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1

An aerial radiological survey of the Nevada Test Site  

SciTech Connect (OSTI)

A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the US Department of Energy's Nevada Test Site including three neighboring areas during August and September 1994. The survey team measured the terrestrial gamma radiation at the Nevada Test Site to determine the levels of natural and man-made radiation. This survey included the areas covered by previous surveys conducted from 1962 through 1993. The results of the aerial survey showed a terrestrial background exposure rate that varied from less than 6 microroentgens per hour (mR/h) to 50 mR/h plus a cosmic-ray contribution that varied from 4.5 mR/h at an elevation of 900 meters (3,000 feet) to 8.5 mR/h at 2,400 meters (8,000 feet). In addition to the principal gamma-emitting, naturally occurring isotopes (potassium-40, thallium-208, bismuth-214, and actinium-228), the man-made radioactive isotopes found in this survey were cobalt-60, cesium-137, europium-152, protactinium-234m an indicator of depleted uranium, and americium-241, which are due to human actions in the survey area. Individual, site-wide plots of gross terrestrial exposure rate, man-made exposure rate, and americium-241 activity (approximating the distribution of all transuranic material) are presented. In addition, expanded plots of individual areas exhibiting these man-made contaminations are given. A comparison is made between the data from this survey and previous aerial radiological surveys of the Nevada Test Site. Some previous ground-based measurements are discussed and related to the aerial data. In regions away from man-made activity, the exposure rates inferred from the gamma-ray measurements collected during this survey agreed very well with the exposure rates inferred from previous aerial surveys.

Hendricks, T J; Riedhauser, S R

1999-12-01T23:59:59.000Z

2

Radiological survey report for the Weldon Spring Raffinate Pits site, Weldon Spring, Missouri  

SciTech Connect (OSTI)

The Weldon Spring Site (WSS) is a US Department of Energy (DOE) surplus facility comprising the Raffinate Pits facility, the Quarry, and potentially contaminated vicinity properties. Radiological characterization of the WSS will be conducted in three phases: the Raffinate Pits facility, Quarry, and the vicinity properties. Bechtel National, Inc. (BNI) and its radiological support subcontractor, Eberline Instrument Corporation (EIC), conducted a radiological characterization survey of the Raffinate Pits during 1982 and 1983 in support of on-site construction work and a technical evaluation of site geology. The survey consisted of direct beta-gamma surface readings, near-surface gamma readings, exposure level measurements, and gamma-logs of boreholes. Soil samples were also collected from the surface, shallow boreholes, and trenches on the site. This report describes the radiological characterization of the Raffinate Pits facility, the procedures used to conduct the survey, the survey results, and their significance. 5 references, 9 figures, 8 tables.

Not Available

1984-08-01T23:59:59.000Z

3

An aerial radiological survey of the Salmon Site and surrounding area, Lamar County, Mississippi  

SciTech Connect (OSTI)

An aerial radiological survey was conducted over the former Atomic Energy Commission Test Site at the Salmon Site and surrounding area between April 20 and May 1, 1992. The Salmon Site is located in Lamar County, Mississippi, approximately 20 miles southwest of Hattiesburg, Mississippi. The purpose of the survey was to measure and document the gamma-ray environment of the Salmon Site and adjacent lands. A contour map showing gamma radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on a rectified aerial photograph of the area. The exposure rates within the area are between 5 and 8 {mu}R/h. The reported exposure rates include a cosmic-ray contribution estimated to be 3.7 {mu}R/h. Radionuclide assays of soil samples and in situ measurements, taken with a pressurized ion chamber and a high-purity germanium detector, were obtained at 4 locations within the survey boundaries. These measurements were taken in support of and are in agreement with the aerial data.

Kernan, W.J.

1994-05-01T23:59:59.000Z

4

Radiological survey results for the Peek Street site properties, Schenectady, New York  

SciTech Connect (OSTI)

The Peek Street Industrial Facility, located at 425 Peek Street, Schenectady, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1955. A variety of operations using radioactive materials were conducted at the site, but the main activities were to design an intermediate breeder reactor and to develop a chemical process for the recovery of uranium and plutonium from spent reactor fuel. Nonradioactive beryllium metal was machined on the site for breeder reactor application. The 4.5-acre site was decommissioned and released in October 1955. A radiological survey was conducted by Oak Ridge National Laboratory in November 1989. The survey included scan and grid point measurements of direct radiation levels outdoors on the five properties and inside the factory building, and radionuclide analysis of samples collected from each property. Radionuclide concentrations were determined in outdoor surface and subsurface soil samples from each property and in dust, debris, and structural materials from inside the factory building. Auger holes were logged to assess location and extent of possible subsurface residual soil radioactivity. Radionuclide concentrations were deter-mined in both indoor and outdoor water samples and in selected samples of vegetation. The presence of fixed and transferable surface residual radioactivity was investigated inside the factory building and on discarded materials outdoors on the property. High-volume air samples as well as additional selected indoor and outdoor soil samples were analyzed to determine levels of elemental beryllium.

Foley, R.D.; Cottrell, W.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

5

Results of the radiological survey at the Sacandaga site Glenville, New York  

SciTech Connect (OSTI)

The Sacandaga site, located on Sacandaga Road, Glenville, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1951. Originally used for the study and development of radar during World War II, the facilities housed later operations involving physics studies and sodium technology development in support of breeder reactor design and other AEC programs. Though not in use since the original equipment was dismantled and removed in the early 1950s, portions of the 51-acre site are known to contain buried rubble from demolished structures used in former operations. At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a characterization of current radiological conditions over the site was performed between August and October 1989. The survey included the measurement of direct radiation levels (gamma, alpha, and beta-gamma) over all surfaces both inside and outside the building and tunnel, radionuclide analysis of systematic, biased, and auger hole soil samples, and analysis of sediments from underground structures. Gamma logging of auger holes was conducted and removable contamination levels inside the tunnel were determined. Samples of soil and structural materials from within and around an excavated concrete bunker were analyzed to determine concentrations of radionuclides and nonradioactive elemental beryllium.

Foley, R.D.; Cottrell, W.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

6

Results of the radiological and beryllium verification survey at the Sacandaga Site, Glenville, New York (SY002V)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent verification radiological and non-radioactive beryllium survey at the Sacandaga Site, located on Sacandaga Road, Glenville, New York following limited remediation of the site by Allwash of Syracuse, Inc. At the time of this survey, only building P was still standing. A small concrete structure at the east of the property had been demolished and the debris hauled away, leaving only a pit. The purpose of the survey, conducted between April and August 1993, was to confirm the success of the remedial actions performed to remove any beryllium concentrations or radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter indoors and outdoors, alpha and beta scans inside building P, and the collection of soil, dust and debris samples and smears for radionuclide and beryllium analyses. Results of the survey demonstrated that all radiological and beryllium measurements on the property were within applicable DOE guidelines. Based on all data collected. the Sacandaga Site, Glenville, New York, conforms to all applicable radiological and non-radioactive beryllium guidelines established for this site by DOE and approved by the State of New York.

Foley, R.D.; Cottrell, W.D.; Johnson, C.A.

1994-09-01T23:59:59.000Z

7

COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE  

Office of Legacy Management (LM)

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8

Results of the radiological and beryllium verification survey at the Peek Street Site, Schenectady, New York (SY001V)  

SciTech Connect (OSTI)

At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent verification radiological and non-radioactive beryllium survey at the Peek Street site, located at 425 Peek Street, Schenectady, New York. The purpose of the survey, conducted during 1993 and continuing through January 1994, was to confirm the success of the remedial actions performed to remove any beryllium concentrations or radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at one meter indoors and outdoors, alpha and beta scans inside the structure, and the collection of soil, dust and debris samples and smears for radionuclide and beryllium analyses. Results of the survey demonstrated that all radiological and beryllium measurements on the property were within applicable DOE guidelines. Based on all data collected, the industrial property at 425 Peek Street and the adjacent state-owned bike path in Schenectady, New York, conforms to all applicable radiological and non-radioactive beryllium guidelines established for this site by DOE and approved by the State of New York.

Foley, R.D.; Johnson, C.A.; Carrier, R.F.; Allred, J.F.

1994-10-01T23:59:59.000Z

9

Radiological survey of the former Baker Brothers, Inc. site, 2551--2555 Harleau Place, Toledo, Ohio (BTO001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted investigative radiological surveys at the REMS, Inc., and the Doug Beet Company, 2551-2555 Harleau Place, Toledo, Ohio (BTO001) in 1988. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work contracted to the Manhattan Engineer District (MED). The survey included gamma scans; directly measured alpha, beta, and gamma radiation levels; transferable contamination levels; and soil, dust, debris, and air sampling for radionuclide analyses. The survey and sampling covered accessible portions of the exterior ground surface, roof, and interiors of buildings. Results of the surveys demonstrated four general areas having radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria for {sup 238}U outdoors and as surface contamination on shelves in one building.

Foley, R.D.; Floyd, L.M.

1992-03-01T23:59:59.000Z

10

Preliminary results of the radiological survey at the former Dow Chemical Company site, Madison, Illinois  

SciTech Connect (OSTI)

During the late 1950s and early 1960s, the former Dow Chemical Company plant, now owned and operated by Spectrulite Consortium Inc., supplied materials and provided services for the Atomic Energy Commission (AEC) under purchase orders issued by the Mallinckrodt Chemical Company, a primary AEC contractor. Information indicates that research and development work involving gamma-phase extrusion of uranium metal was conducted at the Dow Chemical plant. Because documentation establishing the current radiological condition of the property was unavailable, a radiological survey was conducted by members of the Measurement Applications and Development Group of the Oak Ridge National Laboratory in March 1989. The survey included: measurement of indoor gamma exposure rates; collection and radionuclide analysis of dust and debris samples; and measurements to determine alpha and beta-gamma surface contamination. The results of the survey demonstrate that Building 6, the area uranium extrusion and rod-straightening work occurred, is generally free of radioactive residuals originating from former DOE-sponsored activities. However, {sup 238}U- and {sup 232}Th-contaminated dust was found on overhead beams at the south end of Building 6. These findings suggest that past DOE-supported operations were responsible for uranium-contaminated beam dust in excess of guidelines in Building 6. However, the contamination is localized and limited in extent, rendering it highly unlikely that under present use an individual working in or frequenting these remote areas would receive a significant radiation exposure. We recommend that additional scoping survey measurements and sampling be performed to further define the extent of indoor uranium contamination southward to include Building 4 and northward throughout Building 6. 5 refs., 11 figs., 4 tabs.

Cottrell, W.D.; Williams, J.K.

1990-12-01T23:59:59.000Z

11

Results of the radiological survey at the former Alba Craft Laboratory site properties, Oxford, Ohio (OXO001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the former Alba Craft Laboratory Site Properties, Oxford, Ohio. The survey was performed in July and September of 1992. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, primarily [sup 238]U, from uranium machining operations conducted for National Lead of Ohio, a prime Atomic Energy Commission contractor. The survey included scan measurement of direct radiation levels inside and outside the former laboratory, outdoors on eight properties adjoining the former laboratory, and the city right-of-way adjacent to the surveyed properties. Radionuclide concentrations were determined in outdoor surface and subsurface soil samples taken from each property and the exterior of the laboratory. Fixed surface residual radioactivity was measured inside the laboratory and outside the building. Air samples were collected, direct exposure was measured, and samples were collected to measure transferable radioactivity inside the building. Results of the survey indicate areas where surface and soil contamination level s are above the DOE guidelines for uncontrolled areas.

Murray, M.E.; Brown, K.S.; Mathis, R.A.

1993-03-01T23:59:59.000Z

12

Radiological survey of Latty Avenue in the vicinity of the former Cotter site, Hazelwood/Berkeley, Missouri (LM001)  

SciTech Connect (OSTI)

A radiological survey was conducted over a proposed construction corridor in the vicinity of the former Cotter site at 9200 Latty Avenue. The survey included gamma exposure rates at the ground surface and at 1 m above the surface throughout the site, sampling of surface soil, sampling of subsurface soil from auger holes, gamma logging of auger holes, and sampling of subsurface water. The results of the survey demonstrated some degree of radioactive contamination in all areas of the construction corridor, extending north and south in some regions onto adjacent private properties. Redistribution of the contamination by flooding, surface runoff, and road and utility line activities was evident. The pattern of contamination ranged from widespread to isolated spots and was found to occur from near the surface to depths of approx.1.8 m. The most highly contaminated region was noted on both sides of Latty Avenue adjacent to the former Cotter site. Concentrations of /sup 230/Th in soil from that region were as high as 16,000 pCi/g.

Cottrell, W.D.; Carrier, R.F.

1987-05-01T23:59:59.000Z

13

Results of the radiological survey at the former Associate Aircraft Tool and Manufacturing Company site, Fairfield, Ohio (FOH001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from oak Ridge National Laboratory conducted a radiological survey of the former Associate Aircraft Tool and Manufacturing Company facility, Fairfield, Ohio. The survey was performed in July and September 1992. The purpose of the survey was to determine if the facility had become contaminated with residuals containing radioactive materials during the work performed under government contract from February to September, 1956. The survey included gamma scanning over a circumscribed area around and outside of the building, and gamma scanning over most accessible indoor floor surfaces as well as the collection of soil and other samples for radionuclide analyses. Roof trusses were beta-gamma scanned in locations where floor contamination was found. Results of the survey demonstrated radionuclide concentrations in indoor and outdoor samples, and radiation measurements over floor and overhead surfaces, in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines. Elevated uranium concentrations outdoors were limited to several small, isolated spots. Radiation measurements exceeded guidelines indoors over numerous spots and areas inside the building, mainly in the areas that had been used in the early government work.

Murray, M.E.; Carrier, R.F.; Mathis, R.A.

1993-03-01T23:59:59.000Z

14

Results of the radiological survey at the Sacandaga site Glenville, New York. Waste Management Research and Development Programs  

SciTech Connect (OSTI)

The Sacandaga site, located on Sacandaga Road, Glenville, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1951. Originally used for the study and development of radar during World War II, the facilities housed later operations involving physics studies and sodium technology development in support of breeder reactor design and other AEC programs. Though not in use since the original equipment was dismantled and removed in the early 1950s, portions of the 51-acre site are known to contain buried rubble from demolished structures used in former operations. At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a characterization of current radiological conditions over the site was performed between August and October 1989. The survey included the measurement of direct radiation levels (gamma, alpha, and beta-gamma) over all surfaces both inside and outside the building and tunnel, radionuclide analysis of systematic, biased, and auger hole soil samples, and analysis of sediments from underground structures. Gamma logging of auger holes was conducted and removable contamination levels inside the tunnel were determined. Samples of soil and structural materials from within and around an excavated concrete bunker were analyzed to determine concentrations of radionuclides and nonradioactive elemental beryllium.

Foley, R.D.; Cottrell, W.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

15

Radiological survey of the former uranium recovery pilot and process sites, Gardinier, Incorporated, Tampa, Florida. Final report  

SciTech Connect (OSTI)

A radiological survey was conducted at a former uranium recovery plant near Tampa, Florida, operated as a part of a phosphoric acid plant. The uranium recovery operations were conducted from 1951 through 1960, the primary goal being the extraction of uranium from phosphoric acid. Pilot operations were first carried out at a small plant, and full-scale extraction was later carried out at a larger adjacent process plant. The survey included measurement of the followng: beta-gamma dose rates at 1 cm from surfaces and external gamma radiation levels at the surfaces and 1 m above the floor inside the pilot operations building and process building and outdoors in areas around these buildings; fixed and transferable alpha and beta-gamma contamination levels on the floor, walls, ceilings, and roof of the process building and on the floor, walls, and ceiling of the pilot plant offices; concentrations of /sup 226/Ra and /sup 238/U in soil samples taken at grid points around the buildings and in residue samples taken inside the process building; concentrations of /sup 226/Ra and /sup 238/U in water and sediment samples taken outdoors on the site and the concentration of these same nuclides in background samples collected off the site. It was found that beta-gamma and/or alpha contamination levels on surfaces exceed current guidelines for the release of property for unrestricted use at some points inside the process building and in the outdoor area near the process building and pilot operations building. Some samples of soil and residue taken from the floor and equipment on the second level of the process building contained natural uranium in excess of 0.05% by weight and contained natural radium in excess of 900 pCi/g.

Haywood, F F; Goldsmith, W A; Leggett, R W; Doane, R W; Fox, W F; Shinpaugh, W H; Stone, D R; Crawford, D J

1981-03-01T23:59:59.000Z

16

Radiological Habits Survey: Dungeness, 2005  

E-Print Network [OSTI]

exposure 39 4.9 Water based activities 42 5. TERRESTRIAL RADIATION PATHWAYS 44 5.1 Terrestrial survey area.1 Direct radiation survey area 50 6.2 Residential activities 51 6.3 Leisure activities 51 6.4 Commercial 12 2. THE SURVEY 14 2.1 Site activity 14 2.2 Survey objectives 15 2.3 Survey areas 16 2.4 Conduct

17

Radiological characterization survey of the former Diamond Magnesium Company Company site, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001, DMP002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory performed an investigative radiological survey at the former Diamond Magnesium Company (DMC) site at 720 Fairport-Nursery Road, Painesville, Ohio, in September 1990. The purpose of the survey was to determine if the site is contaminated with radioactive residues as a result of federal government operation in the development of nuclear energy for defense-related projects. The survey of the site, separate parcels of which are currently owned by the Uniroyal Chemical Company (DMP001) and the Lonza Chemical Company (DMP002), included a gamma scan over the ground surface, determination of gamma exposure rates at the surface and at 1 m above the surface at grid points, collection and radionuclide analysis of soil samples, and directly measured radiation levels inside three buildings used during original DMC processing. Results of the survey revealed widespread radiological contamination outdoors on the Uniroyal property and several isolated spots of elevated radiation levels on the Lonza property. The contaminants consisted of radium, uranium, and thorium in surface and subsurface soil in concentrations exceeding DOE guidelines for the release of property for unrestricted use.

Foley, R.D.; Carrier, R.F.

1991-12-01T23:59:59.000Z

18

Radiological survey results at Beverly Harbor, Beverly, Massachusetts (VB025)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Beverly Harbor, Beverly, Massachusetts. The survey was performed in may 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to the harbor and neighboring areas. The survey included a surface gamma scan and the collection of soil and biological samples for radionuclide analyses.

Foley, R.D.; Johnson, C.A.

1992-08-01T23:59:59.000Z

19

Formerly utilized MED/AEC sites remedial action program: radiological survey of the former Virginia-Carolina Chemical Corporation Uranium Recovery Pilot Plant, Nichols, Florida. Final report  

SciTech Connect (OSTI)

The results of a radiological survey conducted at the site of a former uranium recovery pilot plant operated by the Virginia-Carolina Chemical Corporation is presented. All that remains of this operation is a concrete pad situated within the boundary of a phosphate products plant now operated by Conserv, Inc., at the Nichols, Florida site. The survey included measurements designed to characterize the residual radioactivity in the vicinity of this pilot plant and to compare the quantities with federal guidelines for the release of decontaminated property for unrestricted use. The results of this survey indicate that only small quantities of radioactivity exist above normal background levels for that area. Some soil contamination was found in the vicinity of a concrete pad on which the pilot plant stood. Much of this contamination was due to /sup 226/Ra and /sup 238/U. Some beta-gamma dose rates in excess of applicable guidelines were observed in this same area. External gamma-ray exposure rates at 1 m above the ground range from 20 to 100 ..mu..R/hr. None of the direct measurements of alpha contamination were above guideline levels.

Haywood, F F; Doane, R W; Goldsmith, W A; Shinpaugh, W H; Crawford, D J; Fox, W F; Leggett, R W; Stone, D R

1980-01-01T23:59:59.000Z

20

Nevada Test Site Radiological Control Manual  

SciTech Connect (OSTI)

This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

Radiological Control Managers' Council Nevada Test Site

2010-02-09T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Radiological survey of the Shpack Landfill, Norton, Massachusetts  

SciTech Connect (OSTI)

The results of a radiological survey of the Shpack Landfill, Norton, Massachusetts, are given in this report. The survey was conducted over approximately eight acres which had received radioactive wastes from 1946 to 1965. The survey included measurement of the following: external gamma radiation at the surface and at 1 m (3 ft) above the surface throughout the site; beta-gamma exposure rates at 1 cm (0.4 in.) from the surface throughout the site; concentrations of /sup 226/Ra, /sup 238/U, and /sup 235/U in surface and subsurface soil on the site; and concentrations of /sup 226/Ra, /sup 238/U, /sup 235/U, /sup 230/Th, and /sup 210/Pb in groundwater on the site and in surface water on and near the site. Results indicate that the radioactive contamination is confined to the site and to the swamp immediately adjacent to the site.

Cottrell, W.D.; Haywood, F.F.; Witt, D.A.; Myrick, T.E.; Goldsmith, W.A.; Shinpaugh, W.H.; Loy, E.T.

