Materials Safety Administration Pipeline Safety: Meetings of the Gas and Liquid... Liquid Pipeline Advisory Committee (LPAC) also known as the Technical Hazardous Liquid Pipeline...

  15. Accelerating the Whiteshell Laboratories Decommissioning Through the Implementation of a Projectized and Delivery-Focused Organization - 13074

    SciTech Connect

    Wilcox, Brian; Mellor, Russ; Michaluk, Craig

    2013-07-01

    Whiteshell Laboratories (WL) is a nuclear research site in Canada that was commissioned in 1964 by Atomic Energy of Canada Limited. It covers a total area of approximately 4,375 hectares (10,800 acres) and includes the main campus site, the Waste Management Area (WMA) and outer areas of land identified as not used for or impacted by nuclear development or operations. The WL site employed up to 1100 staff. Site activities included the successful operation of a 60 MW organic liquid-cooled research reactor from 1965 to 1985, and various research programs including reactor safety research, small reactor development, fuel development, biophysics and radiation applications, as well as work under the Canadian Nuclear Fuel Waste Management Program. In 1997, AECL made a business decision to discontinue research programs and operations at WL, and obtained government concurrence in 1998. The Nuclear Legacy Liabilities Program (NLLP) was established in 2006 by the Canadian Government to remediate nuclear legacy liabilities in a safe and cost effective manner, including the WL site. The NLLP is being implemented by AECL under the governance of a Natural Resources Canada (NRCan)/AECL Joint Oversight Committee (JOC). Significant progress has since been made, and the WL site currently holds the only Canadian Nuclear Safety Commission (CNSC) nuclear research site decommissioning license in Canada. The current decommissioning license is in place until the end of 2018. The present schedule planned for main campus decommissioning is 30 years (to 2037), followed by institutional control of the WMA until a National plan is implemented for the long-term management of nuclear waste. There is an impetus to advance work and complete decommissioning sooner. To accomplish this, AECL has added significant resources, reorganized and moved to a projectized environment. This presentation outlines changes made to the organization, the tools implemented to foster projectization, and the benefits

  16. California Natural Gas Pipelines: A Brief Guide

    SciTech Connect

    Neuscamman, Stephanie; Price, Don; Pezzola, Genny; Glascoe, Lee

    2013-01-22

    The purpose of this document is to familiarize the reader with the general configuration and operation of the natural gas pipelines in California and to discuss potential LLNL contributions that would support the Partnership for the 21st Century collaboration. First, pipeline infrastructure will be reviewed. Then, recent pipeline events will be examined. Selected current pipeline industry research will be summarized. Finally, industry acronyms are listed for reference.

  17. OMAE 1993: Proceedings. Volume 5: Pipeline technology

    SciTech Connect

    Yoon, M.; Murray, A.; Thygesen, J.

    1993-01-01

    This volume of conference proceedings is volume five of a five volume series dealing with offshore and arctic pipeline, marine riser, platforms, and ship design and engineering. This volume is a result of increased use of pipeline transportation for oil, gas, and liquid products and the resultant need for lower design and operating costs. Papers in this conference cover topics on environmental considerations, pipeline automation, computer simulation techniques, materials testing, corrosion protection, permafrost problems, pipeline integrity, geotechnical concerns, and offshore engineering problems.

  18. 30 CFR 250.1005 - Inspection requirements for DOI pipelines.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false Inspection requirements for DOI pipelines. 250... Pipelines and Pipeline Rights-of-Way § 250.1005 Inspection requirements for DOI pipelines. (a) Pipeline... indication of pipeline leakage. The results of these inspections shall be retained for at least 2 years...

  19. World pipeline construction to slip for 1994 and beyond

    SciTech Connect

    Koen, A.D.; True, W.R.