1981-12-01T23:59:59.000Z

22

I COMPREHENSIVE RADIOLOGICAL SURVEY I  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North - t ' v I tfi t7Bechtelim I

23

Site Energy Surveys  

E-Print Network [OSTI]

identified, screening is conducted to develop their economic attractiveness. This presentation reviews factors leading to the need for Site Energy Surveys, the objectives for conducting surveys, the approach utilized, considerations given to values...

Lockett, W., Jr.; Guide, J. J.

1981-01-01T23:59:59.000Z

24

Radiological Scoping Survey of the Scotia Depot, Scotia, NY  

SciTech Connect (OSTI)

The objectives of the radiological scoping survey were to collect adequate field data for use in evaluating the radiological condition of Scotia Depot land areas, warehouses, and support buildings.

Bailey, E. N.

2008-02-25T23:59:59.000Z

25

Radiological survey results at 4400 Piehl Road, Ottawa Lake, Michigan  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 4400 Piehl Road in Ottawa Lake, Michigan. The survey was performed in September, 1992. The purpose of the survey was to determine if materials containing uranium from work performed under government contract at the former Baker Brothers facility in Toledo, Ohio had been transported off-site to this neighboring area. The radiological survey included surface gamma scans indoors and outdoors, alpha and beta scans inside the house and attached garage, beta-gamma scans of the hard surfaces outside, and the collection of soil, water, and dust samples for radionuclide analyses. Results of the survey demonstrated that the majority of the measurements on the property were within DOE guidelines. However, the presence of isolated spots of uranium contamination were found in two areas where materials were allegedly transported to the property from the former Baker Brothers site. Uranium uptake by persons on the property by ingestion is fairly unlikely, but inhalation is a possibility. Based on these findings, it is recommended that the residential property at 4400 Piehl Road in Ottawa Lake, Michigan be considered for inclusion under FUSRAP.

Foley, R.D.; Johnson, C.A.

1993-04-01T23:59:59.000Z

26

Nevada National Security Site Radiological Control Manual  

SciTech Connect (OSTI)

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

Radiological Control Managers’ Council

2012-03-26T23:59:59.000Z

27

Autonomous mobile robot for radiologic surveys  

DOE Patents [OSTI]

An apparatus for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm.

Dudar, Aed M. (Augusta, GA); Wagner, David G. (Augusta, GA); Teese, Gregory D. (Aiken, SC)

1994-01-01T23:59:59.000Z

28

Autonomous mobile robot for radiologic surveys  

DOE Patents [OSTI]

An apparatus is described for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm. 5 figures.

Dudar, A.M.; Wagner, D.G.; Teese, G.D.

1994-06-28T23:59:59.000Z

29

Solar Site Survey Toolkit  

Broader source: Energy.gov [DOE]

After a couple outings, a principal technologist at Sandia National Laboratories saw a need for a travel kit that would have the necessary tools to make the task of site surveys more manageable and safer. They have had great success using the kit in the field already.

30

Radiological re-survey results at 130 West Central Avenue, Maywood, New Jersey (MJ029)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE), designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 130 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, ORNL conducted a radiological survey on this property. A second radiological survey by ORNL was conducted on this property in May, 1993 at the request of DOE after an ad hoc radiological survey, requested by a new property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the survey was to determine if residuals from the old MCW were present on the property, and if so, if any radiological elements present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological survey. The radiological re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses.

Murray, M.E.; Johnson, C.A.

1994-01-01T23:59:59.000Z

31

Radiological survey results at 12 Cliff Street, Beverly, Massachusetts (VB010)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 12 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

32

Radiological survey results at 20 Cliff Street, Beverly, Massachusetts (VB013)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 20 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

33

Radiological survey results at 6 Cliff Street, Beverly, Massachusetts (VB008)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak ridge National Laboratory conducted a radiological survey at 6 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

34

Radiological survey results at 5 Porter Street, Beverly, Massachusetts (VB019)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 5 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Site Remedial Action Program guidelines.

Foley, R.D.; Johnson, C.A.

1992-07-01T23:59:59.000Z

35

Radiological survey results at 19 Wellman Street, Beverly, Massachusetts (VB024)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 19 Wellman Street, Beverly, Massachusetts. The survey was performed in May 1991. The Purpose of the survey was to determine if uranium work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan, a beta-gamma scan of paved areas, and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Site Action Program guidelines.

Foley, R.D.; Johnson, C.A.

1992-07-01T23:59:59.000Z

36

Radiological survey results at 2 Porter Street, Beverly, Massachusetts (VB005)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 2 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples fore radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

37

Radiological survey results at 8 Cliff Street, Beverly, Massachusetts (VB009)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 8 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

38

Radiological survey results at 5 Cliff Street, Beverly, Massachusetts (VB018)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 5 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Johnson, C.A.

1992-08-01T23:59:59.000Z

39

Radiological survey results at 2 Cliff Street, Beverly, Massachusetts (VB007)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 2 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

40

Radiological survey results at 18 Cliff Street, Beverly, Massachusetts (VB012)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 18 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE mannerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Radiological survey results at 9 Porter Street, Beverly, Massachusetts (VB020)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 9 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Johnson, C.A.

1992-07-01T23:59:59.000Z

42

Radiological survey results at 15 Cliff Street, Beverly, Massachusetts (VB014)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 15 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

43

Radiological survey results at 14 Cliff Street, Beverly, Massachusetts (VB011)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 14 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Carrier, R.F.

1992-08-01T23:59:59.000Z

44

Radiological survey results at Porter Street City Park, Beverly, Massachusetts (VB026)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Porter Street City Park, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines

Foley, R.D.; Johnson, C.A.

1992-08-01T23:59:59.000Z

45

Radiological survey results at 9 and 11 Congress Street, Beverly, Massachusetts (VB002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 9 and 11 Congress Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan, a beta-gamma scan of paved areas, and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionucldie concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Uziel, M.S.

1992-05-01T23:59:59.000Z

46

Radiological survey results at 13 Congress Street, Beverly, Massachusetts (VB003)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 13 Congress Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan, a beta-gamma scan of paved areas, and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Uziel, M.S.

1992-07-01T23:59:59.000Z

47

Radiological Habits Survey: Chapelcross Liquid Effluent Pipeline, 2002  

E-Print Network [OSTI]

Radiological Habits Survey: Chapelcross Liquid Effluent Pipeline, 2002 Science commissioned Pipeline, 2002 The Centre for Environment, Fisheries and Aquaculture Science Lowestoft Laboratory Pakefield OF SURVEY 5 2.1 Pipeline description 5 2.2 Occupancy 6 2.3 Gamma dose rate measurements 7 3 SURVEY FINDINGS

48

Radiological survey results at 1 Shady Lane, Lodi, New Jersey (LJ095)  

SciTech Connect (OSTI)

The US Department of Energy (DOE) conducted remedial action at the Stepan property in Maywood, New Jersey and several vicinity properties in Lodi, New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Maywood Interim Storage Site (MISS), adjacent to the former Maywood Chemical Works facility. The property at One Shady Lane, Lodi, New Jersey was not one of these vicinity properties but was surveyed by DOE at the request of the owner. At the request of DOE, a team from Oak Ridge National Laboratory conducted a radiological survey at this property. The purpose of the survey, conducted in November 1994, was to confirm whether remedial actions were to be performed on the property in order to be in compliance with the identified Guidelines. The radiological survey included surface gamma scans and gamma readings at 1 meter, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at One Shady Lane, Lodi, New Jersey, were comparable to background levels in the area, and well within the limits prescribed by DOE radiological guidelines. Based on the results of the radiological survey data, this property does not meet guidelines for inclusion under FUSRAP.

Foley, R.D.; Johnson, C.A.

1995-07-01T23:59:59.000Z

49

The Northern Marshall Islands radiological survey: Data and dose assessments  

SciTech Connect (OSTI)

Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for {sup 137}Cs, {sup 90}Sr, {sup 239+240}Pu and {sup 241}Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from {sup 137}Cs accounts for about 10% to 30% of the dose. {sup 239+240}Pu and {sup 241}Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y{sup -1}. The background dose in the Marshall Islands is estimated to be 2.4 mSv y{sup -1} to 4.5 mSv y{sup -1}. The 50-y integral dose ranges from 0.5 to 65 mSv. 35 refs., 2 figs., 9 tabs.

Robison, W.L.; Noshkin, V.E.; Conrado, C.L. [Lawrence Livermore National Lab., CA (United States)] [and others

1997-07-01T23:59:59.000Z

50

Radiological survey results at 15 Congress Street, Beverly, Massachusetts (VB004)  

SciTech Connect (OSTI)

At the request of the US Department of energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 15 Congress Street, Beverly, Massachusetts. The survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan, a beta-gamma scan of paved areas, and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

Foley, R.D.; Uziel, M.S.

1992-07-01T23:59:59.000Z

51

Nevada Test Site Radiological Control Manual  

SciTech Connect (OSTI)

This document supersedes DOE/NV/11718--079, “NV/YMP Radiological Control Manual,” Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

Radiological Control Managers' Council - Nevada Test Site

2009-10-01T23:59:59.000Z

52

Radiological Habits Survey: Sellafield Review, 2005  

E-Print Network [OSTI]

Atomic Energy Authority (UKAEA) Windscale sites. It is also relevant to marine discharges from the Drigg

53

Considerations for PV Site Surveys  

E-Print Network [OSTI]

and building codes determine how a solar-electric (photovoltaic; PV) system is installed. A site survey- grid system, if solar energy is not collected, then the electrical loads may not be supported withoutConsiderations for PV Site Surveys John Wiles Sponsored by the U.S. Department of Energy this loss

Johnson, Eric E.

54

Radiological Survey of the U. S. Army Reserve Property at the Weldon Spring Site. Final Report. IR-300-302-1.02.  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou areDowntown Site -Miami -NewPlantSteel Co -Sites »

55

Radiological re-survey results at 146 West Central Avenue, Maywood, New Jersey (MJ034)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE) designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 146 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, Oak Ridge National Laboratory (ORNL) conducted a radiological survey on this property. A report describing this survey was published in 1989. A second radiological survey by ORNL was conducted on this property in May 1993 at the request of DOE after an ad hoc radiological survey, requested by the property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the second ORNL survey was to determine whether radioactive materials from the old MCW were present on the property, and if so, if radioactive materials present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological re-survey. The re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses. Results of this survey demonstrated that although elevated residual thorium-232 contamination was present in a few isolated spots on the southern end of the backyard, it did not exceed DOE guidelines.

Murray, M.E.; Johnson, C.A.

1994-05-01T23:59:59.000Z

56

Radiological survey results at 30 Cliff Street, Beverly, Massachusetts (VB022)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 30 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan, a beta-gamma scan of paved areas, and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines. The radionuclide distributions were not significantly different from typical background levels in the Beverly, Massachusetts, area.

Foley, R.D.; Johnson, C.A.

1992-07-01T23:59:59.000Z

57

Radiological verification survey results at 14 Peck Ave., Pequannock, New Jersey (PJ001V)  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W. R. Grace facility. The property at 14 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil and debris samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 14 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

Rodriguez, R.E.; Johnson, C.A.

1995-05-01T23:59:59.000Z

58

Radiological verification survey results at 7 Peck Ave., Pequannock, New Jersey (PJ003V)  

SciTech Connect (OSTI)

The US Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W.R. Grace facility. The property at 7 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 7 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

Rodriguez, R.E.; Johnson, C.A.

1995-05-01T23:59:59.000Z

59

Results of the radiological survey at Two Mile Creek, Tonawanda, New York (TNY002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Two Mile Creek, Tonawanda, New York. The survey was performed in November 1991 and May 1996. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been transported into the creek. The survey included a surface gamma scan in accessible areas near the creek and the collection of soil, sediment, and core samples for radionuclide analyses. Survey results indicate that no significant material originating at the Linde plant is presently in the creek. Three of the 1991 soil sample locations on the creek bank and one near the lake contained slightly elevated concentrations of {sup 238}U with radionuclide distributions similar to that found in materials resulting from former processing activities at the Linde site.

Murray, M.E.; Rodriguez, R.E.; Uziel, M.S.

1997-08-01T23:59:59.000Z

60

Northern Marshall Islands radiological survey: sampling and analysis summary  

SciTech Connect (OSTI)

A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for /sup 241/Am, 6569 for /sup 137/Cs, 4535 for /sup 239 +240/Pu, 4431 for /sup 90/Sr, 1146 for /sup 238/Pu, 269 for /sup 241/Pu, and 114 each for /sup 239/Pu and /sup 240/Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included.

Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

1981-07-23T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Radiological survey of the inactive uranium-mill tailings at Rifle, Colorado  

SciTech Connect (OSTI)

Results of radiological surveys of two inactive uranium-mill sites near Rifle, Colorado, in May 1976 are presented. These sites are referred to as Old Rifle and New Rifle. The calculated /sup 226/Ra inventory of the latter site is much higher than at the older mill location. Data on above-ground measurements of gamma exposure rates, surface and near-surface concentration of /sup 226/Ra in soil and sediment samples, concentration of /sup 226/Ra in water, calculated subsurface distribution of /sup 226/Ra, and particulate radionuclide concentrations in air samples are given. The data serve to define the extent of contamination in the vicinity of the mill sites and their immediate surrounding areas with tailings particles. Results of these measurements were utilized as technical input for an engineering assessment of these two sites.

Haywood, F.F.; Jacobs, D.J.; Ellis, B.S.; Hubbard, H.M. Jr.; Shinpaugh, W.H.

1980-06-01T23:59:59.000Z

62

Site survey method and apparatus  

DOE Patents [OSTI]

The disclosure of the invention is directed to a site survey ground vehicle based apparatus and method for automatically detecting source materials, such as radioactivity, marking the location of the source materials, such as with paint, and mapping the location of the source materials on a site. The apparatus of the invention is also useful for collecting and analyzing samples. The apparatus includes a ground vehicle, detectors mounted at the front of the ground vehicle, and individual detector supports which follow somewhat irregular terrain to allow consistent and accurate detection, and autolocation equipment. 19 figures.

Oldham, J.G.; Spencer, C.R.; Begley, C.L.; Meyer, H.R.

1991-06-18T23:59:59.000Z

63

Radiological survey of the inactive uranium-mill tailings at Gunnison, Colorado  

SciTech Connect (OSTI)

The findings of a radiological survey of the inactive uranium-mill site at Gunnison, Colorado, conducted in May 1976, are presented. Results of surface soil sample analyses and direct gamma radiation measurements indicate limited spread of tailings off the site. The only significant above background measurements off the site were obtained in an area previously covered by the tailings pile. There was little evidence of contamination of the surface or of unconfined groundwater in the vicinity of the tailings pile; however, the hydrologic conditions at the site indicate a potential for such contamination. The concentration of /sup 226/Ra in all water samples except one from the tailings pile was well below the concentration guide for drinking water. The subsurface distribution of /sup 226/Ra in 14 bore holes located on and around the tailings pile was calculated from gamma ray monitoring data obtained jointly with Ford, Bacon and Davis Utah Inc.

Haywood, F.F.; Jacobs, D.G.; Hubbard, H.M. Jr.; Ellis, B.S.; Shinpaugh, W.H.

1980-03-01T23:59:59.000Z

64

Results of the radiological survey at 48 Schlosser Drive, Rochelle Park, New Jersey (RJ005)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956.MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from thisthorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy(DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Schlosser Drive, Rochelle Park, New Jersey (RJO05), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

65

Results of the radiological survey at 77 Sinninger Street, Maywood, New Jersey (MJ052)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 77 Sinninger Street, Maywood, New Jersey (MJ052), was conducted on December 17, 1992. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1993-06-01T23:59:59.000Z

66

Results of the radiological survey at 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Th derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

67

Results of the radiological survey at 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

68

Results of the radiological survey at 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

69

Results of the radiological survey at 48 Schlosser Drive, Rochelle Park, New Jersey (RJ005)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956.MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from thisthorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy(DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Schlosser Drive, Rochelle Park, New Jersey (RJO05), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

70

Results of the radiological survey at 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

71

Results of the radiological survey at 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

72

Results of the radiological survey at 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003)  

SciTech Connect (OSTI)

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

73

Results of the radiological verification survey of the partial remediation at 90 Avenue C, Lodi, New Jersey (LJ079V)  

SciTech Connect (OSTI)

The property at 90 Avenue C, Lodi, New Jersey is one of the vicinity properties of the former Maywood Chemical Works, Maywood, New Jersey designated for remedial action by the US Department of Energy (DOE). In July 1991, Bechtel National, Inc. performed a partial remedial action on this property. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey in July, 1991 at this site. The purpose of the verification survey was to ensure the effectiveness of remedial actions performed within FUSRAP and to confirm the site`s compliance with DOE guidelines. The radiological survey included surface gamma scans indoors and outdoors, ground-level beta-gamma measurements, and systematic and biased soil and material sampling. Results of the verification survey demonstrated that all radiological measurements on the portions of the property that had been remediated were within DOE guidelines. However, there still remains a portion of the property to be remediated that is not covered by this verification survey.

Foley, R.D.; Johnson, C.A.

1994-02-01T23:59:59.000Z

74

Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study  

SciTech Connect (OSTI)

This is a review of the book ''Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study.''

Napier, Bruce A. (BATTELLE (PACIFIC NW LAB))

1999-01-01T23:59:59.000Z

75

Radiological survey results at the former Bridgeport Brass Company facility, Seymour, Connecticut  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of the former Bridgeport Brass Company facility, Seymour, Connecticut. The survey was performed in May 1992. The purpose of the survey was to determine if the facility had become contaminated with residuals containing radioactive materials during the work performed in the Ruffert building under government contract in the 1960s. The survey included a gamma scanning over a circumscribed area around the building, and gamma and beta-gamma scanning over all indoor surfaces as well as the collection of soil and other samples for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in indoor and outdoor samples, and radiation measurements over floor and wall surfaces, in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines. Elevated uranium concentrations outdoors were limited to several small, isolated spots. Radiation measurements exceeded guidelines indoors over numerous spots and areas inside the building, mainly in Rooms 1--6 that had been used in the early government work.

Foley, R.D.; Carrier, R.F.

1993-06-01T23:59:59.000Z

76

Background Radiation Survey of the Radiological/Nuclear Countermeasures Test and Evaluation Center  

SciTech Connect (OSTI)

In preparation for operations at the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC), the Department of Homeland Security Domestic Nuclear Detection Office (DHS/DNDO) requested that personnel from the Remote Sensing Laboratory (RSL) conduct a survey of the present radiological conditions at the facility. The measurements consist of the exposure rate from a high-pressure ion chamber (HPIC), high-resolution spectra from a high-purity germanium (HPGe) system in an in situ configuration, and low-resolution spectra from a sodium iodide (NaI) detector in a radiation detection backpack. Measurements with these systems were collected at discrete locations within the facility. Measurements were also collected by carrying the VECTOR backpack throughout the complex to generate a map of the entire area. The area was also to be surveyed with the Kiwi (an array of eight-2-inch x 4-inch x 16-inch NaI detectors) from the Aerial Measuring Systems; however, conflicts with test preparation activities at the site prevented this from being accomplished.

Colin Okada

2010-09-16T23:59:59.000Z

77

Uncertainty analyses for radiological assessments of St. Louis FUSRAP Sites  

SciTech Connect (OSTI)

Uncertainty analyses were performed in conjunction with radiological assessments of the Formerly Utilized Site Remedial Action Program (FUSRAP) St. Louis Downtown Site (SLDS), the Airport Site (SLAPS), and the Ball Field Site (SLBFS). Contaminants of concern at each location are natural uranium, radium, {sup 232}Th, and {sup 230}Th. The SLDS was used for uranium and thorium ore processing and includes an area of 45 acres. The SLAPS covers 22 acres and was used as a staging area for materials from the SLDS. Contaminants on the SLEFS were dispersed from the SLAPS, which involves an area of 80 acres. Significant levels of uranium contamination range from near zero to several thousand pCi/g and extend to about 20 feet in depth in a few locations at SLAPS and SLDS. Significant areas of peak radium and thorium concentrations are several hundred pCi/g with similar ranges in depth. Peak concentrations correspond to high grade ore. Radium and thorium constitute a greater radiological hazard than does uranium at all three locations. In order to satisfy the Environmental Protection Agency guideline for a lifetime risk of less than 10{sup -4}, the maximally exposed individual must receive less than about 4 mrem y{sup -1} if one assumes a risk of 5% per Sv. Based on the plant ingestion pathway, residual {sup 238}U, {sup 226}Ra, {sup 232}Th, and {sup 230}Th, concentrations of 400, 2, 4, and 40 pCi g{sup -1} at SLDS result in a 10{sup -4} lifetime risk with a 95% confidence level. Slightly different results were obtained for SLAPS and SLBFS. If more pathways are considered, such as radon, these values are even lower. Residual contamination levels could be increased by a factor of 25 if the historical Department of Energy limit of 100 mrem y{sup -1} is acceptable. The volume of contaminated soil that presents a 10{sup -4} lifetime risk is about 500,000 yd{sup 3}. The volume of soil contaminated to greater than 15 pCi g{sup -1} of each radionuclide is about a factor of ten less.

Miller, L.F.; Spencer, K.M.; White, D.E. [Univ. of Tennessee, Knoxville, TN (United States)

1996-06-01T23:59:59.000Z

78

Final report of the radiological release survey of Building 11 at the Grand Junction Office Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 11 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

Johnson, R.K.; Corle, S.G.

1997-09-01T23:59:59.000Z

79

Final report of the radiological release survey of Building 19 at the Grand Junction Office Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 19 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

Johnson, R.K.; Corle, S.G.

1997-09-01T23:59:59.000Z

80

Final report of the radiological release survey of Building 54 at the Grand Junction Office Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 54 and the underlying soil were found not to be radiologically contaminated, and can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual release report for each GJO building.

Johnson, R.K.; Corle, S.G.

1997-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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81

Final report of the radiological release survey of Building 29 at the Grand Junction Office Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailing during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 29 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

Johnson, R.K.; Corle, S.G.

1997-09-01T23:59:59.000Z

82

Radiological Survey Results for Areas A1 North, A5A, A6, and B2 at the Molycorp Washington Remediation Project, Washington, Pennsylvania  

SciTech Connect (OSTI)

Perform radiological surveys of the Molycorp Washington Remediation Project (MWRP) facility in Washington, Pennsylvania

W.C. Adams

2007-03-13T23:59:59.000Z

83

Results of the independent radiological verification survey of the lower Sheffield Brook floodplain, Wayne, New Jersey  

SciTech Connect (OSTI)

Prior to 1971, the W.R. Grace Company processed and stored radioactive materials at Wayne, New Jersey, under license to the Atomic Energy Commission. Decontamination of structures and storage of waste materials on the property at the Wayne Interim Storage Site (WISS) took place in 1974. Surveys by the State of New Jersey Department of Environmental Protection and by Oak Ridge Associated Universities for the NRC in 1982 indicated that properties adjacent to the WISS contained surface contamination by radioactive residuals in amounts exceeding those acceptable under US Department of Energy (DOE) remedial action guidelines. At the request of DOE, remedial actions have been conducted by Bechtel National, Inc., to remove radioactive residuals from properties adjacent to the site. It is the policy of DOE to assign an independent verification contractor to ensure the effectiveness of remedial actions performed within the Formerly Utilized Sites Remedial Action Program. This report describes the methods and results of those studies that were conducted by the Measurement Applications and Development Group of the Oak Ridge National Laboratory for the lower Sheffield Brook floodplain west of the WISS. Based upon post-remedial action and verification survey data, it was concluded that residual soil concentrations and gamma levels following excavation and backfilling of the area are within the limits prescribed by DOE radiological guidelines. 12 refs., 6 figs., 8 tabs.

Yalcintas, M.G.; Carrier, R.F.

1989-05-01T23:59:59.000Z

84

Radiological survey of the inactive uranium-mill tailings at Falls City, Texas  

SciTech Connect (OSTI)

Results of a radiological survey conducted at the Falls City, Texas, site in July 1976 are presented. There are seven partial to fully stabilized tailings piles, and an overburden pile from an open-pit mine. Above ground gamma-ray exposure rate measurements show moderate levels of contamination throughout the area with a maximum exposure rate of 500 ..mu..R/hr above tailings pile 2. The average exposure rate over the different areas varied from 14 ..mu..R/hr over the southwest end of tailings pile 7 to 207 ..mu..R/hr over the northeast end of the same pile. Analyses of surface soil and dry-wash sediment samples, as well as calculations of subsurface /sup 226/Ra distribution, serve to define the spread of tailings around the area. Water erosion of the tailings is evident, but, because of abundant growth of vegetation on the tailings piles, wind erosion probably is not a major problem.

Haywood, F.F.; Christian, D.J.; Loy, E.T.; Lorenzo, D.; Ellis, B.S.

1980-10-01T23:59:59.000Z

85

Radiological survey of the inactive uranium-mill tailings at Durango, Colorado  

SciTech Connect (OSTI)

Results of a radiological survey of the inactive uranium-mill site at Durango, Colorado, conducted in April 1976, in cooperation with a team from Ford, Bacon and Davis Utah Inc., are presented together with descriptions of the instruments and techniques used to obtain the data. Direct above-ground gamma measurements and analysis of surface soil and sediment samples indicate movement of tailings from the piles toward Lightner Creek on the north and the Animas River on the east side of the piles. The concentration of /sup 226/Ra in the former raffinate pond area is only slightly above the background level. Two structures in Durango were found to contain high concentrations of airborne radon daughters, where tailings are known to have been utilized in construction. Near-background concentrations of radon daughters were found in a well-ventilated building close to the tailings.

Haywood, F.F.; Perdue, P.T.; Shinpaugh, W.H.; Ellis, B.S.; Chou, K.D.

1980-03-01T23:59:59.000Z

86

Results of the radiological verification survey at the former Herring-Hall-Marvin Safe Company, 1550 Grand Boulevard, Hamilton Ohio (HO001V)  

SciTech Connect (OSTI)

During the period between the 1940s and early 1950s, the Herring-Hall-Marvin Safe Company, 1550 Grand Boulevard, Hamilton, Ohio, was one company under subcontract to the Manhattan Engineer District (MED), and the Atomic Energy Commission (AEC), the lead agencies in the development of nuclear energy for defense-related projects. The US Department of Energy (DOE) conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, a radiological survey of the Herring-Hall-Marvin Safe Company facility was conducted, and after small fragments of uranium metal were removed, no beta or gamma radiation above background was detected and the building was dismissed from any additional DOE restrictions. In 1993, it was discovered that a portion of the actual machining work was conducted on the third floor of the facility, located in the southeastern comer of the building. At the request of DOE, this part of the facility was radiologically surveyed by an ORNL survey team to determine whether fixed surface contamination could be found that might exceed the DOE guidelines. Results of this radiological survey indicated {sup 238}U contamination in excess of the DOE criteria for surface contamination, and the site was recommended for remediation. In February and March of 1995, a verification survey of the third floor of the former Herring-Hall-Marvin Safe Company facility by an ORNL survey team was performed in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included gamma scans at the surface and at one meter, alpha and beta-gamma scans for fixed contamination, and smears for transferable contamination.

Murray, M.E.; allred, J.F.; Johnson, C.A.

1995-11-01T23:59:59.000Z

87

Surface radiological investigations at the proposed SWSA 7 Site, Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

A surface radiological investigation was conducted intermittently from June 1994 to June 1995 at the proposed site for Solid Waste Storage Area (SWSA) 7. The stimulus for this survey was the observation in June 1992 of a man`s trousers became contaminated with {sup 9O}Sr while he was reviewing work on top of the High Flux Isotope Reactor (HFIR) cooling tower. Radiation surveys identified {sup 9O}Sr on the roofs of older buildings at the HFIR site. Since no {sup 9O}Sr was found on buildings built between 1988 and 1990, the {sup 9O}Sr was thought to have been deposited prior to 1988. Later in 1992, beta particles were identified on a bulldozer that had been used in a wooded area southwest of the Health Physics Research Reactor (HPRR) Access Road. More recently in April 1995, {sup 9O}Sr particles were identified on the top side of ceiling tiles in the overhead area of a building in the HFIR Complex. Considering that the proposed SWSA 7 site was located between the HFIR complex and the HPRR Access Road, it was deemed prudent to investigate the possibility that beta particles might also be present at the SWSA 7 site. A possible explanation for the presence of these particles has been provided by long-time ORNL employees and retirees. Strontium-90 as the titanate was developed in the early 1960s as part of the Systems for Nuclear Auxiliary Power (SNAP) Program. Strontium titanate ({sup 90}SrTiO{sub 3}) was produced at the Fission Product Development Laboratory (Building 3517) in the ORNL main plant area. Waste from the process was loaded into a 1-in. lead-lined dumpster, which was transferred to SWSA 5 where it was dumped into a trench. Dumping allowed some articles to become airborne.

McKenzie, S.P.; Murray, M.E.; Uziel, M.S.

1995-08-01T23:59:59.000Z

88

Radiological Dose Assessment 8 2007 Site environmental report8-  

E-Print Network [OSTI]

) and 64 ± 10 mrem (640 ± 100 Sv) at off-site locations. Both on-and off-site dose measurements include doses measured using thermoluminescent dosimeters (TLDs) at 49 on-site and 15 off-site locations showed penetrating radiation expo- sures both on and off site. The direct measure- ments taken at the off-site

89

Radiological Dose Assessment 8 2006 Site environmental report8-  

E-Print Network [OSTI]

was 68 ± 11 mrem (680 ± 110 Sv) on site and 63 ± 9 mrem (630 ± 90 Sv) at off-site locations. Both of the average doses measured at 47 on-site and 15 off-site locations using thermoluminescent dosimeters (TLDs site. The direct measure- ments taken at the off-site locations are with the premise that off-site

90

Characterization Investigation Study: Volume 3, Radiological survey of surface soils  

SciTech Connect (OSTI)

The Feed Materials Production Center was constructed to produce high purity uranium metal for use at various Department of Energy facilities. The waste products from these operations include general uncontaminated scrap and refuse, contaminated and uncontaminated metal scrap, waste oils, low-level radioactive waste, co-contaminated wastes, mixed waste, toxic waste, sludges from water treatment, and fly ash from the steam plant. This material is estimated to total more than 350,000 cubic meters. Other wastes stored in this area include laboratory chemicals and other combustible materials in the burn pit; fine waste stream sediments in the clear well; fly ash and waste oils in the two fly ash areas; lime-alum sludges and boiler plant blowdown in the lime sludge ponds; and nonradioactive sanitary waste, construction rubble, and asbestos in the sanitary landfill. A systematic survey of the surface soils throughout the Waste Storage Area, associated on-site drainages, and the fly ash piles was conducted using a Field Instrument for Detecting Low-Energy Radiation (FIDLER). Uranium is the most prevalent radioactive element in surface soil; U-238 is the principal radionuclide, ranging from 2.2 to 1790 pCi/g in the general Waste Storage Area. The maximum values for the next highest activity concentrations in the same area were 972 pCi/g for Th-230 and 298 pCi/g for U-234. Elevated activity concentrations of Th-230 were found along the K-65 slurry line, the maximum at 3010 pCi/g. U-238 had the highest value of 761 pCi/g in the drainage just south of pit no. 5. The upper fly ash area had the highest radionuclide activity concentrations in the surface soils with the maximum values for U-238 at 8600 pCi/g, U-235 at 2190 pCi/g, U-234 at 11,400 pCi/g, Tc-99 at 594 pCi/g, Ra-226 at 279 pCi/g, and Th-230 at 164 pCi/g.

Solow, A.J.; Phoenix, D.R.

1987-12-01T23:59:59.000Z

91

Radiological Dose Assessment 8 2009 Site environmental report8-  

E-Print Network [OSTI]

was 71 ± 10 mrem (710 ± 100 Sv) and 65 ± 7 mrem (650 ± 70 Sv) at off-site locations. Both on- and off-site-site and 14 TLDs off-site showed that there was no external dose contribution from BNL operations penetrating radiation expo- sures at both on- and off-site locations. The di- rect measurements taken

92

Radiological Final Status Survey of the Hammond Depot, Hammond, Indiana  

SciTech Connect (OSTI)

ORISE conducted extensive scoping, characterization, and final status surveys of land areas and structures at the DNSC’s Hammond Depot located in Hammond, Indiana in multiple phases during 2005, 2006 and 2007.

T.J. Vitkus

2008-04-07T23:59:59.000Z

93

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site  

SciTech Connect (OSTI)

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 [Public Law (PL) 95-6041]. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. The remedial action at the processing site will be conducted to remove the tailings and contaminated materials to meet the EPA bulk soil cleanup standards for surface and subsurface soils. The site areas disturbed by remedial action excavation will be either contoured or backfilled with radiologically uncontaminated soil and contoured to restore the site. The final contours will produce a final surface grade that will create positive drainage from the site.

Not Available

1993-10-01T23:59:59.000Z

94

Radiological Dose Assessment 8 2008 Site environmental report8-  

E-Print Network [OSTI]

from ambient sources was 69 ± 13 mrem (690 ± 130 Sv) and 63 ± 11 mrem (630 ± 110 Sv) at off-site locations. Both on- and off-site dose measurements include the contribution from natural terrestrial thermoluminescent dosimeters (TLDs) at 49 on-site and 15 off-site locations showed that there was no external dose

95

Radiological Habits Survey, HM Naval Base Clyde, Faslane 2000  

E-Print Network [OSTI]

Environment Report RL 7/02 #12;2 SUMMARY 4 1. BACKGROUND 5 1.1 Regulation of radioactive waste discharges 5 1/y). Table 13. Adult consumption rates of potatoes from the survey area (kg/y). Table 14. Adult consumption

96

ORISE: Characterization surveys  

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

extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental aspect of all D&D projects, characterization surveys provide...

97

Results of the radiological survey at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts (CIO001)  

SciTech Connect (OSTI)

Radiological survey was conducted at Building 23 (Department No. 40) at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts. The survey was performed in August 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Atomic Energy Commission (AEC) during the 1940s. The survey included a gamma scan, a beta-gamma scan, and measurement of alpha activity; measurement of direct and removable alpha and beta-gamma levels; and the collection of soil, dust, debris, and smear samples for radionuclide analyses. Survey emphasis was on interior floors, walls, and overhead beams. Radionuclide analysis of soil, dust, and debris, and analysis of smear samples indicate that residual {sup 238}U attributable to former AEC-supported operations is present at this site. Elevated levels of radioactivity were particularly evident on the floors and walls in the western part of the central area of the building (grid blocks Al through A6). Concentrations of {sup 238}U in dust samples collected from overhead beams exceeded DOE guidelines in grid blocks Al through A14 and remained elevated in grid blocks A15 through A19. Dust on a movable overhead crane in grid block A23 was well above the guideline, probably because the crane had at some time been located further west. Some contamination was evident in grid blocks B1 through B5, but clutter and debris in this area prevented a thorough survey.

Foley, R.D.; Uziel, M.S.

1992-07-01T23:59:59.000Z

98

Confirmatory Survey for the Partial Site Release at the ABB Inc. CE Winsor Site, Windsor, CT  

SciTech Connect (OSTI)

The objectives of the confirmatory surveys were to confirm that remedial actions had been effective in meeting established release criteria and that documentation accurately and adequately describes the final radiological conditions of the PSR Impacted Areas.

W.C. Adams

2008-06-27T23:59:59.000Z

99

Health and Safety Research Division RESULTS OF THE RADIOLOGICAL SURVEY  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North - ConsequencesDGwen N

100

Health and Safety Research Divlsion RESULTS OF THE RADIOLOGICAL SURVEY  

Office of Legacy Management (LM)

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

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site  

SciTech Connect (OSTI)

This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs. Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. Radiological emissions at the PNNL Site result from Physical Sciences Facility (PSF) major emissions units. A team was established to determine how the PNNL Site would meet federal regulations and address guidelines developed to monitor and estimate offsite air emissions of radioactive materials. The result is a program that monitors the impact to the public from the PNNL Site.

Barnett, J. M.; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Ted M.; Rhoads, Kathleen

2010-05-25T23:59:59.000Z

102

A radiological characterization of remediated tank battery sites  

SciTech Connect (OSTI)

Tank battery sites have historically been used for the initial processing of crude oil which separates water and sediment from the produced oil. Typically, one or more producing wells is connected to a tank battery site consisting of storage and separation tanks. Historical operating practices also included a production holding pit for increaesd separation of oil, water, and sediment.

Hebert, M.B. [NORMCO, Amelia, LA (United States); Scott, L.M. [Louisiana State Univ., Baton Rouge, LA (United States); Zrake, S.J. [Ashland Exploration, Inc., Houston, TX (United States)

1995-03-01T23:59:59.000Z

103

Surface Radiation Survey at the Shepley’s Hill Remediation Site, Devens, Massachusettes  

SciTech Connect (OSTI)

The Idaho National Laboratory (INL) provided technical support for ongoing environmental remediation activities at the Shepley’s Hill remediation site, near Devens, MA. The technical support included the completion of a radiation survey of naturally occurring radioactive materials (NORM) at Shepley’s Hill, Shepley’s Hill landfill cover, and Red Cove areas. The objective of the radiation survey was to assess the ability of the INL backpack sodium iodide spectroscopy (BaSIS) system to detect elevated levels of NORM that may be associated with radon-222 emanation from near surface and subsurface fractures in the area. It is postulated that these fracture zones provide subsurface conduits for the transport of environmental contaminants. As such, location of these fracture sets will proved EPA Region 1 with the means for completing the development of an accurate site conceptual model. The results of the radiological survey show that some of the radiological anomalies correlate with currently mapped rock outcrops; however, not all of the rock outcrops in the surveyed area have been mapped. As such, it is not conclusive that all of the radiological anomalies correspond with surface rock outcrops. EPA Region 1 intends to perform a more comprehensive correlation of the radiation data collected with the BaSIS system with additional data sets such as detailed bedrock structural mapping, 2-dimensional resistivity profiling, and high-resolution topographic mapping. The results of this effort will be used in consideration of designing a potential follow-on effort for mapping of radon.

J. R. Giles; C. P. Oertel; L. G. Roybal

2009-09-01T23:59:59.000Z

104

Final report of the radiological release survey of Building 30B at the Grand Junction Office Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 30B and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

Krauland, P.A.; Corle, S.G.

1997-09-01T23:59:59.000Z

105

DRAFT - Design of Radiological Survey and Sampling to Support Title Transfer or Lease of Property on the Department of Energy Oak Ridge Reservation  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) owns, operates, and manages the buildings and land areas on the Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee. As land and buildings are declared excess or underutilized, it is the intent of DOE to either transfer the title of or lease suitable property to the Community Reuse Organization of East Tennessee (CROET) or other entities for public use. It is DOE's responsibility, in coordination with the U.S. Environmental Protection Agency (EPA), Region 4, and the Tennessee Department of Environment and Conservation (TDEC), to ensure that the land, facilities, and personal property that are to have the title transferred or are to be leased are suitable for public use. Release of personal property must also meet site requirements and be approved by the DOE contractor responsible for site radiological control. The terms title transfer and lease in this document have unique meanings. Title transfer will result in release of ownership without any restriction or further control by DOE. Under lease conditions, the government retains ownership of the property along with the responsibility to oversee property utilization. This includes involvement in the lessee's health, safety, and radiological control plans and conduct of site inspections. It may also entail lease restrictions, such as limiting access to certain areas or prohibiting digging, drilling, or disturbing material under surface coatings. Survey and sampling requirements are generally more rigorous for title transfer than for lease. Because of the accelerated clean up process, there is an increasing emphasis on title transfers of facilities and land. The purpose of this document is to describe the radiological survey and sampling protocols that are being used for assessing the radiological conditions and characteristics of building and land areas on the Oak Ridge Reservation that contain space potentially available for title transfer or lease. After necessary surveys and sampling and laboratory analyses are completed, the data are analyzed and included in an Environmental Baseline Summary (EBS) report for title transfer or in a Baseline Environmental Analysis Report (BEAR) for lease. The data from the BEAR is then used in a Screening-Level Human Health Risk Assessment (SHHRA) or a risk calculation (RC) to assess the potential risks to future owners/occupants. If title is to be transferred, release criteria in the form of specific activity concentrations called Derived Concentration Guideline Levels (DCGLs) will be developed for the each property. The DCGLs are based on the risk model and are used with the data in the EBS to determine, with statistical confidence, that the release criteria for the property have been met. The goal of the survey and sampling efforts is to (1) document the baseline conditions of the property (real or personal) prior to title transfer or lease, (2) obtain enough information that an evaluation of radiological risks can be made, and (3) collect sufftcient data so that areas that contain minimal residual levels of radioactivity can be identified and, following radiological control procedures, be released from radiological control. (It should be noted that release from radiological control does not necessarily mean free release because DOE may maintain institutional control of the site after it is released from radiological control). To meet the goals of this document, a Data Quality Objective (DQO) process will be used to enhance data collection efficiency and assist with decision-making. The steps of the DQO process involve stating the problem, identifying the decision, identifying inputs to the decision, developing study boundaries, developing the decision rule, and optimizing the design. This document describes the DQOs chosen for surveys and sampling efforts performed for the purposes listed above. The previous version to this document focused on the requirements for radiological survey and sampling protocols that are be used for leasing. Because the primary focus at this time is on title transfer, th

Cusick L.T.