    1994-02-07

    World pipeline construction planned in 1994 and beyond has fallen in the past year, reflecting uncertainties in energy markets. Still, significant expansions are under way or planned for Latin America, Asia and the Pacific regions, and Europe. Latest Oil and Gas Journal data, derived from its survey of world pipeline operators, industry sources, and published information, show more than 55,000 miles of crude oil, product, and natural gas pipeline planned for 1994 and beyond. The data include projections for pipeline construction in Russia and former republics of the Soviet Union. Western Russia and all countries west of the Ural Mountains are included under totals for Europe, eastern Russia and countries east of the Urals under totals for the Asia-Pacific region. The paper discusses the following: European gas lines; North Sea projects; Gulf of Thailand; Yacheng subsea pipeline; Australian gas lines; other Asian lines; Russian activity; Algeria-Europe gas lines; Southeast US; Gulf gathering systems; Western US; South America; Trans-Ecuadorian expansion; Chilean gas network; and Bolivia-Brazil gas line.

  20. 49 CFR 195.210 - Pipeline location.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 3 2013-10-01 2013-10-01 false Pipeline location. 195.210 Section 195.210 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  1. 49 CFR 195.422 - Pipeline repairs.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Pipeline repairs. 195.422 Section 195.422 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  2. 49 CFR 195.210 - Pipeline location.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Pipeline location. 195.210 Section 195.210 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  3. 49 CFR 195.422 - Pipeline repairs.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 3 2014-10-01 2014-10-01 false Pipeline repairs. 195.422 Section 195.422 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  4. 27 CFR 19.274 - Pipelines.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Pipelines. 19.274 Section... THE TREASURY LIQUORS DISTILLED SPIRITS PLANTS Construction, Equipment and Security § 19.274 Pipelines. (a) General. (1) Pipelines for the conveyance of spirits, denatured spirits, articles, or wines...

  5. 49 CFR 195.210 - Pipeline location.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 3 2012-10-01 2012-10-01 false Pipeline location. 195.210 Section 195.210 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  6. 49 CFR 195.422 - Pipeline repairs.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Pipeline repairs. 195.422 Section 195.422 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  7. 49 CFR 195.210 - Pipeline location.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 3 2014-10-01 2014-10-01 false Pipeline location. 195.210 Section 195.210 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  8. 27 CFR 19.587 - Pipelines.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Pipelines. 19.587 Section... THE TREASURY LIQUORS DISTILLED SPIRITS PLANTS Containers and Marks Containers § 19.587 Pipelines. Pursuant to the provisions of this part, pipelines which conform to the requirements of § 19.274 may...

  9. 49 CFR 195.422 - Pipeline repairs.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 3 2012-10-01 2012-10-01 false Pipeline repairs. 195.422 Section 195.422 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  10. 49 CFR 195.210 - Pipeline location.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Pipeline location. 195.210 Section 195.210 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  11. 49 CFR 195.422 - Pipeline repairs.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 3 2013-10-01 2013-10-01 false Pipeline repairs. 195.422 Section 195.422 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS LIQUIDS...

  12. The RoboPol pipeline and control system

    NASA Astrophysics Data System (ADS)

    King, O. G.; Blinov, D.; Ramaprakash, A. N.; Myserlis, I.; Angelakis, E.; Baloković, M.; Feiler, R.; Fuhrmann, L.; Hovatta, T.; Khodade, P.; Kougentakis, A.; Kylafis, N.; Kus, A.; Modi, D.; Paleologou, E.; Panopoulou, G.; Papadakis, I.; Papamastorakis, I.; Paterakis, G.; Pavlidou, V.; Pazderska, B.; Pazderski, E.; Pearson, T. J.; Rajarshi, C.; Readhead, A. C. S.; Reig, P.; Steiakaki, A.; Tassis, K.; Zensus, J. A.

    2014-08-01

    We describe the data reduction pipeline and control system for the RoboPol project. The RoboPol project is monitoring the optical R-band magnitude and linear polarization of a large sample of active galactic nuclei that is dominated by blazars. The pipeline calibrates and reduces each exposure frame, producing a measurement of the magnitude and linear polarization of every source in the 13 arcmin × 13 arcmin field of view. The control system combines a dynamic scheduler, real-time data reduction, and telescope automation to allow high-efficiency unassisted observations.

  13. SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499

    SciTech Connect

    Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

    2010-01-04

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material

  14. The Classroom to Prison Pipeline

    ERIC Educational Resources Information Center

    Christensen, Linda

    2012-01-01

    The school-to-prison pipeline doesn't just begin with cops in the hallways and zero tolerance discipline policies. It begins when teachers fail to create a curriculum and a pedagogy that connects with students, that takes them seriously as intellectuals, that lets students know teachers care about them, that gives them the chance to channel their…

  15. Pipelined Flexible Krylov Subspace Methods

    NASA Astrophysics Data System (ADS)

    Sanan, Patrick; Schnepp, Sascha M.; May, Dave A.

    2015-04-01

    State-of-the-art geophysical forward models expend most of their computational resources solving large, sparse linear systems. To date, preconditioned Krylov subspace methods have proven to be the only algorithmically scalable approach to solving these systems. However, at `extreme scale', the global reductions required by the inner products within these algorithms become a computational bottleneck, and it becomes advantageous to use pipelined Krylov subspace methods. These allow overlap of global reductions with other work, at the expense of using more storage and local computational effort, including overhead required to synchronize overlapping work. An impediment to using currently-available pipelined solvers for relevant geophysical forward modeling is that they are not `flexible', meaning that they cannot support nonlinear or varying preconditioners. Such preconditioners are effective for solving challenging linear systems, notably those arising from modelling of Stokes flow with highly heterogeneous viscosity structure. To this end, we introduce, for the first time, Krylov subspace methods which are both pipelined and flexible. We implement and demonstrate pipelined, flexible Conjugate Gradient, GMRES, and Conjugate Residual methods, which will be made publicly available via the open source PETSc library. Our algorithms are nontrivial modifications of the flexible methods they are based on (that is, they are not equivalent in exact arithmetic), so we analyze them mathematically and through a number of numerical experiments employing multi-level preconditioners. We highlight the benefits of these algorithms by solving variable viscosity Stokes problems directly relevant to lithospheric dynamics.

  16. Corrosion beneath disbonded pipeline coatings

    SciTech Connect

    Beavers, J.A.; Thompson, N.G.

    1997-04-01

    The relationship between coatings, cathodic protection (CP), and external corrosion of underground pipelines is described. Historically, this problem has been addressed by focusing on the corrosion and CP processes associated with holidays, e.g., coating disbondment and CP current flow within the disbonded region. These issues and those associated with disbonded areas distant from holidays are also discussed.

  17. Seismic assessment of buried pipelines

    SciTech Connect

    Al-Chaar, G.; Brady, P.; Fernandez, G.

    1995-12-31

    A structure and its lifelines are closely linked because the disruption of lifeline systems will obstruct emergency service functions that are vitally needed after an earthquake. As an example of the criticality of these systems, the Association of Bay Area Government (ABAG) recorded thousands of leaks in pipelines that resulted in more than twenty million gallons of hazardous materials being released in several recorded earthquakes. The cost of cleaning the spills from these materials was very high. This information supports the development of seismic protection of lifeline systems. The US Army Corps of Engineers Construction Engineering Research Laboratories (USACERL) has, among its missions, the responsibility to develop seismic vulnerability assessment procedures for military installations. Within this mission, a preliminary research program to assess the seismic vulnerability of buried pipeline systems on military installations was initiated. Phase 1 of this research project resulted in two major studies. In the first, evaluating current procedures to seismically design or evaluate existing lifeline systems, the authors found several significant aspects that deserve special consideration and need to be addressed in future research. The second was focused on identifying parameters related to buried pipeline system vulnerability and developing a generalized analytical method to relate these parameters to the seismic vulnerability assessment of existing pipeline systems.

  18. Dynamic assessment of undersea pipeline bedding condition

    NASA Astrophysics Data System (ADS)

    Zhu, X. Q.; Hao, H.

    2007-04-01

    In this paper, a dynamic method will be developed to identify the surrounding bedding conditions of an undersea pipeline. The pipeline on the seabed is modeled as a simply supported beam on an elastic foundation. Two parameters are used to describe the scour or free span of the pipeline: they are the central location of the scour or span and the width of the scour or span. The study takes into account the dynamic interaction between the pipeline and the elastic foundation. The parameters are determined from natural frequencies of the pipeline. The effect of the number of natural frequencies and the measurement noise levels on the accuracy of the identification results of the pipeline bedding conditions is studied. Numerical simulation shows that the method is effective and reliable to assess the bedding conditions of the undersea pipeline.

  19. Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

    SciTech Connect

    Arave, A.E.; Rodman, G.R.