2002-09-25T23:59:59.000Z

106

Uranium Mill Tailings Remedial Action Program. Partial radiological survey of Shiprock vicinity property SH14 Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

As part of a detailed radiological assessment of the vicinity properties at Shiprock, a comprehensive survey of the vicinity property designated as SH14 was initiated during October and November 1982. At the time of the survey, vicinity property SH14 consisted of about 20 acres of open lands to the northeast of, and directly across the San Juan River from, the upper tailings pile at Shiprock. The lands consisted of a sandy soil, sparsley covered with trees and other vegetation. The partial assessment activities included determination of surface radiation levels on about a 2-meter grid spacing through direct instrument surveys and analysis of a soil sample collected from the area. The partial radiological assessment indicated elevated levels of radioactivity at several general areas within the open lands. Radiochemical analyses of the soil sample collected from one of these areas indicated a radium concentration of 18 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in the EPA Standard (40 CFR 192). Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Further measurements required to completely determine and accurately report the radiological status of this vicinity property, including additional direct instrument surveys, collection and analyses of soil samples, and the establishment of a 200-ft grid system, were planned for the final phase of this assessment. However, that phase of the program was cancelled before these measurements were accomplished. The total extent of the radiological contamination of vicinity property SH14 is presently unknown. Nonetheless, since the surface soil contamination levels exceeded the limits specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-06-01T23:59:59.000Z

107

Results of the radiological survey at the former ALCOA New Kensington Works, Pine and Ninth Streets, New Kensington, Pennsylvania (ANK002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the former ALCOA New Kensington Works, Pine and Ninth Streets, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally, as a result of work done for the Manhattan Engineer District in 1944. The survey included a gamma scan of three bays inside Building 18; measurement of direct alpha and beta-gamma levels in the same area; and collection of a dust sample for radionuclide analysis from the center of each bay. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines for uranium. The radionuclide distributions were not significantly different from typical background levels in the Pittsburgh, Pennsylvania area.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

108

Results of the radiological survey at the former McKinney Tool and Manufacturing Company, 1688 Arabella Road, Cleveland, Ohio (MTC001 and MTC002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the site of the former McKinney Tool and Manufacturing Company, 1688, Arabella Road, Cleveland, Ohio. The survey was performed on November 17 and 18, 1990. The purpose of the survey was to determine whether the property ws contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Manhattan Engineer District in 1944. The survey included a gamma scan, a beta-gamma scan, and measurement of alpha level; measurements of direct and removable alpha and beta-gamma levels; and the collection of soil and sediment, dust, and air samples for radionuclide analyses. The survey and sampling covered accessible areas of buildings currently occupied by Parker Rust-Proof and Meistermatic, Inc., and exterior areas immediately adjacent to these buildings.

Foley, R.D.; Uziel, M.S.

1991-11-01T23:59:59.000Z

109

Hanford Site Annual Report Radiological Dose Calculation Upgrade Evaluation  

SciTech Connect (OSTI)

Operations at the Hanford Site, Richland, Washington, result in the release of radioactive materials to offsite residents. Site authorities are required to estimate the dose to the maximally exposed offsite resident. Due to the very low levels of exposure at the residence, computer models, rather than environmental samples, are used to estimate exposure, intake, and dose. A DOS-based model has been used in the past (GENII version 1.485). GENII v1.485 has been updated to a Windows®-based software (GENII version 2.08). Use of the updated software will facilitate future dose evaluations, but must be demonstrated to provide results comparable to those of GENII v1.485. This report describes the GENII v1.485 and GENII v2.08 dose exposure, intake, and dose estimates for the maximally exposed offsite resident reported for calendar year 2008. The GENII v2.08 results reflect updates to implemented algorithms. No two environmental models produce the same results, as was again demonstrated in this report. The aggregated dose results from 2008 Hanford Site airborne and surface water exposure scenarios provide comparable dose results. Therefore, the GENII v2.08 software is recommended for future offsite resident dose evaluations.

Snyder, Sandra F.

2010-02-28T23:59:59.000Z

110

Radiological characterization survey results for Gaskill Hall, Miami University, Oxford, Ohio (OXO015)  

SciTech Connect (OSTI)

Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Although the amount of uranium found on the property posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. Because it was suspected that uranium may have been used in the past in the immediate vicinity of Alba Craft in a Miami University building a team from ORNL, performed a radiological characterization survey of that structure in January 1994. The survey was conducted at the request of DOE as a precautionary measure to ensure that no radioactive residuals were present at levels exceeding guidelines. The survey included the determination of directly measured radiation levels and the collection of smear samples to detect possible removable alpha and beta-gamma activity levels, and comparison of these data to the guidelines. Results of the survey showed that all measurements were below the applicable guideline limits set by DOE.

Kleinhans, K.R.; Murray, M.E.; Carrier, R.F.

1996-04-01T23:59:59.000Z

111

Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities  

SciTech Connect (OSTI)

This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs.

Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

1986-01-01T23:59:59.000Z

112

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH03, Shiprock, NM, July-November 1982  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH03 was conducted on an intermittent basis from July 26 to November 11, 1982. At the time of the survey, three structures were located on the property - a residential trailer, the main structure, and an old gas pump housing. The lands surrounding the structures were either sparsely covered with arid vegetation or paved. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air, soil, and other material samples. No evidence of radioactive contamination was found inside the trailer. However, the results of the radiological assessment did indicate the occurrence of elevated levels of gamma, surface alpha, and radon daughter radioactivity within the main structure. The short-term radon daughter measurements exceeded the limit of 0.02 Working Level for average annual concentration including background. The assessment also indicated elevated levels of radioactivity in the outdoor environs, encompassing about 32,000 ft/sup 2/ of the grounds adjacent to and surrounding the main structure on the east, south, and west sides. The contamination appeared to be due to the presence of unprocessed uranium ore. Analysis of surface soil samples collected from the environs indicated radium concentrations in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination levels exceeded the limits specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-04-01T23:59:59.000Z

113

Results of the radiological survey at the New Betatron Building, Granite City Steel facility, Granite City, Illinois (GSG002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the New Betatron Building, located in the South Plant facility of Granite City Steel Division, 1417 State Street, Granite City, Illinois. The survey was performed in August 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Atomic Energy Commission (AEC) from 1958 to 1966. The survey included a surface gamma scan of the ground surface outdoors near the building, the floor and walls in all accessible areas inside the building, and the roof; measurement of beta-gamma dose rates, alpha radiation levels, and removable alpha and beta-gamma activity levels at selected locations inside the building and on the roof; and radionuclide analysis of outdoor soil samples and indoor samples of shield-wall fill material land debris. Analysis of soil, shield-wall fill material, debris, and smear samples showed no residual {sup 238}U attributable to former AEC-supported operations at this site. None of the indoor or outdoor gamma exposure rate measurements were elevated above DOE guidelines. The slight elevations in gamma levels found outdoors and on the roof over the shield wall are typical of naturally occurring radioactive substances present in coal ash and cinders in the fill material surrounding the building and in concrete and cinders used in constuction of the shield wall. The slightly elevated gamma levels measured at soil sampling locations can be attributed to the presence of naturally occurring radionuclides. In all samples, {sup 226}Ra and {sup 238}U appeared to be in equilibrium, indicating that these radionuclides were of natural origin and not derived from former AEC activities at this site.

Murray, M.E.; Uziel, M.S.

1992-01-01T23:59:59.000Z

114

An aerial radiological survey of the Waste Isolation Pilot Plant and surrounding area, Carlsbad, New Mexico: Date of survey, April 1988  

SciTech Connect (OSTI)

An aerial radiological survey was conducted during the period April 8 to April 19, 1988 over a 404-square-kilometer (156-square-mile) area covering the Waste Isolation Pilot Plant (WIPP) located near Carlsbad, New Mexico, the surrounding area. The survey was conducted at a nominal altitude of 91 meters (300 feet) with a line spacing of 152 meters (500 feet). A contour map of the terrestrial exposure rates plus the cosmic exposure rate extrapolated to 1 meter above ground level was prepared and overlaid on an aerial photograph of the area. The average terrestrial exposure rates ranged from approximately 6.0 to 9.0 microroentgens per hour ({mu}R/h). Two areas of increased exposure rate were evident. Both areas indicated higher than normal concentrations of naturally occurring radionuclides. A machine-aided search of the data for man-made sources of radiation indicated the presence of Cs-137 at the Gnome Site, which was expected from previous survey work done in the area. No other sources of man-made radiation were found.

Not Available

1989-06-01T23:59:59.000Z

115

Anesthesia Practice and Clinical Trends in Interventional Radiology: A European Survey  

SciTech Connect (OSTI)

Purpose: To determine current European practice in interventional radiology regarding nursing care, anesthesia, and clinical care trends.Methods: A survey was sent to 977 European interventional radiologists to assess the use of sedoanalgesia, nursing care, monitoring equipment, pre- and postprocedural care, and clinical trends in interventional radiology. Patterns of sedoanalgesia were recorded for both vascular and visceral interventional procedures. Responders rated their preferred level of sedoanalgesia for each procedure as follows: (a) awake/alert, (b) drowsy/arousable, (c) asleep/arousable, (d) deep sedation, and (e) general anesthesia. Sedoanalgesic drugs and patient care trends were also recorded. A comparison was performed with data derived from a similar survey of interventional practice in the United States.Results: Two hundred and forty-three of 977 radiologists responded (25%). The total number of procedures analyzed was 210,194. The majority (56%) of diagnostic and therapeutic vascular procedures were performed at the awake/alert level of sedation, 32% were performed at the drowsy/arousable level, and 12% at deeper levels of sedation. The majority of visceral interventional procedures were performed at the drowsy/arousable level of sedation (41%), 29% were performed at deeper levels of sedation, and 30% at the awake/alert level. In general, more sedoanalgesia is used in the United States. Eighty-three percent of respondents reported the use of a full-time radiology nurse, 67% used routine blood pressure/pulse oximetry monitoring, and 46% reported the presence of a dedicated recovery area. Forty-nine percent reported daily patient rounds, 30% had inpatient hospital beds, and 51% had day case beds.Conclusion: This survey shows clear differences in the use of sedation for vascular and visceral interventional procedures. Many, often complex, procedures are performed at the awake/alert level of sedation in Europe, whereas deeper levels of sedation are used in the United States. Trends toward making interventional radiology a clinical specialty are evident, with 51% of respondents having day case beds, and 30% having inpatient beds.

Haslam, Philip J.; Yap, Bernard [Department of Radiology, Beaumont Hospital and Royal College of Surgeons in Ireland Medical School, Dublin 9 (Ireland); Mueller, Peter R. [Department of Radiology, WHT220, Massachusetts General Hospital, Harvard Medical School, 32 Fruit Street, Boston, MA 02114 (United States); Lee, Michael J. [Department of Radiology, Beaumont Hospital and Royal College of Surgeons in Ireland Medical School, Dublin 9 (Ireland)

2000-07-15T23:59:59.000Z

116

Results of the radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York (TNY001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York. The survey was performed in September 1991. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been deposited in the landfill. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey suggest that material originating at the Linde plant may have been deposited in the landfill. Soil samples S54 and B12 contained technologically enhanced levels of [sup 238]U not unlike the product formerly produced by the Linde plant. In contrast, samples B4A, B5A and B7B, containing elevated concentrations of [sup 226]Ra and [sup 230]Th with much lower concentrations of [sup 238]U, were similar to the residue or byproduct of the refinery operation conducted at the Linde plant. In 24 instances, soil samples from the Town of Tonawanda Landfill exceeded DOE guideline values for [sup 238]U, [sup 226]Ra, and/or [sup 230]Th in surface or subsurface soil. Nine of these samples contained radionuclide concentrations more than 30 times the guideline value.

Rodriguez, R.E.; Murray, M.E.; Uziel, M.S.

1992-10-01T23:59:59.000Z

117

Results of the radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York (TNY001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York. The survey was performed in September 1991. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been deposited in the landfill. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey suggest that material originating at the Linde plant may have been deposited in the landfill. Soil samples S54 and B12 contained technologically enhanced levels of {sup 238}U not unlike the product formerly produced by the Linde plant. In contrast, samples B4A, B5A and B7B, containing elevated concentrations of {sup 226}Ra and {sup 230}Th with much lower concentrations of {sup 238}U, were similar to the residue or byproduct of the refinery operation conducted at the Linde plant. In 24 instances, soil samples from the Town of Tonawanda Landfill exceeded DOE guideline values for {sup 238}U, {sup 226}Ra, and/or {sup 230}Th in surface or subsurface soil. Nine of these samples contained radionuclide concentrations more than 30 times the guideline value.

Rodriguez, R.E.; Murray, M.E.; Uziel, M.S.

1992-10-01T23:59:59.000Z

118

DISS/ET modernization site/user survey details  

SciTech Connect (OSTI)

This purpose of this document is to provide: a record of site visits, a summary of the comments received from the user survey forms and site interviews, a description of the manual process used for personnel security clearances. The participants in the user survey and site surveys were users at: DOE contractor clearance offices (LLNL), DOE operations offices (ORO,Y-12, Albuquerque ,Sandia, San Francisco) Office of Personnel Management (OPM) - Federal Investigations Processing Center (FIPC).

Pierson, C.

1993-12-21T23:59:59.000Z

119

Environmental Survey preliminary report, Hanford Site, Richland, Washington  

SciTech Connect (OSTI)

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Hanford Site, conducted August 18 through September 5, 1986. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Hanford Site. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Hanford Site, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by a DOE National Laboratory or a support contractor. When completed, the results will be incorporated into the Environmental Survey Interim Report for the Hanford Site. The Interim Report will reflect the final determinations of the Hanford Site Survey. 44 refs., 88 figs., 74 tabs.

Not Available

1987-08-01T23:59:59.000Z

120

Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 – Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or “clean,” building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, “Final Status Survey Plan for Corrective Action Unit 117 – Pluto Disassembly Facility, Building 2201”) was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room into one of three categories: Class 1, Class 2 or Class 3 (a fourth category is a “Non-Impacted Class” which in the case of Building 2201 only pertained to exterior surfaces of the building.) The majority of the rooms were determined to fall in the less restrictive Class 3 category, however, Rooms 102, 104, 106, and 107 were identified as containing Class 1 and 2 areas. Building 2201 was divided into “survey units” and surveyed following the requirements of the Final Status Survey Plan for each particular class. As each survey unit was completed and documented, the survey results were evaluated. Each sample (static measurement) with units of counts per minute (cpm) was corrected for the appropriate background and converted to a value with units of dpm/100 cm2. With a surface contamination value in the appropriate units, it was compared to the surface contamination limits, or in this case the derived concentration guideline level (DCGLw). The appropriate statistical test (sign test) was then performed. If the survey unit was statistically determined to be below the DCGLw, then the survey unit passed and the null hypothesis (that the survey unit is above limits) was rejected. If the survey unit was equal to or below the critical value in the sign test, the null hypothesis was not rejected. This process was performed for all survey units within Building 2201. A total of thirty-three “Class 1,” four “Class 2,” and one “Class 3” survey units were developed, surveyed, and evaluated. All survey units successfully passed the statistical test. Building 2201 meets the release criteria commensurate with the Waste Acceptance Criteria (for radiological purposes) of the U10C landfill permit residing within NNSS boundaries. Based on the thorough statistical sampling and scanning of the building’s interior, Building 2201 may be considered radiologically “clean,” or free of contamination.

Jeremy Gwin and Douglas Frenette

2010-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

2 OVERVIEW OF THE RADIATION SURVEY AND SITE INVESTIGATION PROCESS  

E-Print Network [OSTI]

2 OVERVIEW OF THE RADIATION SURVEY AND SITE INVESTIGATION PROCESS 2.1 Introduction This chapter provides a brief overview of the Radiation Survey and Site Investigation (RSSI) Process, several important aspects of this Process, and its underlying principles. The concepts introduced here are discussed

122

A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP  

SciTech Connect (OSTI)

The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

Milchikov, A.; Hund, G.; Davidko, M.

1999-10-20T23:59:59.000Z

123

Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. The original DQO (PNNL-19427) considered radiological emissions at the PNNL Site from Physical Sciences Facility (PSF) major emissions units. This first revision considers PNNL Site changes subsequent to the implementation of the original DQO. A team was established to determine how the PNNL Site changes would continue to meet federal regulations and address guidelines developed to monitor air emissions and estimate offsite impacts of radioactive material operations. The result is an updated program to monitor the impact to the public from the PNNL Site. The team used the emission unit operation parameters and local meteorological data as well as information from the PSF Potential-to-Emit documentation and Notices of Construction submitted to the Washington State Department of Health (WDOH). The locations where environmental monitoring stations would most successfully characterize the maximum offsite impacts of PNNL Site emissions from the three PSF buildings with major emission units were determined from these data. Three monitoring station locations were determined during the original revision of this document. This first revision considers expanded Department of Energy operations south of the PNNL Site and relocation of the two offsite, northern monitoring stations to sites near the PNNL Site fenceline. Inclusion of the southern facilities resulted in the proposal for a fourth monitoring station in the southern region. The southern expansion added two minor emission unit facilities and one diffuse emission unit facility. Relocation of the two northern stations was possible due to the use of solar power, rather than the previous limitation of the need for access to AC power, at these more remote locations. Addendum A contains all the changes brought about by the revision 1 considerations. This DQO report also updates the discussion of the Environmental Monitoring Plan for the PNNL Site air samples and how existing Hanford Site monitoring program results could be used. This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs.

Barnett, J. M.; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Theodore M.; Antonio, Ernest J.

2012-11-12T23:59:59.000Z

124

An aerial radiological survey of Pocatello and Soda Springs, Idaho and surrounding area, June--July 1986  

SciTech Connect (OSTI)

Three aerial radiological surveys were conducted during the period 16 June through 15 July 1986 over the towns of Pocatello, Soda Springs, and Fort Hall, Idaho and the surrounding areas. The surveys were performed for the United States Environmental Protection Agency (EPA) by the United States Department of Energy's (DOE) Remote Sensing Laboratory (RSL), utilizing the Aerial Measuring System (AMS). This work was completed in cooperation with a study by the EPA to conduct a dose assessment of human radiation exposure for industrial sources in Pocatello and Soda Springs, Idaho. The aerial surveys were performed to document the natural terrestrial radiological environment of the three localities and to map the spatial extent and degree of contamination due to phosphate milling operations. The results of these surveys will be used for planning ground-based measurements in addition to being incorporated into the dose assessment document. 4 refs., 14 figs., 6 tabs.

Berry, H.A.

1987-02-01T23:59:59.000Z

125

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH01, Shiprock, NM, August-November 1982  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH01 was conducted on an intermittent basis from August 23 to November 11, 1982. At the time of the survey, three structures were located on the property - two residential structures and a residential trailer. In addition to the three residences, the frame from a former truck scale was still on the property. The lands surrounding the structures and former truck scale were sparsely covered with vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels through direct instrument surveys and analysis of air and soil samples. No evidence of radioactive contamination was found inside the structures, although elevated levels of radioactivity due to proximity to or shine from contaminated soils were indicated within all. The short-term radon daughter measurements did not exceed the limit of 0.02 Working Level for average annual concentration including background, as specified in the EPA Standard 40 CFR 192. The assessment indicated elevated levels of radioactivity in the outdoor environs, encompassing about 32,000 ft/sup 2/ (2900 m/sup 2/) of land surrounding, and north of, the former truck scale. Analysis of a surface soil sample collected from the environs indicated a radium concentration considerably in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination level exceeded the limit specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-04-01T23:59:59.000Z

126

The Role of Gamma-ray Imaging in Performing Radiological Characterisation at the Magnox Storage Ponds at the Bradwell Decommissioning Site - 13628  

SciTech Connect (OSTI)

A gamma-ray imaging device has been used to perform radiological characterisation work at the spent fuel ponds complex at the site of the Bradwell Magnox Power Station, which is currently undergoing accelerated decommissioning. The objective of using a gamma-ray imaging system was to independently verify previous radiological survey work and to evaluate the adequacy of the random distribution of the destructive core sampling which had been performed. In performing this work the gamma-ray imager clearly identified the exact locations of the sources of radiation that gave rise to the elevated gamma dose rates measured by conventional health physics surveys of the area. In addition, the gamma-ray imager was able to characterise each hotspot as being either dominated by Cs-137 or by Co-60. The gamma imaging survey was undertaken with a RadScan gamma imaging system deployed on the walkways which run along the lengths of the ponds; this enabled the whole imaging survey to be performed with minimal dose uptake, demonstrating the ALARP principle within decommissioning. (authors)

Hughes, Karl; Shaw, Tracey [Babcock International, B14.1, Sellafield, Cumbria, CA20 1PG (United Kingdom)] [Babcock International, B14.1, Sellafield, Cumbria, CA20 1PG (United Kingdom)

2013-07-01T23:59:59.000Z

127

Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River Site  

SciTech Connect (OSTI)

As a result of operations at the Savannah River Site (SRS), over 50 radionuclides have been released to the atmosphere and to onsite streams and seepage basins. Now, many of these radionuclides are available to aquatic and/or terrestrial organisms for uptake and cycling through the food chain. Knowledge about the uptake and cycling of these radionuclides is now crucial in evaluating waste management and clean-up alternatives for the site. Numerous studies have been conducted at the SRS over the past forty years to study the uptake and distribution of radionuclides in the Savannah River Site environment. In many instances, bioconcentration factors have been calculated to quantify the uptake of a radionuclide by an organism from the surrounding medium (i.e., soil or water). In the past, it has been common practice to use bioconcentration factors from the literature because site-specific data were not readily available. However, because of the variability of bioconcentration factors due to experimental or environmental conditions, site-specific data should be used when available. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at the Savannah River Site (SRS). An extensive literature search yielded site-specific bioconcentration factors for cesium, strontium, cobalt, plutonium, americium, curium, and tritium. These eight radionuclides have been the primary radionuclides studied at SRS because of their long half lives or because they are major contributors to radiological dose from exposure. For most radionuclides, it was determined that the site-specific bioconcentration factors were higher than those reported in literature. This report also summarizes some conditions that affect radionuclide bioavailability to and bioconcentration by aquatic and terrestrial organisms.