    1992-12-01

    The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D&D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D&D plans for the turbine building were prepared from 1979 through 1990. D&D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D&D activities were completed with no radiation exposure to the workers. The D&D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

  20. Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

    SciTech Connect

    Arave, A.E.; Rodman, G.R.

    1992-12-01

    The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D D plans for the turbine building were prepared from 1979 through 1990. D D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D D activities were completed with no radiation exposure to the workers. The D D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

  1. Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas

    SciTech Connect

    Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A.; Duncan, D.R.

    1994-08-01

    This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

  2. Effects of road decommissioning on carbon stocks, losses, and emissions in north coastal California

    USGS Publications Warehouse

    Madej, Mary A.; Seney, Joseph; van Mantgem, Philip

    2013-01-01

    During the last 3 decades, many road removal projects have been implemented on public and private lands in the United States to reduce erosion and other impacts from abandoned or unmaintained forest roads. Although effective in decreasing sediment production from roads, such activities have a carbon (C) cost as well as representing a carbon savings for an ecosystem. We assessed the carbon budget implications of 30 years of road decommissioning in Redwood National Park in north coastal California. Road restoration techniques, which evolved during the program, were associated with various carbon costs and savings. Treatment of 425 km of logging roads from 1979 to 2009 saved 72,000 megagrams (Mg) C through on-site soil erosion prevention, revegetation, and soil development on formerly compacted roads. Carbon sequestration will increase in time as forests and soils develop more fully on the restored sites. The carbon cost for this road decommissioning work, based on heavy equipment and vehicle fuel emissions, short-term soil loss, and clearing of vegetation, was 23,000 Mg C, resulting in a net carbon savings of 49,000 Mg C to date. Nevertheless, the degree to which soil loss is a carbon sink or source in steep mountainous watersheds needs to be further examined. The ratio of carbon costs to savings will differ by ecosystem and road removal methodology, but the procedure outlined here to assess carbon budgets on restoration sites should be transferable to other systems.

  3. INL - NNL an International Technology Collaboration Case Study - Advanced Fogging Technologies for Decommissioning - 13463

    SciTech Connect

    Banford, Anthony; Edwards, Jeremy; Demmer, Rick; Rankin, Richard; Hastings, Jeremy

    2013-07-01

    International collaboration and partnerships have become a reality as markets continue to globalize. This is the case in nuclear sector where over recent years partnerships commonly form to bid for capital projects internationally in the increasingly contractorized world and international consortia regularly bid and lead Management and Operations (M and O) / Parent Body Organization (PBO) site management contracts. International collaboration can also benefit research and technology development. The Idaho National Laboratory (INL) and the UK National Nuclear Laboratory (NNL) are internationally recognized organizations delivering leading science and technology development programmes both nationally and internationally. The Laboratories are actively collaborating in several areas with benefits to both the laboratories and their customers. Recent collaborations have focused on fuel cycle separations, systems engineering supporting waste management and decommissioning, the use of misting for decontamination and in-situ waste characterisation. This paper focuses on a case study illustrating how integration of two technologies developed on different sides of the Atlantic are being integrated through international collaboration to address real decommissioning challenges using fogging technology. (authors)

  4. Fixed-Price Subcontracting for Decontamination and Decommissioning of Small Facilities at Oak Ridge National Laboratory

    SciTech Connect

    Harper, M. A.; Julius, J. F. K.; McKenna, M. K.

    2002-02-26

    Abandoned facilities were decontaminated and decommissioned in preparation for final remediation of Solid Waste Storage Area (SWSA) 4 at Oak Ridge National Laboratory. The facilities varied in age from approximately 5 years to more than 40 years, with radiological conditions ranging from clean to highly contaminated with fission products. A fixed-price subcontract (FPSC) was awarded by the U.S. Department of Energy's (DOE's) Environmental Management (EM) Management and Integration (M&I) contractor for decontamination and decommissioning (D&D) of these facilities. Included in the FPSC scope were the following: preparation of pre-D&D regulatory documentation; demolition of surface structures to slab; stabilization of below-grade structures; waste management and disposal; and preparation of post-D&D regulatory documentation. Using stand-off techniques to the extent possible, building structures and ancillary equipment were prepared for demolition and demolished. A fixative coating system was used in conjunction with continuous water misting to control airborne contamination. Demolition waste consisted of two major streams: clean construction and demolition waste and low-level (radioactive) waste. The debris was size-reduced and packaged, again via remote means. At all times during the D&D, personnel safety, environmental compliance, and as low as reasonably achievable exposure considerations were paramount. Upon completion of D&D activities, each site was inspected and accepted by the M&I contractor. This project is a success story for fixed-price subcontracting of D&D work under DOE's M&I arrangement.

  5. Induction of auroral zone electric currents within the Alaska pipeline

    USGS Publications Warehouse

    Campbell, W.H.

    1978-01-01

    The Alaskar pipeline is a highly conducting anomaly extending 800 miles (1300 km) from about 62?? to 69?? geomagnetic latitude beneath the most active regions of the ionospheric electrojet current. The spectral behavior of the magnetic field from this current was analyzed using data from standard geomagnetic observatories to establish the predictable patterns of temporal and spatial changes for field pulsation periods between 5 min and 4 hr. Such behavior is presented in a series of tables, graphs and formulae. Using 2- and 3-layer models of the conducting earth, the induced electric fields associated with the geomagnetic changes were established. From the direct relationship of the current to the geomagnetic field variation patterns one can infer counterpart temporal and spatial characteristics of the pipeline current. The relationship of the field amplitudes to geomagnetic activity indices, Ap, and the established occurrence of various levels of Ap over several solar cycles were employed to show that about half of the time the induced currents in the pipe would be under 1 A for the maximum response oscillatory periods near 1 hr. Such currents should be of minimal consequence in corrosion effects for even a section of the pipeline unprotected by sacrificial electrodes. Of greater interest was the result that the extreme surges of current should reach over one-hundred amperes in the pipeline during high activity. ?? 1978 Birkha??user Verlag.

  6. Packaging, Transportation, and Disposal Logistics for Large Radioactively Contaminated Reactor Decommissioning Components

    SciTech Connect

    Lewis, Mark S.

    2008-01-15

    The packaging, transportation and disposal of large, retired reactor components from operating or decommissioning nuclear plants pose unique challenges from a technical as well as regulatory compliance standpoint. In addition to the routine considerations associated with any radioactive waste disposition activity, such as characterization, ALARA, and manifesting, the technical challenges for large radioactively contaminated components, such as access, segmentation, removal, packaging, rigging, lifting, mode of transportation, conveyance compatibility, and load securing require significant planning and execution. In addition, the current regulatory framework, domestically in Titles 49 and 10 and internationally in TS-R-1, does not lend itself to the transport of these large radioactively contaminated components, such as reactor vessels, steam generators, reactor pressure vessel heads, and pressurizers, without application for a special permit or arrangement. This paper addresses the methods of overcoming the technical and regulatory challenges. The challenges and disposition decisions do differ during decommissioning versus component replacement during an outage at an operating plant. During decommissioning, there is less concern about critical path for restart and more concern about volume reduction and waste minimization. Segmentation on-site is an available option during decommissioning, since labor and equipment will be readily available and decontamination activities are routine. The reactor building removal path is also of less concern and there are more rigging/lifting options available. Radionuclide assessment is necessary for transportation and disposal characterization. Characterization will dictate the packaging methodology, transportation mode, need for intermediate processing, and the disposal location or availability. Characterization will also assist in determining if the large component can be transported in full compliance with the transportation

  7. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, draft report for comment. Volume 2

    SciTech Connect

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.

    1994-09-01

    On June 27, 1988, the U.S. Nuclear Regulatory Commission (NRC) published in the Federal Register (53 FR 24018) the final rule for the General Requirements for Decommissioning Nuclear Facilities. With the issuance of the final rule, owners and operators of licensed nuclear power plants are required to prepare, and submit to the NRC for review, decommissioning plans and cost estimates. The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s WNP-2, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives, which now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste. Costs for labor, materials, transport, and disposal activities are given in 1993 dollars. Sensitivities of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances are also examined.