Cummins, C.L.

1994-09-01T23:59:59.000Z

128

Environmental Survey preliminary report, Nevada Test Site, Mercury, Nevada  

SciTech Connect (OSTI)

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Nevada Test Site (NTS), conducted June 22 through July 10, 1987. The Survey is being conducted by a multidisciplinary team of environmental specialists led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team members are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the NTS. The Survey covers all environment media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations and activities performed at the NTS, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain environmental problems identified during its on-site activities. The Sampling and Analysis Plan is being executed by the Battelle Columbus Division under contract with DOE. When completed, the results will be incorporated into the NTS Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the NTS Survey. 165 refs., 42 figs., 52 tabs.

Not Available

1988-04-01T23:59:59.000Z

129

Robotic Exploration: Video Survey of the USS Macon Crash Site  

E-Print Network [OSTI]

Robotic Exploration: Video Survey of the USS Macon Crash Site Stanford Aerospace Robotics Lab Prof of MBARI Photo courtesy of Naval Archives #12;2006 Goal: Video Survey Image courtesy of MBARI #12;Issue;User Interface #12;Control System Implementation PC ROV Control ROV + + Pilot joystick commands Video

Prinz, Friedrich B.

130

2010 Ecological Survey of the Pacific Northwest National Laboratory Site  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Pacific Northwest Site Office (PNSO) oversees and manages the DOE contract for the Pacific Northwest National Laboratory (PNNL), a DOE Office of Science multi-program laboratory located in Richland, Washington. PNSO is responsible for ensuring that all activities conducted on the PNNL Site comply with applicable laws, policies, and DOE orders. The DOE Pacific Northwest Site Office Cultural and Biological Resources Management Plan (DOE/PNSO 2008) addresses the requirement for annual surveys and monitoring for species of concern and to identify and map invasive species. In addition to the requirement for an annual survey, proposed project activities must be reviewed to assess any potential environmental consequences of conducting the project. The assessment process requires a thorough understanding of the resources present, the potential impacts of a proposed action to those resources, and the ultimate consequences of those actions. The PNNL Site is situated on the southeastern corner of the DOE Hanford Site, located at the north end of the city of Richland in south-central Washington. The site is bordered on the east by the Columbia River, on the west by Stevens Drive, and on the north by the Hanford Site 300 Area (Figure 1). The environmental setting of the PNNL Site is described in Larson and Downs (2009). There are currently two facilities on the PNNL Site: the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL), and the recently completed Physical Sciences Facility (PSF). This report describes the results of the annual survey of the biological resources found on the undeveloped portions of the PNNL Site in 2010. A brief description of the methods PNNL ecologists used to conduct the surveys and the results of the surveys are presented. Actions taken to fully delineate noxious weed populations discovered in 2009 and efforts in 2010 to control those weeds also are described. Appendix A provides a list of plant and animal species identified on the PNNL Site.

Chamness, Michele A.; Perry, Christopher; Downs, Janelle L.; Powell, Sylvia D.

2011-02-16T23:59:59.000Z

131

Results of the radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania (ANK001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally [sup 238]U, as a result of work done for the Manhattan Engineer District in 1944. The survey included measurement of direct alpha and beta-gamma levels in the northeast comer of the basement of Building 29, and the collection of a debris sample from a floor drain for radionuclide analysis. The survey area was used for experimental canning of uranium slugs prior to production activities at the former New Kensington Works nearby.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

132

The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis  

SciTech Connect (OSTI)

From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of {sup 90}Sr, {sup 137}Cs, {sup 241}Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA`s radiochemistry department were accepted.

Kehl, S.R.; Mount, M.E.; Robison, W.L.

1995-09-01T23:59:59.000Z

133

Results of the independent radiological verification survey of the remedial action performed at 525 S. Main Street, Oxford, Ohio, (OXO002)  

SciTech Connect (OSTI)

Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Above-guideline radiation levels were also found both indoors and outdoors at 525 S. Main Street, a private residential property in the immediate vicinity of the Alba Craft site. This document reports the findings at this private residence. Although the amount of uranium found on the properties posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. A team from ORNL conducted a radiological verification survey of the property at 525 S. Main Street, between November 1993 and December 1994. The survey was conducted at the request of DOE and included directly measured radiation levels, the collection and analysis of soil samples to determine concentrations of uranium and certain other radionuclides, and comparison of these data to the guidelines.

Kleinhans, K.R.; Rice, D.E.; Murray, M.E.; Carrier, R.F.

1996-04-01T23:59:59.000Z

134

EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York  

Broader source: Energy.gov [DOE]

The Naval Nuclear Propulsion Program (NNPP) intent to prepare an Environmental Assessment for a radiological work and storage building at the Knolls Atomic Power Laboratory (Kesselring Site in West Milton, New York. A new facility is needed to streamline radioactive material handling and storage operations, permit demolition of aging facilities, and accommodate efficient maintenance of existing nuclear reactors.

135

2011 Annual Ecological Survey: Pacific Northwest National Laboratory Site  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Pacific Northwest Site Office (PNSO) oversees and manages the DOE contract for the Pacific Northwest National Laboratory (PNNL), a DOE Office of Science multi-program laboratory located in Richland, Washington. PNSO is responsible for ensuring that all activities conducted on the PNNL site comply with applicable laws, policies, and DOE Orders. The DOE Pacific Northwest Site Office Cultural and Biological Resources Management Plan (DOE/PNSO 2008) addresses the requirement for annual surveys and monitoring for species of concern and to identify and map invasive species. In addition to the requirement for an annual survey, proposed project activities must be reviewed to assess any potential environmental consequences of conducting the project. The assessment process requires a thorough understanding of the resources present, the potential impacts of a proposed action to those resources, and the ultimate consequences of those actions. The PNNL site is situated on the southeastern corner of the DOE Hanford Site, located at the north end of the city of Richland in south-central Washington. The site is bordered on the east by the Columbia River, on the west by Stevens Drive, and on the north by the Hanford Site 300 Area (Figure 1). The environmental setting of the PNNL site is described in Larson and Downs (2009). There are currently two facilities on the PNNL site: the William R. Wiley Environmental Molecular Sciences Laboratory and the Physical Sciences Facility. This report describes the annual survey of biological resources found on the undeveloped upland portions of the PNNL site. The annual survey is comprised of a series of individual field surveys conducted on various days in late May and throughout June 2011. A brief description of the methods PNNL ecologists used to conduct the baseline surveys and a summary of the results of the surveys are presented. Appendix A provides a list of plant and animal species identified in the upland areas of the PNNL site in 2011. Efforts in 2011 to control noxious weed populations (comprising plant species designated as Class B noxious weeds by the Washington State Noxious Weed Control Board) discovered in 2009 and initially treated with herbicides in 2010 are described in Appendix B.

Becker, James M.; Chamness, Michele A.

2012-02-27T23:59:59.000Z

136

Radiological Characterization and Final Facility Status Report Tritium Research Laboratory  

SciTech Connect (OSTI)

This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC&FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate.

Garcia, T.B.; Gorman, T.P.

1996-08-01T23:59:59.000Z

137

Aerial radiological and photographic survey of eleven atolls and two islands within the Northern Marshall Islands. Dates of surveys, July-November 1978  

SciTech Connect (OSTI)

An aerial radiological survey was conducted over eleven atolls and two islands within the northern Marshall Islands between September and November 1978. This survey was part of a comprehensive radiological survey, which included extensive terrestrial and marine sampling, to determine possible residual contamination which might remain as a result of the United States nuclear testing program conducted at Bikini Enewetak Atolls between 1946 and 1958. A similar survey was conducted at Enewetak Atoll in 1972. The present survey covered those atolls known to have received direct fallout from the Bravo event, conducted in March 1954 at Bikini Atoll. These included Bikini, Rongelap, Rongerik, Ailinginae, Bikar, Taka, and Utirik Atolls. In addition, several atolls and islands which might have been at the fringes of the Bravo fallout were also surveyed, including Likiep and Ailuk Atolls, Jemo and Mejit Islands, and Wotho Atoll. Ujelang Atoll, which lies approximately 200 km southwest of Enewetak, was also surveyed. Island-averaged terrestrial exposure rates in the range of 30 to 50 ..mu..R/h were observed over parts of Bikini Atoll, including Bikini Island, and over the northern part of Rongelap Atoll. Levels over southern Rongelap and over Rongerik Atoll ranged from 4 to 7 ..mu..R/h. Levels were somewhat lower at Ailinginae Atoll (approximately 2 ..mu..R/h) and at Utirik Atoll (approximately 0.7 ..mu..R/h). The variations observed were consistent with what might be expected from the fallout pattern of the Bravo event. Levels at Ailuk, Likiep, Wotho and Ujelang Atolls and at Mejit and Jemo Islands were consistent with /sup 137/Cs activity, due to worldwide fallout, observed within the United States and at other locations in the central Pacific. These four atolls and the two islands, therefore, do not appear to have recieved any significant direct contamination from the Bravo event or the other tests conducted at Bikini and Enewetak Atolls.

Not Available

1981-06-01T23:59:59.000Z

138

Soil Survey and Ecological Sites: Integrated Map Unit Design and  

E-Print Network [OSTI]

Intensity Methods Map units Order 1 Grid mapping 2 (detailed) Confirm boundary and components 3 (broad) Confirm dominant components 4 Reconnaissance #12;Intensity Methods Map units Order 1 Grid mapping SingleSoil Survey and Ecological Sites: Integrated Map Unit Design and Interpretation Arlene J. Tugel

139

Nearest Neighbor Averaging and its Effect on the Critical Level and Minimum Detectable Concentration for Scanning Radiological Survey Instruments that Perform Facility Release Surveys.  

SciTech Connect (OSTI)

Through the SNL New Mexico Small Business Assistance (NMSBA) program, several Sandia engineers worked with the Environmental Restoration Group (ERG) Inc. to verify and validate a novel algorithm used to determine the scanning Critical Level (L c ) and Minimum Detectable Concentration (MDC) (or Minimum Detectable Areal Activity) for the 102F scanning system. Through the use of Monte Carlo statistical simulations the algorithm mathematically demonstrates accuracy in determining the L c and MDC when a nearest-neighbor averaging (NNA) technique was used. To empirically validate this approach, SNL prepared several spiked sources and ran a test with the ERG 102F instrument on a bare concrete floor known to have no radiological contamination other than background naturally occurring radioactive material (NORM). The tests conclude that the NNA technique increases the sensitivity (decreases the L c and MDC) for high-density data maps that are obtained by scanning radiological survey instruments.

Fournier, Sean Donovan; Beall, Patrick S [Sandia National Laboratories, Livermore, CA; Miller, Mark L.

2014-08-01T23:59:59.000Z

140

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH16, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment indicated elevated levels of radioactivity at several areas in the outside environs. Three localized areas, or discrete hot spots, were found within the backyard. A general area of elevated radioactivity was found at the back alleyway, encompassing about 1200 ft/sup 2/. Radiochemical analyses of the soil sample collected from the backyard indicated a radium concentration of 14 +- 1 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of surface soil samples collected at the alleyway from nearly vicinity property sites also indicated radium concentrations in excess of the limit. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Waste Isolation Pilot Plant (WIPP) site gravity survey and interpretation  

SciTech Connect (OSTI)

A portion of the WIPP site has been extensively surveyed with high-precision gravity. The main survey (in T22S, R31E) covered a rectangular area 2 by 4-1/3 mi encompassing all of WIPP site Zone II and part of the disturbed zone to the north of the site. Stations were at 293-ft intervals along 13 north-south lines 880 ft apart. The data are considered accurate to within a few hundredths of a milligal. Long-wavelength gravity anomalies correlate well with seismic time structures on horizons below the Castile Formation. Both the gravity anomalies and the seismic time structures are interpreted as resulting from related density and velocity variations within the Ochoan Series. Shorter wavelength negative gravity anomalies are interpreted as resulting from bulk density alteration in the vicinity of karst conduits. The WIPP gravity survey was unable to resolve low-amplitude, long-wavelength anomalies that should result from the geologic structures within the disturbed zone. It did indicate the degree and character of karst development within the surveyed area.

Barrows, L.J.; Fett, J.D.

1983-04-01T23:59:59.000Z

142

Uranium Mill Tailings Remedial Action Program. Partial radiological survey of Shiprock vicinity property SH13 Shiprock, New Mexico, November 1982  

SciTech Connect (OSTI)

As part of a detailed radiological assessment of the vicinity properties at Shiprock, a comprehensive survey of the vicinity property designated as SH13 was initiated on November 19, 1982. At that time, a single residential structure existed in the northwest corner of the property. The lands surrounding the structure were extensively cluttered with junk. The initial assessment activities were limited to measurements within the residential structure of the ambient external penetrating radiation level at a 1-meter height and analyses of indoor air samples for airborne radioactivity. The external penetrating radiation exposure rate (12.3 ..mu..R/h) was less than the 20 ..mu..R/h above background limit specified in the EPA Standard (40 CFR 192.12(b)(2)). As determined by the air samples, the short-term radon daughter concentration within the structure (0.36 mWL) did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard. Further measurements required to completely determine the radiological status of this vicinity property, such as measurements of surface radiation both indoors and outdoors and collection and analyses of soil samples, were planned for the final phase of this assessment. However, that phase of the program was terminated before these measurements were accomplished. Thus, the extent of outdoor radiological contamination is presently unknown, and the evaluation of indoor contamination (if any) is incomplete.

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

1984-05-01T23:59:59.000Z

143

Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site  

SciTech Connect (OSTI)

This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters -- both beta and alpha emitters -- residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methods included the use of the Toulmin model of argument, represented using Toulmin diagrams, to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using "background makers"; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra.

Millsap, William J. [Mission Support Alliance, Richland, WA (United States); Brush, Daniel J. [Mission Support Alliance, Richland, WA (United States)

2013-11-13T23:59:59.000Z

144

In-Situ Radiological Surveys to Address Nuclear Criticality Safety Requirements During Remediation Activities at the Shallow Land Disposal Area, Armstrong County, Pennsylvania - 12268  

SciTech Connect (OSTI)

Cabrera Services Inc. (CABRERA) is the remedial contractor for the Shallow Land Disposal Area (SLDA) Site in Armstrong County Pennsylvania, a United States (US) Army Corps of Engineers - Buffalo District (USACE) contract. The remediation is being completed under the USACE's Formerly Utilized Sites Remedial Action Program (FUSRAP) which was established to identify, investigate, and clean up or control sites previously used by the Atomic Energy Commission (AEC) and its predecessor, the Manhattan Engineer District (MED). As part of the management of the FUSRAP, the USACE is overseeing investigation and remediation of radiological contamination at the SLDA Site in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 US Code (USC), Section 9601 et. seq, as amended and, the National Oil and Hazardous Substance Pollution Contingency Plan (NCP), Title 40 of the Code of Federal Regulations (CFR) Section 300.430(f) (2). The objective of this project is to clean up radioactive waste at SLDA. The radioactive waste contains special nuclear material (SNM), primarily U-235, in 10 burial trenches, Cabrera duties include processing, packaging and transporting the waste to an offsite disposal facility in accordance with the selected remedial alternative as defined in the Final Record of Decision (USACE, 2007). Of particular importance during the remediation is the need to address nuclear criticality safety (NCS) controls for the safe exhumation and management of waste containing fissile materials. The partnership between Cabrera Services, Inc. and Measutronics Corporation led to the development of a valuable survey tool and operating procedure that are essential components of the SLDA Criticality Safety and Material Control and Accountability programs. Using proven existing technologies in the design and manufacture of the Mobile Survey Cart, the continued deployment of the Cart will allow for an efficient and reliable methodology to allow for the safe exhumation of the Special Nuclear Material in existing SLDA trenches. (authors)

Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike [Cabrera Services (United States); Matthews, Brian [Nuclear Safety Associates (United States)

2012-07-01T23:59:59.000Z

145

Radiological Control Manual  

SciTech Connect (OSTI)

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

Not Available

1993-04-01T23:59:59.000Z

146

Challenges in defining a radiologic and hydrologic source term for underground nuclear test centers, Nevada Test Site, Nye County, Nevada  

SciTech Connect (OSTI)

The compilation of a radionuclide inventory for long-lived radioactive contaminants residual from nuclear testing provides a partial measure of the radiologic source term at the Nevada Test Site. The radiologic source term also includes potentially mobile short-lived radionuclides excluded from the inventory. The radiologic source term for tritium is known with accuracy and is equivalent to the hydrologic source term within the saturated zone. Definition of the total hydrologic source term for fission and activation products that have high activities for decades following underground testing involves knowledge and assumptions which are presently unavailable. Systematic investigation of the behavior of fission products, activation products and actinides under saturated or Partially saturated conditions is imperative to define a representative total hydrologic source term. This is particularly important given the heterogeneous distribution of radionuclides within testing centers. Data quality objectives which emphasize a combination of measurements and credible estimates of the hydrologic source term are a priority for near-field investigations at the Nevada Test Site.

Smith, D.K.

1995-06-01T23:59:59.000Z

147

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH04, Shiprock, New Mexico, September-November 1982  

SciTech Connect (OSTI)

The radiological assessment conducted at the Shiprock vicinity property SH04 by the ANL Radiological Survey Group indicated background levels of radioactivity within the residential structure. Short-term radon daughter measurements did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard (40 CFR 192.12(b)(1)). The assessment indicated elevated levels of radioactivity at several areas in the outside environs. Twelve discrete hot spots or localized areas were found in the backyard, most associated with small slabs of decorative flagstone. Radiochemical analyses of the stone sample collected from one of the localized areas indicated the presence of natural uranium ore. Radiochemical analysis of the soil sample collected from one other of the localized areas indicated a radium concentration of 33 +- 3 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in Section 192.12(a)(1) of the EPA Standard. From the analyses of the samples and the history of the site, the contaminating material in the general area at the backyard and alleyway, in the area in the frontyard, and at several of the discrete locations in the backyard appears to be residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978 in the form of radium-enhanced material (i.e., tailings) and natural uranium ore. Since the surface soil contamination levels exceed the limits specified in the EPA Standard, remedial action for this vicinity site should be considered. 10 references, 4 figures, 5 tables.

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

1984-05-01T23:59:59.000Z

148

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH05, Shiprock, New Mexico, August-November 1982  

SciTech Connect (OSTI)

The radiological assessment conducted at the Shiprock vicinity property SH05 by the ANL Radiological Survey Group indicated background levels of radioactivity within the residential structure. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard (40 CFR 192.12(b)(2)). Short-term radon daughter measurements within the residence did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard (Section 192.12(b)(1)). The assessment indicated elevated levels of radioactivity at several areas in the outside environs. One discrete hot spot or localized area was found in the frontyard, near the front porch of the residence. Radiochemical analysis of the soil sample collected there indicated a radium concentration of 352 +- 35 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in Section 192.12(a)(1) of the EPA Standard. From soil sample analyses and the history of the site, the contaminating material appears to be residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978 in the form of radium-enhanced material (i.e., tailings) and natural uranium ore. Since the surface soil contamination levels exceed the limits specified in the EPA Standard, remedial action for this vicinity site should be considered. 10 references, 4 figures, 5 tables.

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

1984-05-01T23:59:59.000Z

149

ORNL/TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORAT...  

Office of Legacy Management (LM)

R.D. Foley - Field Survey Supervisor Survey Team Members A. C. Butler J. H. Rice C. Johnson C. A: Muhr W. Winton Work performed as part of the MEASUREMENT APPLICATIONS AND...