  8. Finding of no significant impact, decontamination and decommissioning of Battelle Columbus Laboratories in Columbus and West Jefferson, Ohio

    SciTech Connect

    Not Available

    1990-01-01

    This Environmental Assessment has been developed by the Department of Energy in accordance with the requirements of the National Environmental Policy Act of 1969 for the proposed decommissioning of contaminated areas at the Battelle Memorial Institute, Columbus, Ohio. The discussions in Section 1.0 provide general background information on the proposed action. Section 2.0 describes the existing radiological and non-radiological condition of the Battelle Columbus Laboratories. Section 3.0 identifies the alternatives considered for the proposed action and describes in detail the proposed decommissioning project. Section 4.0 evaluates the potential risks the project poses to human health and the environment. Section 5.0 presents the Department of Energy's proposed action. As a result of nuclear research and development activities conducted over a period of approximately 43 years performed for the Department of Energy, its predecessor agencies, and under commercial contracts, the 15 buildings became contaminated with varying amounts of radioactive material. The Department of Energy no longer has a need to utilize the facilities and is contractually obligate to remove that contamination such that they can be used by their owners without radiological restrictions. This Environmental Assessment for the Battelle Columbus Laboratories Decommissioning Project is consistent with the direction from the Secretary of Energy that public awareness and participation be considered in sensitive projects and is an appropriate document to determine action necessary to satisfy the requirements of the National Environmental Policy Act. 30 refs., 6 figs., 9 tabs.

  9. Cost Estimating for Decommissioning of a Plutonium Facility--Lessons Learned From The Rocky Flats Building 771 Project

    SciTech Connect

    Stevens, J. L.; Titus, R.; Sanford, P. C.

    2002-02-26

    The Rocky Flats Closure Site is implementing an aggressive approach in an attempt to complete Site closure by 2006. The replanning effort to meet this goal required that the life-cycle decommissioning effort for the Site and for the major individual facilities be reexamined in detail. As part of the overall effort, the cost estimate for the Building 771 decommissioning project was revised to incorporate both actual cost data from a recently-completed similar project and detailed planning for all activities. This paper provides a brief overview of the replanning process and the original estimate, and then discusses the modifications to that estimate to reflect new data, methods, and planning rigor. It provides the new work breakdown structure and discusses the reasons for the final arrangement chosen. It follows with the process used to assign scope, cost, and schedule elements within the new structure, and development of the new code of accounts. Finally, it describes the project control methodology used to track the project, and provides lessons learned on cost tracking in the decommissioning environment.

  10. Carbon-14 Bioassay for Decommissioning of Hanford Reactors

    SciTech Connect

    Carbaugh, Eugene H.; Watson, David J.

    2012-05-01

    The old production reactors at the US Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for 14C radiobioassay of workers was identified. Technical issues associated with 14C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S 14C anticipated to be encountered. However the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of 14C are not credible, thus rendering moot the need for such bioassay.

  11. Carbon-14 bioassay for decommissioning of Hanford reactors.

    PubMed

    Carbaugh, Eugene H; Watson, David J

    2012-05-01

    The production reactors at the U.S. Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for ¹⁴C radiobioassay of workers was identified. Technical issues associated with ¹⁴C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S ¹⁴C anticipated to be encountered. However, the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of ¹⁴C are not credible, thus rendering moot the need for such bioassay.

  12. Carbon-14 bioassay for decommissioning of Hanford reactors.

    PubMed

    Carbaugh, Eugene H; Watson, David J

    2012-05-01

    The production reactors at the U.S. Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for ¹⁴C radiobioassay of workers was identified. Technical issues associated with ¹⁴C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S ¹⁴C anticipated to be encountered. However, the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of ¹⁴C are not credible, thus rendering moot the need for such bioassay. PMID:22469998

  13. Annual summary report on the Decontamination and Decommissioning Program at the Oak Ridge Y-12 Plant for the period ending September 30, 1992. Environmental Restoration Program

    SciTech Connect

    Not Available

    1993-02-01

    The Y-12 Decontamination and Decommissioning (D&D) Program provides for the ultimate disposition of plant process buildings and their supporting facilities. The overall objective is to enable the Y-12 Plant to meet applicable environmental regulations and Department of Energy (DOE) orders to protect human health and the environment from contaminated facilities through decommissioning activities. This objective is met by providing for the surveillance and maintenance (S&M) of accepted standby or shutdown facilities awaiting decommissioning; planning for decommissioning of these facilities; and implementing a program to accomplish the safe, cost-effective, and orderly disposition of contaminated facilities. The Y-12 D&D Program was organized during FY 1992 to encompass the needs of surplus facilities at the Y-12 Plant. The need existed for a program which would include Weapons Program facilities as well as other facilities used by several programs within the Y-12 Plant. Building 9201-4 (Alpha 4) is the only facility that is formally in the D&D Program. Funding for the work completed in FY 1992 was shared by the Environmental Restoration and Waste Management Program (EW-20) and Weapons Operations (GB-92). This report summarizes the FY 1992 D&D activities associated with Building 9201-4. A section is provided for each task; the tasks include surveillance, routine and special maintenance, safety, and D&D planning.