150

Potential Offsite Radiological Doses Estimated for the Proposed Divine Strake Experiment, Nevada Test Site  

SciTech Connect (OSTI)

An assessment of the potential radiation dose that residents offsite of the Nevada Test Site (NTS) might receive from the proposed Divine Strake experiment was made to determine compliance with Subpart H of Part 61 of Title 40 of the Code of Federal Regulations, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities. The Divine Strake experiment, proposed by the Defense Threat Reduction Agency, consists of a detonation of 700 tons of heavy ammonium nitrate fuel oil-emulsion above the U16b Tunnel complex in Area 16 of the NTS. Both natural radionuclides suspended, and historic fallout radionuclides resuspended from the detonation, have potential to be transported outside the NTS boundary by wind. They may, therefore, contribute radiological dose to the public. Subpart H states ''Emissions of radionuclides to the ambient air from Department of Energy facilities shall not exceed those amounts that would cause any member of the public to receive in any year an effective dose equivalent of 10 mrem/yr'' (Title 40 of the Code of Federal Regulations [CFR] 61.92) where mrem/yr is millirem per year. Furthermore, application for U.S. Environmental Protection Agency (EPA) approval of construction of a new source or modification of an existing source is required if the effective dose equivalent, caused by all emissions from the new construction or modification, is greater than or equal to 0.1 mrem/yr (40 CFR 61.96). In accordance with Section 61.93, a dose assessment was conducted with the computer model CAP88-PC, Version 3.0. In addition to this model, a dose assessment was also conducted by the National Atmospheric Release Advisory Center (NARAC) at the Lawrence Livermore National Laboratory. This modeling was conducted to obtain dose estimates from a model designed for acute releases and which addresses terrain effects and uses meteorology from multiple locations. Potential radiation dose to a hypothetical maximally exposed individual at the closest NTS boundary to the proposed Divine Strake experiment, as estimated by the CAP88-PC model, was 0.005 mrem with wind blowing directly towards that location. Boundary dose, as modeled by NARAC, ranged from about 0.006 to 0.007 mrem. Potential doses to actual offsite populated locations were generally two to five times lower still, or about 40 to 100 times lower then the 0.1 mrem level at which EPA approval is required pursuant to Section 61.96.

Ron Warren

2006-12-01T23:59:59.000Z

151

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH12, Shiprock, NM, October-November 1982  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH12 was conducted on an intermittent basis from October 27 to November 22, 1982. At the time of the survey, several exhibition halls and concession stands; an auction yard; a race track and rodeo arena with associated stands, shutes, and corrals; and a hogan were located on the property. The surrounding environs were either sparsely covered with arid vegetation or covered with gravel. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air, soil, and other material samples. The radiological assessment indicated elevated levels of radioactivity within only one of the structures. Background levels of radioactivity were indicated within all other structures. The assessment indicated elevated levels of radioactivity at the rodeo arena and nearby shutes and corrals, encompassing about 49,000 ft/sup 2/ of land. Radiochemical analysis of the soil sample collected from this general area indicated 23 +- 2 pCi/g for radium, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface. Elevated levels of radioactivity were also found at the southern end of the west parking lot, encompassing about 7500 ft/sup 2/ of land, and at several areas in the southern section of the property, encompassing about 160,000 ft/sup 2/ of land. Radiochemical analyses of two of the soil samples collected from the southern section indicated radium concentrations of 43 +- 5 and 42 +- 5 pCi/g of soil, in excess of the limit of 5 pCi/g above background as specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known.

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

1984-04-01T23:59:59.000Z

152

Radiological Dose Assessment 8 2011 Site environmental report8-1  

E-Print Network [OSTI]

) and 61 ± 10 mrem (610 ± 100 Sv) at off-site locations. Both on- and off-site dose measurements include doses measured using 49 on-site thermoluminescent dosimeters (TLDs) and 14 off-site TLDs showed is also posted with TLDs to assess the dose impact, if any, beyond the site's boundaries. On- and off-site

153

Radiological Dose Assessment 8 2004 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network [OSTI]

Sv) on site and 62 ± 10 mrem (620 ± 100 µSv) at off-site locations. Both measurements include contributions measured at 47 on-site and 16 off-site thermoluminescent dosimeters (TLDs) showed direct penetrating radiation expo- sures both on and off site. The direct measure- ments taken at the off-site

154

Radiological survey of the Mare Island Naval Shipyard, Alameda Naval Air Station, and Hunters Point Shipyard  

SciTech Connect (OSTI)

Since 1963, the Eastern Environmental Radiation Facility (EERF), US Environmental Protection Agency (USEPA), in cooperation with the US Naval Sea Systems Command (NAVSEA) has surveyed facilities serving nuclear-powered warships on the Atlantic and Pacific coasts and the Gulf of Mexico. These surveys assess whether the operation of nuclear-powered warships, during construction, maintenance, overhaul, or refueling, have created elevated levels of radioactivity. The surveys emphasize sampling those areas and pathways that could expose the public. In 1984, NAVSEA requested that EPA survey all active facilities serving nuclear-powered warships over the next three years. This report contains the results of surveys conducted at Naval facilities located at Mare Island, Alameda, and Hunters Point in the San Francisco region. The locations of these facilities are shown. 3 refs., 4 figs., 3 tabs.

Semler, M.O.; Blanchard, R.L. (Environmental Protection Agency, Montgomery, AL (USA). Eastern Environmental Radiation Facility)

1989-06-01T23:59:59.000Z

155

Radiological Dose Assessment 8 2012 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network [OSTI]

to members of the public is calculated at an off-site location closest to emission source as the maximum dose that could be received by an off-site individual defined as the "maximally exposed off-site individual) and 62 ± 10 mrem (620 ± 100 Sv) at off-site locations. Both on- and off-site external dose measurements

156

Radiological Dose Assessment 8 2003 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network [OSTI]

± 10 mrem (640 ± 100 Sv) on site and 61 ± 9 mrem (610 ± 90 Sv) at off-site locations. Both comparison of the average doses from 56 on- site and 18 off-site thermoluminescent dosimeters showed sources. This is achieved by measur- ing direct penetrating radiation exposures both on and off site

Homes, Christopher C.

157

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH02 Shiprock, New Mexico, August-November 1984  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH02 was conducted on an intermittent basis from August 3 to November 11, 1982. At the time of the survey, seven structures were located on the property - two residential trailers, one institutional building, two institutional trailers, a storage building, and a pump house. The lands surrounding the structures were either sparsely covered with vegetation or gravelled. The assessment activities included determination of indoor and outdoor surface radiation levels through direct instrument surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analysis of air and soil samples. No evidence of radioactive contamination was found inside the structures; background levels of radioactivity were indicated within all seven. The short-term radon daughter measurements did not exceed the limit of 0.02 Working Level for average annual concentration including background, as specified in the EPA Standard 40 CFR 192. The assessment indicated elevated levels of radioactivity at one general area in the outdoor environs, encompassing about 1400 ft/sup 2/ (130 m/sup 2/) of land along the property's northern boundary. Analysis of a surface soil sample collected from this area indicated a radium concentration considerably in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination level exceeded the limit specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-04-01T23:59:59.000Z

158

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH11, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure used as a business office was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at a few areas in the outside environs. Two discrete hot spots or localized areas were found in the frontyard. A general area of elevated radioactivity was found at the back alleyway encompassing about 1100 ft/sup 2/. Radiochemical analyses of the sample collected from one of the localized areas indicated the presence of natural uranium ore and a radium concentration of 165 +- 17 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of surface soil samples collected at the alleyway from nearby vicinity property sites also indicated radium concentrations in excess of the limits. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

159

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH08, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at a few areas in the outside environs. A general area of elevated radioactivity was found at the west edge of the property, paralleling the roadway and encompassing an area of about 70 ft/sup 2/; and another general area of contamination was found in the backyard, encompassing about 960 ft/sup 2/, and extending into the alleyway, encompassing a general area of about 1100 ft/sup 2/ there. Radiochemical analyses of the soil sample collected from the general area in the backyard indicated a radium concentration of 6.7 +- 0.7 pCi/g, which cannot be confidently interpreted to be below the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface. However, analyses of surface soil samples collected at the alleyway from nearby vicinity property sites indicated radium concentrations in excess of those limits. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

160

Radiological review of conditions created during & after a fire on the Hanford Site in the BC Crib controlled area & areas of radiological concern  

SciTech Connect (OSTI)

The radiological implications of fighting a wildland fire in the BC Crib controlled area with the surrounding Soil Contamination Area (SCA) and for fighting a wildland fire in the genera1 600 Area are addressed in this document. The primary focus is on the BC Crib controlled area; however, the 600 Area radiological concerns are much lower and generally have the same constraints as the BC Crib controlled area. This analysis addresses only radiological hazards and does not address any physical hazards or industrial hygiene hazards.

EVANS, C.L.

2003-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

8-1 2001 SITE ENVIRONMENTAL REPORT CHAPTER 8: RADIOLOGICAL DOSE ASSESSMENT  

E-Print Network [OSTI]

. The ambient on-site external dose was 75.5 ± 10 mrem (755 ± 100 mSv) per year and the off-site ambient. A statistical comparison of the on-site and off-site average dose values indicated that there was no additional. To evaluate the potential impact of BNL operations, TLDs are deployed at BNL and off site, where members

Homes, Christopher C.

162

Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network [OSTI]

to members of the public is calculated at an off-site location closest to an emission source as the maximum dose that could be received by an off-site individual, defined as the "maximally exposed off-site mrem (660 ± 80 Sv) and 61 ± 7 mrem (610 ± 70 Sv) from off-site ambient sources. Both on- and off-site

163

Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network [OSTI]

was 66 ± 12 mrem (660 ± 120 Sv) and 61 ± 11 mrem (610 ± 110 Sv) at off-site locations. Both on- and off-site) and 14 off-site TLDs showed that there was no external dose contribution from BNL operations, if any, beyond the site's boundaries. On- and off-site locations are divided into grids, and each TLD

164

8-1 2002 SITE ENVIRONMENTAL REPORT CHAPTER 8: RADIOLOGICAL DOSE ASSESSMENT  

E-Print Network [OSTI]

photon energy (i.e., light), which is measured with a photomultiplier tube; the light #12;8-22002 SITE and the Department of Energy. The average annual ambient external dose reading on site was 71 ± 15 mrem (710 ± 150 m from all pathways is 100 mrem (1,000 mSv). Additionally, 10 on-site remediation and waste management

Homes, Christopher C.

165

Urandium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH06, Shiprock, New Mexico, August-November 1982  

SciTech Connect (OSTI)

The radiological assessment conducted at the Shiprock vicinity property SH06 by the ANL Radiological Survey Group indicated background levels of radioactivity within the residential structure. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard (40 CFR 192.12(b)(2)). Short-term radon daughter measurements did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard (40 CFR 192.12(b)(1)). The assessment indicated elevated levels of radioactivity at several areas in the outside environs. General areas of elevated radioactivity were found over almost the entire frontyard, encompassing about 1300 ft/sup 2/ (120 m/sup 2/), and at the west side of the residence, encompassing about 460 ft/sup 2/ (43 m/sup 2/). Radiochemical analysis of the soil sample collected from the frontyard near the residence indicated a radium concentration of 24 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in Section 192.12(a)(1) of the EPA Standard. Elevated levels were also found at a 37-ft/sup 2/ (3.4-m/sup 2/) strip of land along the east property line, and in the backyard, at a small shack encompassing about 21 ft/sup 2/ (2.0 m/sup 2/) of land. From soil sample analyses and the history of the site, the contaminating material appears to be residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978 in the form of radium-enhanced material (i.e., tailings). Since the surface soil contamination levels exceed the limits specified in the EPA Standard, remedial action for this vicinity site should be considered. 9 references, 4 figures, 5 tables.

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

1984-05-01T23:59:59.000Z

166

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH15, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were landscaped with lawn cover and other vegetation. The lands in the unlandscaped east section contained a large garden plot and a dirt driveway leading to the back easement. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background as specified in the EPA Standard. The assessment indicated elevated levels of radioactivity in the outside environs. General areas of contamination were found in the backyard, along the back easement and encompassing about 1200 ft/sup 2/ of land area there, and extending into the unlandscaped east section, encompassing about 2400 ft/sup 2/ there. Several discrete hot spots or localized areas were found within these general areas. Radiochemical analysis of the soil samples collected from the areas indicated radium concentrations of 64 +- 6 and 82 +- 8 pCi/g, which are in excess of the limit of 5 pCi/g above background. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is now known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

167

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184  

SciTech Connect (OSTI)

The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: ? Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. ? DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. ? DOE must continue to maintain constructive relationships with the U.S. Army Corps of Engineers and state and federal regulators.

Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

2012-02-26T23:59:59.000Z

168

RADIOLOGICAL SURVEY OF A PORTION OF PROPERTY OWNED BY MODERN LANDFILL, INC. -  

Office of Legacy Management (LM)

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169

Radiological Survey Data for 38 Grove Avenue, Rochelle Park, l'lew Jersey  

Office of Legacy Management (LM)

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170

Radiologic characterization of the Mexican Hat, Utah, uranium mill tailings remedial action site: Appendix D, Addenda D1--D7  

SciTech Connect (OSTI)

This radiologic characterization of the inactive uranium millsite at Mexican Hat, Utah, was conducted by Bendix Field Engineering Corporation foe the US Department of Energy (DOE), Grand Junction Project Office, in response to and in accord with a Statement of Work prepared by the DOE Uranium Mill tailings Remedial Action Project (UMTRAP) Technical Assistance Contractor, Jacobs Engineering Group, Inc. the objective of this project was to determine the horizontal and vertical extent of contamination that exceeds the US Environmental Protection Agency (EPA) standards at the Mexican Hat site. The data presented in this report are required for characterization of the areas adjacent to the Mexican Hat tailings piles and for the subsequent design of cleanup activities. Some on-pile sampling was required to determine the depth of the 15-pCi/g Ra-226 interface in an area where wind and water erosion has taken place.

Ludlam, J.R.

1985-01-01T23:59:59.000Z

171

Results of the radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania (ANK001). Environmental Restoration and Waste Management Non-Defense Programs  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Manhattan Engineer District in 1944. The survey included measurement of direct alpha and beta-gamma levels in the northeast comer of the basement of Building 29, and the collection of a debris sample from a floor drain for radionuclide analysis. The survey area was used for experimental canning of uranium slugs prior to production activities at the former New Kensington Works nearby.

Foley, R.D.; Brown, K.S.

1992-10-01T23:59:59.000Z

172

Radiological survey of the inactive uranium-mill tailings at Green River, Utah  

SciTech Connect (OSTI)

The uranium-mill tailings at Green River, Utah, are relatively low in /sup 226/Ra content and concentration (20 Ci and 140 pCi/g, respectively) because the mill was used to upgrade the uranium ore by separating the sand and slime fractions; most of the radium was transported along with the slimes to another mill site. Spread of tailings was observed in all directions, but near-background gamma exposure rates were reached at distances of 40 to 90 m from the edge of the pile. Water erosion of the tailings is evident and, since a significant fraction of the tailings pile lies in Brown's Wash, the potential exists for repetition of the loss of a large quantity of tailings such as occurred during a flood in 1959. In general, the level of surface contamination was low at this site, but some areas in the mill site, which were being used for nonuranium work, have gamma-ray exposure rates up to 143 ..mu..R/hr.

Haywood, F.F.; Christian, D.J.; Ellis, B.S.; Hubbard, H.M. Jr.; Lorenzo, D.; Shinpaugh, W.H.

1980-03-01T23:59:59.000Z

173

NNSA to Conduct Aerial Radiological Surveys Over Washington, D.C. and  

National Nuclear Security Administration (NNSA)

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174

Site environmental report for Calendar Year 1994 on radiological and nonradiological parameters  

SciTech Connect (OSTI)

Battelle Memorial Institute`s nuclear research facilities are currently being maintained in a surveillance and maintenance (S&M) mode with continual decontamination and decommissioning (D&D) activities being conducted under Department of Energy (DOE) Contract W-7405-ENG-92. These activities are referred to under the Contract as the Battelle Columbus Laboratories Decommissioning Project (BCLDP). Operations referenced in this report are performed in support of S&M and D&D activities. Battelle`s King Avenue facility is not considered in this report to the extent that the West Jefferson facility is. The source term at the King Avenue site is a small fraction of the source term at the West Jefferson site. Off site levels of radionuclides that could be attributed to the west Jefferson and King Avenue nuclear operations wereindistinguishable from background levels at specific locations where air, water, and direct radiation measurements were performed. Environmental monitoring continued to demonstrate compliance by Battelle with federal, state and local regulations. Routine, nonradiological activities performed include monitoring liquid effluents and monitoring the ground water system for the West Jefferson North site. Samples of various environmental media including air, water, grass, fish, field and garden crops, sediment and soil were collected from the region surrounding the two sites and analyzed.

NONE

1995-06-30T23:59:59.000Z

175

Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the Marine Sciences Laboratory, Sequim Site  

SciTech Connect (OSTI)

This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006), as well as several other published DQOs. The intent of this report is to determine the necessary steps required to ensure that radioactive emissions to the air from the Marine Sciences Laboratory (MSL) headquartered at the Pacific Northwest National Laboratory’s Sequim Marine Research Operations (Sequim Site) on Washington State’s Olympic Peninsula are managed in accordance with regulatory requirements and best practices. The Sequim Site was transitioned in October 2012 from private operation under Battelle Memorial Institute to an exclusive use contract with the U.S. Department of Energy, Office of Science, Pacific Northwest Site Office.

Barnett, J. M.; Meier, Kirsten M.; Snyder, Sandra F.; Antonio, Ernest J.; Fritz, Brad G.; Poston, Theodore M.

2012-12-27T23:59:59.000Z

176

Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River site  

SciTech Connect (OSTI)

Since the early 1950s, the Savannah River Site (SRS) released over 50 radionuclides into the environment while producing nuclear defense materials. These releases directly exposed aquatic and terrestrial biota to ionizing radiation from surface water, soil, and sediment, and also indirectly by the ingestion of items in the food chain. As part of new missions to develop waste management strategies and identify cost-effective environmental restoration options, knowledge concerning the uptake and distribution of these radionuclides is essential. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at SRS.

Friday, G.P.; Cummins, C.L.; Schwartzman, A.L.

1996-12-31T23:59:59.000Z

177

Confirmatory radiological survey of the BORAX-V turbine building Idaho National Engineering Laboratory, Idaho Falls, Idaho  

SciTech Connect (OSTI)

An independent assessment of the remediation of the BORAX-V (Boiling Water Reactor Experiment) turbine building at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho, was accomplished by the Oak Ridge National Laboratory Pollutant Assessments Group (ORNL/PAG). The purpose of the assessment was to confirm the site`s compliance with applicable Department of Energy guidelines. The assessment included reviews of both the decontamination and decommissioning Plan and data provided from the pre- and post-remedial action surveys and an independent verification survey of the facility. The independent verification survey included determination of background exposure rates and soil concentrations, beta-gamma and gamma radiation scans, smears for detection of removable contamination, and direct measurements for alpha and beta-gamma radiation activity on the basement and mezzanine floors and the building`s interior and exterior walls. Soil samples were taken, and beta-gamma and gamma radiation exposure rates were measured on areas adjacent to the building. Results of measurements on building surfaces at this facility were within established contamination guidelines except for elevated beta-gamma radiation levels located on three isolated areas of the basement floor. Following remediation of these areas, ORNL/PAG reviewed the remedial action contractor`s report and agreed that remediation was effective in removing the source of the elevated direct radiation. Results of all independent soil analyses for {sup 60}Co were below the detection limit. The highest {sup 137}Cs analysis result was 4.6 pCi/g; this value is below the INEL site-specific guideline of 10 pCi/g.

Stevens, G.H.; Coleman, R.L.; Jensen, M.K.; Pierce, G.A. [Oak Ridge National Lab., TN (US); Egidi, P.V.; Mather, S.K. [Oak Ridge Inst. for Science and Education, Grand Junction, CO (United States)

1993-07-01T23:59:59.000Z

178

BCLDP site environmental report for calendar year 1997 on radiological and nonradiological parameters  

SciTech Connect (OSTI)

Battelle Memorial Institute currently maintains its retired nuclear research facilities in a surveillance and maintenance (S and M) mode and continues decontamination and decommissioning (D and D) activities. The activities are referred to as the Battelle Columbus Laboratories Decommissioning Project (BCLDP). Operations reference in this report are performed in support of S and M and D and D activities. The majority of this report is devoted to discussion of the West Jefferson facility, because the source term at this facility is larger than the source term at Battelle`s King Avenue site. The contamination found at the King Avenue site consists of small amounts of residual radioactive material in solid form, which has become embedded or captured in nearby surfaces such as walls, floors, ceilings, drains, laboratory equipment, and soils. By the end of calendar year (CY) 1997, most remediation activities were completed at the King Avenue site. The contamination found at the West Jefferson site is the result of research and development activities with irradiated materials. During CY 1997, multiple tests at the West Jefferson Nuclear Sciences Area found no isotopes present above the minimum detectable activity (MDA) for air releases or for liquid discharges to Big Darby Creek. Data obtained from downstream sampling locations were statistically indistinguishable from background levels.

Fry, J.

1998-09-30T23:59:59.000Z

179

PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE  

Office of Legacy Management (LM)

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180

Environmental radiological monitoring of air, rain, and snow on and near the Hanford Site, 1945-1957  

SciTech Connect (OSTI)

This report is a result of the Hanford Environmental Dose Reconstruction (HEDR) Project. The goal of the HEDR Project is to estimate the radiation dose that individuals could have received from emissions since 1944 at the Hanford Site near Richland, Washington. Members of the HEDR Project`s Environmental Monitoring Data Task have developed databases of historical environmental measurements of such emissions. Hanford documents were searched for information on the radiological monitoring of air, rain, and snow at and near the Hanford Site in Richland, Washington. The monitoring information was reviewed and summarized. The end product is a yearly overview of air, rain, and snow samples as well as ambient radiation levels in the air that were measured from 1945 through 1957. The following information is provided in each annual summary: the media sampled, the constituents (radionuclides) measured/reported, the sampling locations, the sampling frequencies, the sampling methods, and the document references. For some years a notes category is included that contains additional useful information. For the years 1948 through 1957, tables summarizing the sampling locations for the various sample media are also included in the appendix. A large number of documents were reviewed to obtain the information in this report. A reference list is attached to the end of each annual summary. All of the information summarized here was obtained from reports originating at Hanford. These reports are all publicly available and can be found in the Richland Operations Office (RL) public reading room. The information in this report has been compiled without analysis and should only be used as a guide to the original documents.

Hanf, R.W.; Thiede, M.E.

1994-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

ORNL-5680 Radiological Surveys  

Office of Legacy Management (LM)

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182

radiological | EMSL  

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

radiological radiological Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a candidate...

183

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Federal Radiological Monitoring and Assessment Center Emergency Response Accident Response Group Radiation Emergency Assistance Center Training Site National Atmospheric Release...

184

Multi-agency radiation survey and site investigation manual (MARSIM). Final report  

SciTech Connect (OSTI)

The MARSSIM provides information on planning, conducting, evaluating, and documenting building surface and surface soil final status radiological surveys for demonstrating compliance with dose or risk-based regulations or standards. The MARSSIM is a multi-agency consensus document that was developed collaboratively by four Federal agencies having authority and control over radioactive materials: Department of Defense (DOD), Department of Energy (DOE), Environmental Protection Agency (EPA), and Nuclear Regulatory Commission (NRC). The MARSSIM`s objective is to describe a consistent approach for planning, performing, and assessing building surface and surface soil final status surveys to meet established dose or risk-based release criteria, while at the same time encouraging an effective use of resources.

NONE

1997-12-01T23:59:59.000Z

185

"CONFIRMATORY SURVEY RESULTS FOR THE ABB COMBUSTION ENGINEERING SITE WINDSOR, CONNECTICUT DCN 5158-SR-02-2  

SciTech Connect (OSTI)

The objectives of the confirmatory activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the contractor?s procedures and FSS results. ORAU reviewed ABB CE?s decommissioning plan, final status survey plan, and the applicable soil DCGLs, which were developed based on an NRC-approved radiation dose assessment. The surveys include gamma surface scans, gamma direct measurements, and soil sampling.

ADAMS, WADE C

2013-03-25T23:59:59.000Z

186

Archaeological survey of the McGee Ranch vicinity, Hanford Site, Washington  

SciTech Connect (OSTI)

In response to a request for a cultural resources review from Westinghouse Hanford Company for the Action Plan for Characterization of McGee Ranch Soil, Pacific Northwest Laboratory`s Hanford Cultural Resources Laboratory (HCRL) conducted an archaeological survey of the McGee Ranch vicinity, located in the northwest portion of the Hanford Site. Staff members covered 8.4 km{sup 2} and recorded 42 cultural resources; 22 sites, and 20 isolated artifacts. Only 2 sites and 3 isolates were attributed to a prehistoric Native American occupation. The historic sites date from the turn of the century to the 1940s and are representative of the settlement patterns that occurred throughout the Columbia Basin. In addition to an archaeological pedestrian survey of the project area, we conducted literature and records searches and examined available aerial photographs. Records kept at HCRL were reviewed to determine if any archaeological survey had been conducted previously within the project area. Although no survey had been conducted, portions of the area adjacent to project boundaries were surveyed in 1988 and 1990. During those surveys, historic and prehistoric cultural resources were observed, increasing the possibility that similar land usage had taken place within the current project boundaries. Literature searches established a general historical sequence for this area. Aerial photographs alerted researchers to homesteads and linear features, such as roads and irrigation ditches, that might not be apparent from ground level.

Gard, H.A.; Poet, R.M.

1992-09-01T23:59:59.000Z

187

Archaeological survey of the McGee Ranch vicinity, Hanford Site, Washington  

SciTech Connect (OSTI)

In response to a request for a cultural resources review from Westinghouse Hanford Company for the Action Plan for Characterization of McGee Ranch Soil, Pacific Northwest Laboratory's Hanford Cultural Resources Laboratory (HCRL) conducted an archaeological survey of the McGee Ranch vicinity, located in the northwest portion of the Hanford Site. Staff members covered 8.4 km{sup 2} and recorded 42 cultural resources; 22 sites, and 20 isolated artifacts. Only 2 sites and 3 isolates were attributed to a prehistoric Native American occupation. The historic sites date from the turn of the century to the 1940s and are representative of the settlement patterns that occurred throughout the Columbia Basin. In addition to an archaeological pedestrian survey of the project area, we conducted literature and records searches and examined available aerial photographs. Records kept at HCRL were reviewed to determine if any archaeological survey had been conducted previously within the project area. Although no survey had been conducted, portions of the area adjacent to project boundaries were surveyed in 1988 and 1990. During those surveys, historic and prehistoric cultural resources were observed, increasing the possibility that similar land usage had taken place within the current project boundaries. Literature searches established a general historical sequence for this area. Aerial photographs alerted researchers to homesteads and linear features, such as roads and irrigation ditches, that might not be apparent from ground level.

Gard, H.A.; Poet, R.M.

1992-09-01T23:59:59.000Z

188

ORISE: Multi-Agency Radiation Survey and Site Investigation Manual  

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

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189

DESIGNATION SURVEY ADDENDUM REPORT II COMBUSTION ENGINEERING SITE  

Office of Legacy Management (LM)

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190

Independent Verification Survey Report for the Operable Unit-1 Miamisburg Closure Project, Miamisburg, OH  

SciTech Connect (OSTI)

The objectives of the independent verification survey were to confirm that remedial actions have been effective in meeting established release criteria and that documentation accurately and adequately describes the current radiological and chemical conditions of the MCP site.

Weaver, P.

2008-03-17T23:59:59.000Z

191

Fiscal year 1991 report on archaeological surveys of the 100 Areas, Hanford Site, Washington  

SciTech Connect (OSTI)

In compliance with Section 106 of the National Historic Preservation Act (NHPA), and at the request of Westinghouse Hanford Company, the Hanford Cultured Resources Laboratory (HCRL) conducted an archaeological survey during FY 1991 of the 100-Area reactor compounds on the US Department of Energy's Hanford Site. This survey was conducted as part of a comprehensive resources review of 100-Area Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) operable units in support of CERCLA characterization activities. The work included a lite and records review and pedestrian survey of the project area following procedures set forth in the Hanford Cultural Resources Management Plan.

Chatters, J.C.; Gard, H.A.; Minthorn, P.E.

1992-09-01T23:59:59.000Z

192

Fiscal year 1991 report on archaeological surveys of the 100 Areas, Hanford Site, Washington  

SciTech Connect (OSTI)

In compliance with Section 106 of the National Historic Preservation Act (NHPA), and at the request of Westinghouse Hanford Company, the Hanford Cultured Resources Laboratory (HCRL) conducted an archaeological survey during FY 1991 of the 100-Area reactor compounds on the US Department of Energy`s Hanford Site. This survey was conducted as part of a comprehensive resources review of 100-Area Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) operable units in support of CERCLA characterization activities. The work included a lite and records review and pedestrian survey of the project area following procedures set forth in the Hanford Cultural Resources Management Plan.

Chatters, J.C.; Gard, H.A.; Minthorn, P.E.

1992-09-01T23:59:59.000Z

193

Radiological Control Manual. Revision 0, January 1993  

SciTech Connect (OSTI)

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

Not Available

1993-04-01T23:59:59.000Z

194

Radionuclide site survey report, Ashland, Kansas (RN-74). Final technical report  

SciTech Connect (OSTI)

The purpose of this report is to validate that the Ashland, Kansas site will fulfill treaty requirements as set forth by the Preparatory Commission for the Comprehensive Test Ban Treaty Organization. The team performing the site survey followed accepted scientific methods in collecting air and soil samples near the proposed site. The samples were analyzed by the McClellan Central Laboratory and the results forwarded to AFTAC/TM for review. The team included meteorological and technical staff. Possible sources of radionuclides were examined, as well as meteorological conditions that might affect the validity of recorded data at the site. All necessary background information required by the Commission was researched and is included in the report. The analysis of the samples identifies all radionuclide isotopes and their sources that might affect future samples at the site. There are no significant findings that would prevent this site from meeting treaty requirements.

Walker, F.; Lucas, J.; Owen, M.; McKethan, E.M.; MacCartney, J.

1999-01-07T23:59:59.000Z

195

Archaeological survey of the 200 East and 200 West Areas, Hanford Site, Washington  

SciTech Connect (OSTI)

Responding to a heavy demand for cultural resource reviews of excavation sites, the Westinghouse Hanford Company contracted with Pacific Northwest Laboratory to conduct a comprehensive archaeological resource review for the 200 Areas of the Hanford Site, Washington. This was accomplished through literature and records review and an intensive pedestrian survey of all undisturbed portions of the 200 East Area and a stratified random sample of the 200 West Area. The survey, followed the Secretary of the Interior's guidelines for the identification of historic properties. The result of the survey is a model of cultural resource distributions that has been used to create cultural resource zones with differing degrees of sensitivity. 11 refs., 7 figs., 1 tab.

Chatters, J.C.; Cadoret, N.A.

1990-03-01T23:59:59.000Z

196

Fiscal year 1992 report on archaeological surveys of the 100 Areas, Hanford Site, Washington  

SciTech Connect (OSTI)

During FY 1992, the Hanford Cultural Resources Laboratory (HCRL) conducted a field survey of the 100-HR-3 Operable Unit (600 Area) and tested three sites near the 100 Area reactor compounds on the US Department of Energy`s Hanford Site at the request of Westinghouse Hanford Company. These efforts were conducted in compliance with Section 106 of the National Historic Preservation Act (NHPA) and are part of a cultural resources review of 100 Area Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) operable units in support of CERCLA characterization studies.The results of the FY 1992 survey and test excavation efforts are discussed in this report. 518 ha in the 100-HR-3 Operable Unit and conducted test excavations at three prehistoric sites near the 100-F and 100-K reactors to determine their eligibility for listing on the National Register of Historic Places.

Wright, M.K.

1993-09-01T23:59:59.000Z

197

Radiological-dose assessments of atolls in the northern Marshall Islands  

SciTech Connect (OSTI)

The Marshall Islands in the Equatorial Pacific, specifically Enewetak and Bikini Atolls, were the site of US nuclear testing from 1946 through 1958. In 1978, the Northern Marshall Islands Radiological Survey was conducted to evaluate the radiological conditions of two islands and ten atolls downwind of the proving grounds. The survey included aerial external gamma measurements and collection of soil, terrestrial, and marine samples for radionuclide analysis to determine the radiological dose from all exposure pathways. The methods and models used to estimate doses to a population in an environment where natural processes have acted on the source-term radionuclides for nearly 30 y, data bases developed for the models, and results of the radiological dose analyses are described.

Robison, W.L.

1983-04-01T23:59:59.000Z

198

2010 Dry and 2009 - 2010 Wet Season Branchiopod Survey Report, Site 300  

SciTech Connect (OSTI)

Lawrence Livermore National Laboratory (LLNL) requested that Condor Country Consulting, Inc. (CCCI) perform wet season surveys and manage the dry season sampling for listed branchiopods in two ponded locations within the Site 300 Experimental Test Site. Site 300 is located in Alameda and San Joaquin Counties, located between the Cities of Livermore and Tracy. The two pool locations have been identified for possible amphibian enhancement activities in support of the Compensation Plan for impacts tied to the Building 850 soil clean-up project. The Building 850 project design resulted in formal consultation with the U.S. Fish and Wildlife Service (USFWS) as an amendment (File 81420-2009-F-0235) to the site-wide Biological Opinion (BO) (File 1-1-02-F-0062) in the spring of 2009 and requires mitigation for the California tiger salamander (AMCA, Ambystoma californiense) and California red-legged frog (CRLF, Rana draytonii) habitat loss. Both pools contain breeding AMCA, but do not produce metamorphs due to limited hydroperiod. The pool to the southeast (Pool BC-FS-2) is the preferred site for amphibian enhancement activities, and the wetland to northwest (Pool OA-FS-1) is the alternate location for enhancement. However, prior to enhancement, LLNL has been directed by USFWS (BO Conservation Measure 17 iii) to 'conduct USFWS protocol-level branchiopod surveys to determine whether listed brachiopod species are present within the compensation area.' CCCI conducted surveys for listed branchiopods in the 2009-2010 wet season to determine the presence of federally-listed branchiopods at the two pools (previous surveys with negative findings were performed by CCCI in 2001-2002 and 2002-2003 onsite). Surveys were conducted to partially satisfy the survey requirements of the USFWS 'Interim Survey Guidelines to Permittees for Recovery Permits under Section 10(a)(1)(A) of the Endangered Species Act for the Listed Vernal Pool Branchiopods' ('Guidelines, USFWS 1996 and BO Conservation Measure 17 iii). The dry sampling (included as an Appendix D) followed the wet season surveys in the summer of 2010.

Dexter, W

2011-03-14T23:59:59.000Z

199

Survey of subsurface treatment technologies for environmental restoration sites at Sandia National Laboratories, New Mexico.  

SciTech Connect (OSTI)

This report provides a survey of remediation and treatment technologies for contaminants of concern at environmental restoration (ER) sites at Sandia National Laboratories, New Mexico. The sites that were evaluated include the Tijeras Arroyo Groundwater, Technical Area V, and Canyons sites. The primary contaminants of concern at these sites include trichloroethylene (TCE), tetrachloroethylene (PCE), and nitrate in groundwater. Due to the low contaminant concentrations (close to regulatory limits) and significant depths to groundwater ({approx}500 feet) at these sites, few in-situ remediation technologies are applicable. The most applicable treatment technologies include monitored natural attenuation and enhanced bioremediation/denitrification to reduce the concentrations of TCE, PCE, and nitrate in the groundwater. Stripping technologies to remove chlorinated solvents and other volatile organic compounds from the vadose zone can also be implemented, if needed.

McGrath, Lucas K.; Ho, Clifford Kuofei; Wright, Jerome L.

2003-08-01T23:59:59.000Z

200

EMSL - radiological  

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

radiological en Diffusional Motion of Redox Centers in Carbonate Electrolytes . http:www.emsl.pnl.govemslwebpublicationsdiffusional-motion-redox-centers-carbonate-electrolytes...

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Confirmatory radiological survey of the Grand Junction Projects Office Remedial Action Project exterior portions, 1989-1995  

SciTech Connect (OSTI)

The purpose of this independent assessment was to provide the U.S. Department of Energy (DOE) with an independent verification (IV) that the soil at the Grand Junction Projects Office (GJPO) complies with applicable DOE guidelines. Oak Ridge National Laboratory/ Environmental Technology Section (ORNL/ETS) which is also located at the GJPO, was assigned by DOE as the Independent Verification Contractor (IVC). The assessment included reviews of the decontamination and decommissioning plan, annual environmental monitoring reports, data in the pre- and post-remedial action reports, reassessment reports and IV surveys. Procedures and field methods used during the remediation were reviewed, commented on, and amended as needed. The IV surveys included beta-gamma and gamma radiation scans, soil sampling and analyses. Based on the data presented in the post-remedial action report and the results of the IV surveys, the remediation of the outdoor portions of the GJPO has achieved the objectives. Residual deposits of uranium contamination may exist under asphalt because the original characterization was not designed to identify uranium and subsequent investigations were limited. The IVC recommends that this be addressed with the additional remediation. The IVC is working with the remedial action contractor (RAC) to assure that final documentation WM be sufficient for certification. The IVC will address additional remediation of buildings, associated utilities, and groundwater in separate reports. Therefore, this is considered a partial verification.

Forbes, G.H.; Egidi, P.V.

1997-04-01T23:59:59.000Z

202

ORNL/RASA-84/LJ2 Health and Safety Research Division RESULTS OF THE RADIOLOGICAL SURVEY AT  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawandaUniversity21 theB 4q-utSPJ\ AA ).

203

ORNL/RASA-84/LJ3 Health and Safety Research Division RESULTS OF THE RADIOLOGICAL SURVEY AT  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawandaUniversity21 theB 4q-utSPJ\ AA ).LJ3

204

ORNL/RASA-84/LJ4 Health and Safety Research Division RESULTS OF THE RADIOLOGICAL SURVEY AT  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawandaUniversity21 theB 4q-utSPJ\ AA

205

A multispectral scanner survey of the Salmon Site and surrounding area, Lamar County, Mississippi  

SciTech Connect (OSTI)

An airborne multispectral scanner survey was conducted over the Salmon Site and the surrounding area in Lamar County, Mississippi, on May 8, 1992. Twelve-channel daytime multispectral data were collected from altitudes of 2,000 feet, 4,000 feet, and 6,000 feet above ground level. Large-scale color photography was acquired simultaneously with the scanner data. Three different composite images have been prepared to demonstrate the digital image enhancement techniques that can be applied to the data. The data that were acquired offer opportunity for further standard and customized analysis based on any specific environmental characterization issues associated with this site.

Blohm, J.D.; Brewster, S.B. Jr.; Shines, J.E.

1994-06-01T23:59:59.000Z

206

Letter Report - Verification Survey of Final Grids at the David Witherspoon, Inc. 1630 Site Knoxville, Tennessee  

SciTech Connect (OSTI)

Conduct verification surveys of grids at the DWI 1630 Site in Knoxville, Tennessee. The independent verification team (IVT) from ORISE, conducted verification activities in whole and partial grids, as completed by BJC. ORISE site activities included gamma surface scans and soil sampling within 33 grids; G11 through G14; H11 through H15; X14, X15, X19, and X21; J13 through J15 and J17 through J21; K7 through K9 and K13 through K15; L13 through L15; and M14 through M16

P.C. Weaver

2009-02-17T23:59:59.000Z

207

Challenges with Final Status Surveys at a Large Decommissioning Site - 13417  

SciTech Connect (OSTI)

As part of decommissioning a former nuclear fuel manufacturing site, one of the crucial final steps is to conduct Final Status Surveys (FSS) in order to demonstrate compliance with the release criteria. At this decommissioning site, the area for FSS was about 100 hectares (248 acres) and included varying terrain, wooded areas, ponds, excavations, buildings and a brook. The challenges in performing the FSS included determining location, identifying FSS units, logging gamma walkover survey data, determining sample locations, managing water in excavations, and diverting water in the brook. The approaches taken to overcome these challenges will be presented in the paper. The paper will present and discuss lessons learned that will aid others in the FSS process. (authors)

Downey, Heath; Collopy, Peter; Shephard, Eugene; Walter, Nelson [AMEC, 511 Congress Street, Portland, ME 04112 (United States)] [AMEC, 511 Congress Street, Portland, ME 04112 (United States); Conant, John [ABB Inc., 5 Waterside Crossing, Windsor, CT 06095 (United States)] [ABB Inc., 5 Waterside Crossing, Windsor, CT 06095 (United States)

2013-07-01T23:59:59.000Z

208

Radiological survey and evaluation of the fallout area from the Trinity test: Chupadera Mesa and White Sands Missile Range, New Mexico  

SciTech Connect (OSTI)

Current radiological conditions were evaluated for the site of the first nuclear weapons test, the Trinity test, and the associated fallout zone. The test, located on White Sands Missile Range, was conducted as part of the research with nuclear materials for the World War II Manhattan Engineer District atomic bomb project. Some residual radioactivity attributable to the test was found in the soils of Ground Zero on White Sands Missile Range and the areas that received fallout from the test. The study considered relevant information including historical records, environmental data extending back to the 1940s, and new data acquired by field sampling and measurements. Potential exposures to radiation were evaluated for current land uses. Maximum estimated doses on Chupadera Mesa and other uncontrolled areas are less than 3% of the DOE Radiation Protection Standards (RPSs). Radiation exposures during visits to the US Army-controlled Ground Zero area are less than 1 mrem per annual visit or less than 0.2% of the RPS for a member of the public. Detailed data and interpretations are provided in appendixes. 14 figs., 45 tabs.

Hansen, W.R.; Rodgers, J.C.

1985-06-01T23:59:59.000Z

209

Interim Letter Report - Verification Survey of 19 Grids in the Lester Flat Area, David Witherspoon Inc. 1630 Site Knoxville, Tennessee  

SciTech Connect (OSTI)

Perform verification surveys of 19 available grids located in the Lester Flat Area at the Davod Witherspoon Site. The survey grids included E11, E12, E13, F11, F12, F13, F14, F15, G15, G16, G17, H16, H17, H18, X16, X17, X18, K16, and J16.