  14. Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

    SciTech Connect

    Jackson, P.K.; Freemerman, R.L.

    1989-11-01

    On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as the Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.

  15. Aroma potential of oak battens prepared from decommissioned oak barrels.

    PubMed

    Li, Sijing; Crump, Anna M; Grbin, Paul R; Cozzolino, Daniel; Warren, Peter; Hayasaka, Yoji; Wilkinson, Kerry L

    2015-04-01

    During barrel maturation, volatile compounds are extracted from oak wood and impart aroma and flavor to wine, enhancing its character and complexity. However, barrels contain a finite pool of extractable material, which diminishes with time. As a consequence, most barrels are decommissioned after 5 or 6 years. This study investigated whether or not decommissioned barrels can be "reclaimed" and utilized as a previously untapped source of quality oak for wine maturation. Oak battens were prepared from staves of decommissioned French and American oak barrels, and their composition analyzed before and after toasting. The oak lactone glycoconjugate content of untoasted reclaimed oak was determined by liquid chromatography-tandem mass spectrometry, while the concentrations of cis- and trans-oak lactone, guaiacol, 4-methlyguaiacol, vanillin, eugenol, furfural, and 5-methylfurfural present in toasted reclaimed oak were determined by gas chromatography-mass spectrometry. Aroma potential was then evaluated by comparing the composition of reclaimed oak with that of new oak. Comparable levels of oak lactone glycoconjugates and oak volatiles were observed, demonstrating the aroma potential of reclaimed oak and therefore its suitability as a raw material for alternative oak products, i.e., chips or battens, for the maturation of wine. The temperature profiles achieved during toasting were also measured to evaluate the viability of any yeast or bacteria present in reclaimed oak. PMID:25771908

  16. Evaluating alternatives for decommissioning California's offshore oil and gas platforms.

    PubMed

    Bernstein, Brock B

    2015-10-01

    This paper introduces a series of 6 additional papers in this issue that describe an in-depth analysis of options for decommissioning oil and gas platforms offshore southern California. Although current leases require lessees in both state and federal waters to completely remove all production facilities and restore the seafloor to its pre-platform condition, other options have emerged since these leases were signed. Laws and regulations in other jurisdictions (particularly in federal waters) have evolved to allow a number of other uses such as aquaculture, alternative energy production, and artificial reefing. In response, the California Natural Resources Agency initiated an effort to investigate the issues associated with these and other decommissioning alternatives. The papers in this series are the result of the second phase in this process, a broad investigation of the engineering, economic, and environmental costs and benefits of the most feasible and likely options. In addition to the project's final report, the authors produced an interactive mathematical decision model, PLATFORM, that enables users to explore the implications of different decommissioning projects and options, as well as the effects of different approaches to valuing the associated costs and benefits.

  17. Practitioner versus analyst methods: a nuclear decommissioning case study.

    PubMed

    Walker, Guy; Cooper, Mhairi; Thompson, Pauline; Jenkins, Dan

    2014-11-01

    A requirement arose during decommissioning work at a UK Magnox Nuclear Power Station to identify the hazards involved in removing High Dose Rate Items from a Cartridge Cooling Pond. Removing objects from the cooling pond under normal situations is a routine event with well understood risks but the situation described in this paper is not a routine event. The power station has shifted from an operational phase in its life-cycle to a decommissioning phase, and as such the risks, and procedures to deal with them, have become more novel and uncertain. This raises an important question. Are the hazard identification methods that have proven useful in one phase of the system lifecycle just as useful in another, and if not, what methods should be used? An opportunity arose at this site to put the issue to a direct test. Two methods were used, one practitioner focussed and in widespread use during the plant's operational phase (the Structured What-If method), the other was an analyst method (Cognitive Work Analysis). The former is proven on this site but might not be best suited to the novelty and uncertainty brought about by a shift in context from operations to decommissioning. The latter is not proven on this site but it is designed for novelty and uncertainty. The paper presents the outcomes of applying both methods to a real-world hazard identification task. PMID:24947001

  18. A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING

    SciTech Connect

    R. L. Demmer

    2011-04-01

    The Idaho National Laboratory (INL) has been at the forefront of developing methods to reduce the cost and schedule of deactivating spent fuel pools (SFP). Several pools have been deactivated at the INL using an underwater approach with divers. These projects provided a basis for the INL cooperation with the Dresden Nuclear Power Station Unit 1 SFP (Exelon Generation Company) deactivation. It represents the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating process. This approach has advantages in many aspects, particularly in reducing airborne contamination and allowing safer, more cost effective deactivation. The INL pioneered underwater coating process was used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by INL and Exelon to decommission SFPs using the underwater coating process. The rationale used to select the underwater coating process and the advantages and disadvantages are described. Special circumstances are also discussed, such as the use of a remotely-operated underwater vehicle to visually and radiologically map the pool areas that were not readily accessible. A larger project, the INTEC-603 SFP in-situ (grouting) deactivation, is reviewed. Several specific areas where special equipment was employed are discussed and a Lessons Learned evaluation is included.

  19. Evaluating alternatives for decommissioning California's offshore oil and gas platforms.

    PubMed

    Bernstein, Brock B

    2015-10-01

    This paper introduces a series of 6 additional papers in this issue that describe an in-depth analysis of options for decommissioning oil and gas platforms offshore southern California. Although current leases require lessees in both state and federal waters to completely remove all production facilities and restore the seafloor to its pre-platform condition, other options have emerged since these leases were signed. Laws and regulations in other jurisdictions (particularly in federal waters) have evolved to allow a number of other uses such as aquaculture, alternative energy production, and artificial reefing. In response, the California Natural Resources Agency initiated an effort to investigate the issues associated with these and other decommissioning alternatives. The papers in this series are the result of the second phase in this process, a broad investigation of the engineering, economic, and environmental costs and benefits of the most feasible and likely options. In addition to the project's final report, the authors produced an interactive mathematical decision model, PLATFORM, that enables users to explore the implications of different decommissioning projects and options, as well as the effects of different approaches to valuing the associated costs and benefits. PMID:25914401

  20. Study on Evaluation of Project Management Data for Decommissioning of Uranium Refining and Conversion Plant - 12234

    SciTech Connect

    Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo; Shibahara, Yuji; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Tanaka, Yoshio; Sugitsue, Noritake

    2012-07-01

    Some of nuclear facilities that would no longer be required have been decommissioned in JAEA (Japan Atomic Energy Agency). A lot of nuclear facilities have to be decommissioned in JAEA in near future. To implement decommissioning of nuclear facilities, it was important to make a rational decommissioning plan. Therefore, project management data evaluation system for dismantling activities (PRODIA code) has been developed, and will be useful for making a detailed decommissioning plan for an object facility. Dismantling of dry conversion facility in the uranium refining and conversion plant (URCP) at Ningyo-toge began in 2008. During dismantling activities, project management data such as manpower and amount of waste generation have been collected. Such collected project management data has been evaluated and used to establish a calculation formula to calculate manpower for dismantling equipment of chemical process and calculate manpower for using a green house (GH) which was a temporary structure for preventing the spread of contaminants during dismantling. In the calculation formula to calculate project management data related to dismantling of equipment, the relation of dismantling manpower to each piece of equipment was evaluated. Furthermore, the relation of dismantling manpower to each chemical process was evaluated. The results showed promise for evaluating dismantling manpower with respect to each chemical process. In the calculation formula to calculate project management data related to use of the GH, relations of GH installation manpower and removal manpower to GH footprint were evaluated. Furthermore, the calculation formula for secondary waste generation was established. In this study, project management data related to dismantling of equipment and use of the GH were evaluated and analyzed. The project management data, manpower for dismantling of equipment, manpower for installation and removal of GH, and secondary waste generation from GH were considered