P.C. Weaver

2008-10-17T23:59:59.000Z

210

Siting Study Framework and Survey Methodology for Marine and Hydrokinetic Energy Project in Offshore Southeast Florida  

SciTech Connect (OSTI)

Dehlsen Associates, LLC was awarded a grant by the United States Department of Energy (DOE) Golden Field Office for a project titled 'Siting Study Framework and Survey Methodology for Marine and Hydrokinetic Energy Project in Offshore Southeast Florida,' corresponding to DOE Grant Award Number DE-EE0002655 resulting from DOE funding Opportunity Announcement Number DE-FOA-0000069 for Topic Area 2, and it is referred to herein as 'the project.' The purpose of the project was to enhance the certainty of the survey requirements and regulatory review processes for the purpose of reducing the time, efforts, and costs associated with initial siting efforts of marine and hydrokinetic energy conversion facilities that may be proposed in the Atlantic Ocean offshore Southeast Florida. To secure early input from agencies, protocols were developed for collecting baseline geophysical information and benthic habitat data that can be used by project developers and regulators to make decisions early in the process of determining project location (i.e., the siting process) that avoid or minimize adverse impacts to sensitive marine benthic habitat. It is presumed that such an approach will help facilitate the licensing process for hydrokinetic and other ocean renewable energy projects within the study area and will assist in clarifying the baseline environmental data requirements described in the U.S. Department of the Interior Bureau of Ocean Energy Management, Regulation and Enforcement (formerly Minerals Management Service) final regulations on offshore renewable energy (30 Code of Federal Regulations 285, published April 29, 2009). Because projects generally seek to avoid or minimize impacts to sensitive marine habitats, it was not the intent of this project to investigate areas that did not appear suitable for the siting of ocean renewable energy projects. Rather, a two-tiered approach was designed with the first step consisting of gaining overall insight about seabed conditions offshore southeastern Florida by conducting a geophysical survey of pre-selected areas with subsequent post-processing and expert data interpretation by geophysicists and experienced marine biologists knowledgeable about the general project area. The second step sought to validate the benthic habitat types interpreted from the geophysical data by conducting benthic video and photographic field surveys of selected habitat types. The goal of this step was to determine the degree of correlation between the habitat types interpreted from the geophysical data and what actually exists on the seafloor based on the benthic video survey logs. This step included spot-checking selected habitat types rather than comprehensive evaluation of the entire area covered by the geophysical survey. It is important to note that non-invasive survey methods were used as part of this study and no devices of any kind were either temporarily or permanently attached to the seabed as part of the work conducted under this project.

Vinick, Charles; Riccobono, Antonino, MS; Messing, Charles G., Ph.D.; Walker, Brian K., Ph.D.; Reed, John K., Ph.D.

2012-02-28T23:59:59.000Z

211

Radiological health aspects of uranium milling  

SciTech Connect (OSTI)

This report describes the operation of conventional and unconventional uranium milling processes, the potential for occupational exposure to ionizing radiation at the mill, methods for radiological safety, methods of evaluating occupational radiation exposures, and current government regulations for protecting workers and ensuring that standards for radiation protection are adhered to. In addition, a survey of current radiological health practices is summarized.

Fisher, D.R.; Stoetzel, G.A.

1983-05-01T23:59:59.000Z

212

Radiological Habits Survey, Faslane, 2006  

E-Print Network [OSTI]

;3 SUMMARY 5 1. BACKGROUND 5 1.1 Regulation of radioactive waste discharges 5 1.2 The critical group concept' consumption rates of root vegetables in the Faslane area (kg/y) Table 12. Adults' consumption rates of potato

213

Radiological Habits Survey, Chapelcross, 2005  

E-Print Network [OSTI]

;2 #12;3 SUMMARY 6 1. BACKGROUND 6 1.1 Regulation of radioactive waste discharges 6 1.2 The critical of potato in the Chapelcross area (kg/y) Table 15. Adult consumption rates of domestic fruit. Children's consumption rates of potato in t

214

Radiological Habits Survey, Dounreay, 2003  

E-Print Network [OSTI]

;2 #12;3 SUMMARY 6 1. BACKGROUND 7 1.1 Regulation of radioactive waste discharges 7 1.2 The critical (kg/y) of potatoes in the Dounreay area Table 16. Adult consumption rates (kg/y) of domestic fruit/y) of potatoes in the Dounreay area Table 32. Children's consumption rates (k

215

Radiological Habits Survey, Hunterston 2001  

E-Print Network [OSTI]

;3 SUMMARY 6 1. BACKGROUND 7 1.1 Regulation of radioactive waste discharges 7 1.2 The critical group concept rates of root vegetables from the Hunterston area (kg/y) Table 15. Adult consumption rates of potatoes the Hunterston area (kg/y) Table 31. Children's consumption rates of potatoes from the Hunterston area (kg

216

Description of the Formerly Utilized Sites Remedial Action Program  

SciTech Connect (OSTI)

The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed.

Not Available

1980-09-01T23:59:59.000Z

217

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH07, Shiprock, New Mexico, September-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at several areas in the outside environs. A general area of elevated radioactivity was found in the frontyard and alleyway, encompassing about 2300 ft/sup 2/. Elevated levels were also found in the northwest corner of the property, encompassing about 320 ft/sup 2/, and in the southeast corner, encompassing about 39 ft/sup 2/. An area of elevated radioactivity was found at a backyard slab, constructed of decorative flagstone and encompassing about 160 ft/sup 2/. Radiochemical analyses of the soil sample collected from the southeast corner indicated a radium concentration of 41 +- 5 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of a surface soil sample collected in the alley from an adjacent vicinity property site also indicated a radium concentration in excess of those limits. Subsurface soil sampling was not conducted. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

218

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH09, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were landscaped with lawn cover and trees. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background as specified in the EPA Standard. The assessment indicated elevated levels of radioactivity at several areas in the outside environs. A general area was found along the west side of the residence, encompassing about 160 ft/sup 2/, and a discrete hot spot of localized area was found near the back porch of the residence. General areas of elevated radioactivity also were found at the west edge of the property, paralleling the roadway and encompassing about 120 ft/sup 2/, and at the alleyway, encompassing about 1300 ft/sup 2/. Radiochemical analyses of the soil sample collected from the west edge of the property indicated a radium concentration of 24 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of surface soil samples collected at the alleyway from nearby vicinity property sites also indicated radium concentrations in excess of the limits. Subsurface soil sampling was not conducted. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

219

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

SciTech Connect (OSTI)

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

J. R. Morton

2000-09-01T23:59:59.000Z

220

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH10, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at several areas in the outside environs. A general area was found along the east edge of the property, paralleling the roadway and encompassing about 24 ft/sup 2/, and two discrete hot spots or localized areas were detected in the southeast corner of the property. Additionally, general areas were found near the southwest corner of the structure, encompassing about 6.8 ft/sup 2/; to the west of the structure, encompassing about 60 ft/sup 2/; and at the west edge of the property and alleyway, encompassing about 1400 ft/sup 2/. Radiochemical analyses of the soil sample collected from this area indicated a radium concentration of 19 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background. Subsurface soil sampling was not conducted. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Gamma radiological surveys of the Oak Ridge Reservation, Paducah Gaseous Diffusion Plant, and Portsmouth Gaseous Diffusion Plant, 1990-1993, and overview of data processing and analysis by the Environmental Restoration Remote Sensing Program, Fiscal Year 1995  

SciTech Connect (OSTI)

Three gamma radiological surveys have been conducted under auspices of the ER Remote Sensing Program: (1) Oak Ridge Reservation (ORR) (1992), (2) Clinch River (1992), and (3) Portsmouth Gaseous Diffusion Plant (PORTS) (1993). In addition, the Remote Sensing Program has acquired the results of earlier surveys at Paducah Gaseous Diffusion Plant (PGDP) (1990) and PORTS (1990). These radiological surveys provide data for characterization and long-term monitoring of U.S. Department of Energy (DOE) contamination areas since many of the radioactive materials processed or handled on the ORR, PGDP, and PORTS are direct gamma radiation emitters or have gamma emitting daughter radionuclides. High resolution airborne gamma radiation surveys require a helicopter outfitted with one or two detector pods, a computer-based data acquisition system, and an accurate navigational positioning system for relating collected data to ground location. Sensors measure the ground-level gamma energy spectrum in the 38 to 3,026 KeV range. Analysis can provide gamma emission strength in counts per second for either gross or total man-made gamma emissions. Gross count gamma radiation includes natural background radiation from terrestrial sources (radionuclides present in small amounts in the earth`s soil and bedrock), from radon gas, and from cosmic rays from outer space as well as radiation from man-made radionuclides. Man-made count gamma data include only the portion of the gross count that can be directly attributed to gamma rays from man-made radionuclides. Interpretation of the gamma energy spectra can make possible the determination of which specific radioisotopes contribute to the observed man-made gamma radiation, either as direct or as indirect (i.e., daughter) gamma energy from specific radionuclides (e.g., cesium-137, cobalt-60, uranium-238).

Smyre, J.L.; Moll, B.W.; King, A.L.

1996-06-01T23:59:59.000Z

222

Verification Survey of the Building 4059 Site (Phase B); Post Historical Site Assessment Sites, Block 1; and Radioactive Materials Handling Facility HOldup Pond (Site 4614), Santa Susana Field Laboratory, The Boeing Company, Ventura County, California  

SciTech Connect (OSTI)

Confirm that the final radiological conditions were accurately and adequately described in the FSS documentation, relative to the established release criteria.

T.J. Vitkus

2008-06-06T23:59:59.000Z

223

Estimating radiological background using imaging spectroscopy  

SciTech Connect (OSTI)

Optical imaging spectroscopy is investigated as a method to estimate radiological background by spectral identification of soils, sediments, rocks, minerals and building materials derived from natural materials and assigning tabulated radiological emission values to these materials. Radiological airborne surveys are undertaken by local, state and federal agencies to identify the presence of radiological materials out of regulatory compliance. Detection performance in such surveys is determined by (among other factors) the uncertainty in the radiation background; increased knowledge of the expected radiation background will improve the ability to detect low-activity radiological materials. Radiological background due to naturally occurring radiological materials (NORM) can be estimated by reference to previous survey results, use of global 40K, 238U, and 232Th (KUT) values, reference to existing USGS radiation background maps, or by a moving average of the data as it is acquired. Each of these methods has its drawbacks: previous survey results may not include recent changes, the global average provides only a zero-order estimate, the USGS background radiation map resolutions are coarse and are accurate only to 1 km – 25 km sampling intervals depending on locale, and a moving average may essentially low pass filter the data to obscure small changes in radiation counts. Imaging spectroscopy from airborne or spaceborne platforms can offer higher resolution identification of materials and background, as well as provide imaging context information. AVIRIS hyperspectral image data is analyzed using commercial exploitation software to determine the usefulness of imaging spectroscopy to identify qualitative radiological background emissions when compared to airborne radiological survey data.

Bernacki, Bruce E.; Schweppe, John E.; Stave, Sean C.; Jordan, David V.; Kulisek, Jonathan A.; Stewart, Trevor N.; Seifert, Carolyn E.

2014-06-13T23:59:59.000Z

224

Effectiveness of Shallow Temperatures Surveys to Target a Geothermal Reservoir at Previously Explored Sites at McGee Mountain, Nevada  

Broader source: Energy.gov [DOE]

DOE Geothermal Peer Review 2010 - Presentation. Project Objectives: To evaluate the cost-effectiveness of two innovative technologies in early-stage geothermal exploration:a) shallow (2m) survey; b) hydroprobe; and Identify a geothermal resource at the project site.

225

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH17, Shiprock, New Mexico, August and November 1982  

SciTech Connect (OSTI)

The assessment activities included determination of indoor surface radiation levels in two buildings through direct instrument surveys, measurement of ambient external penetrating radiation levels at 1-meter heights, and analysis of air samples. No evidence of radioactive contamination was found inside either building; the assessment indicated no elevated levels of radioactivity that could not be attributed to the structural materials used in the construction of the buildings. The levels of radiation that were detected from these sources were considered normal for the glazed-tile and cement-block materials encountered. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard. Short-term radon daughter measurements within the buildings did not exceed the 0.02 WL limit for average annual concentrations including background as specified in the EPA Standard. The assessment did not indicate the presence of residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978. Remedial action for this vicinity site should not be considered.

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

1984-05-01T23:59:59.000Z

226

Women in pediatric radiology  

E-Print Network [OSTI]

AM et al. (2001) Pediatric radiology at the millennium.a case study of pediatric radiology. J Am Coll Radiol 6:635–WORKPLACE Women in pediatric radiology M. Ines Boechat # The

Boechat, M. Ines

2010-01-01T23:59:59.000Z

227

ELIPGRID-PC and INRADS{copyright}: Tools for reducing costs and optimizing data collection on sites contaminated with NORM  

SciTech Connect (OSTI)

Oak Ridge National Laboratory (ORNL), Environmental Technology Section (ETS), located in Grand Junction, Colorado has more than ten years experience in radiological surveying and more than twenty years as part of the ongoing Formerly Utilized Sites Remedial Action Project surveys conducted by ORNL Health Sciences Research Division. As part of our mission, ETS researchers develops and applies innovative technologies to share with private industry. The ELIPGRID-PC software and INRADS multidetector radiologic survey instrument are works in progress are discussed. ELIPGRID-PC is a tool that aids in survey design, and the INRADS system automates and increases the amount of data collected.

Egidi, P.V.

1996-12-31T23:59:59.000Z

228

CONFIRMATORY SURVEY OF THE FUEL OIL TANK AREA HUMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA  

SciTech Connect (OSTI)

During the period of February 14 to 15, 2012, ORISE performed radiological confirmatory survey activities for the former Fuel Oil Tank Area (FOTA) and additional radiological surveys of portions of the Humboldt Bay Power Plant site in Eureka, California. The radiological survey results demonstrate that residual surface soil contamination was not present significantly above background levels within the FOTA. Therefore, it is ORISE’s opinion that the radiological conditions for the FOTA surveyed by ORISE are commensurate with the site release criteria for final status surveys as specified in PG&E’s Characterization Survey Planning Worksheet. In addition, the confirmatory results indicated that the ORISE FOTA survey unit Cs-137 mean concentrations results compared favorably with the PG&E FOTA Cs-137 mean concentration results, as determined by ORISE from the PG&E characterization data. The interlaboratory comparison analyses of the three soil samples analyzed by PG&E’s onsite laboratory and the ORISE laboratory indicated good agreement for the sample results and provided confidence in the PG&E analytical procedures and final status survey soil sample data reporting.

WADE C. ADAMS

2012-04-09T23:59:59.000Z

229

Standardized radiological dose evaluations  

SciTech Connect (OSTI)

Following the end of the Cold War, the mission of Rocky Flats Environmental Technology Site changed from production of nuclear weapons to cleanup. Authorization baseis documents for the facilities, primarily the Final Safety Analysis Reports, are being replaced with new ones in which accident scenarios are sorted into coarse bins of consequence and frequency, similar to the approach of DOE-STD-3011-94. Because this binning does not require high precision, a standardized approach for radiological dose evaluations is taken for all the facilities at the site. This is done through a standard calculation ``template`` for use by all safety analysts preparing the new documents. This report describes this template and its use.

Peterson, V.L.; Stahlnecker, E.

1996-05-01T23:59:59.000Z

230

Radiological control manual. Revision 1  

SciTech Connect (OSTI)

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

Kloepping, R.

1996-05-01T23:59:59.000Z

231

Interim Letter Report - Verification Survey of Partial Grids H19, J21, J22, X20, and X21 at the David Witherspoon, Inc. 1630 Site, Knoxville Tennessee  

SciTech Connect (OSTI)

Conduct verification surveys of available grids at the David Witherspoon Incorporated 1630 Site (DWI 1630) in Knoxville, Tennessee. The IVT conducted verification activities of partial grids H19, J21, J22, X20, and X21.

P.C. Weaver

2008-03-19T23:59:59.000Z

232

Survey of ecological resources at selected US Department of Energy sites  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) owns and manages a wide range of ecological resources. During the next 30 years, DOE Headquarters and Field Offices will make land-use planning decisions and conduct environmental remediation and restoration activities in response to federal and state statutes. This document fulfills, in part, DOE`s need to know what types of ecological resources it currently owns and manages by synthesizing information on the types and locations of ecological resources at 10 DOE sites: Hanford Site, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Sandia National Laboratory, Rocky Flats Plant, Los Alamos National Laboratory, savannah River Site, Oak Ridge National Laboratory, Argonne National Laboratory, and Fernald Environmental Management Project. This report summarizes information on ecosystems, habitats, and federally listed threatened, endangered, and candidate species that could be stressed by contaminants or physical activity during the restoration process, or by the natural or anthropogenic transport of contaminants from presently contaminated areas into presently uncontaminated areas. This report also provides summary information on the ecosystems, habitats, and threatened and endangered species that exist on each of the 10 sites. Each site chapter contains a general description of the site, including information on size, location, history, geology, hydrology, and climate. Descriptions of the major vegetation and animal communities and of aquatic resources are also provided, with discussions of the treatened or endangered plant or animal species present. Site-specific ecological issues are also discussed in each site chapter. 106 refs., 11 figs., 1 tab.

McAllister, C.; Beckert, H.; Abrams, C. [and others

1996-09-01T23:59:59.000Z

233

Life-cycle framework for assessment of site remediation options: Method and generic survey  

SciTech Connect (OSTI)

To address burdens associated with contaminated sites and issuing from remediation activities, a life-cycle framework (LCF) was developed, including an approach based on life-cycle management (LCM) and an adaptation of life-cycle assessment (LCA). Intended for application to a wide range of remediation options, the objective of the LCF is to broaden consideration of potential impacts beyond the contaminated site and over a prolonged time frame. The LCM approach is a qualitative method for investigating remediation activities from a life-cycle perspective. This adaptation of the more rigorous, quantitative LCA method has involved specifying appropriate life-cycle stages, a long-term time horizon, a spatial boundary encompassing the contaminated site and other affected locations, a process boundary containing the contaminated soil, and an impact assessment method that considers site- and process-related metrics. To assess the suitability of LCM as a decision-making tool, six generic site remediation options were investigated: no action, encapsulation, excavation and disposal, vapor extraction, in situ bioremediation, and soil washing. The analysis exemplified tradeoffs between the streamlined LCM, and comprehensive, quantitative LCA approaches, and highlighted potential environmental and human health impacts arising from the six technologies investigated.

Diamond, M.L.; Page, C.A. [Univ. of Toronto, Ontario (Canada). Dept. of Geography; Campbell, M. [Toronto Public Health, North York, Ontario (Canada); McKenna, S. [City of Toronto, Ontario (Canada). Community and Neighbourhood Services; Lall, R. [R. Addison Lall and Associates, Toronto, Ontario (Canada)

1999-04-01T23:59:59.000Z

234

Final Report - Independent Verification Survey Activities at the Seperations Process Research Unit Sites, Niskayuna, New York  

SciTech Connect (OSTI)

The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

Evan Harpenau

2011-03-15T23:59:59.000Z

235

I COMPRE}IENSIVE RADIOLOGICAI SURVEY OFF-SITE PROPERTY N,-NORTS  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North - t ' v I tfi t7Bechtelim

236

Final Report-Confirmatory Survey Results for the ABB Combustion Engineering Site, Windsor, Connecticut; Revision 1 (DCN 5158-SR-02-1) (Docket No. 030-03754; RFTA No. 12-003)  

SciTech Connect (OSTI)

The objectives of the confirmatory activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the contractor?s procedures and FSS results. ORAU reviewed ABB CE?s decommissioning plan, final status survey plan, and the applicable soil DCGLs, which were developed based on an NRC-approved radiation dose assessment. The surveys included gamma surface scans, gamma direct measurements, and soil sampling.

ADAMS, WADE C

2013-01-28T23:59:59.000Z

237

Evaluation of critical pathways, radionuclides, and remedial measures for reducing the radiological dose to returning populations at a former nuclear test site  

SciTech Connect (OSTI)

Bikini Island, the major residence island at Bikini Atoll, was contaminated with radioactive fallout as a result of the BRAVO test conducted on March 1, 1954. We have identified the critical radionuclides and supplied radiological data needed to develop dose estimates for all possible exposure pathways. These estimates show that the major dose to returning populations would result from ingestion of cesium-137 (137 Cs) in locally grown terrestrial foods where the predicted population average effective dose exceeds current federal guidelines. Consequently, we designed several long-term field experiments to develop and evaluate methods to reduce the 137 Cs content in locally grown foods.This paper gives a general outline of the remediation experiments with a more detailed description of a preferred combined option. Our comparative evaluation on various remedial methods show that the combined option--potassium treatment of the entire islands with limited excavation of soil in village an d housing areas--will be effective in reducing the dose to about 10% of pretreatment levels, and offers very significant benefits with respect to adverse environmental impacts as well as savings in overall costs, time, and required expert resources.

Robison, W. L., LLNL

1997-11-01T23:59:59.000Z

238

Radiological Survey of Contaminated Installations of Research Reactor before Dismantling in High Dose Conditions with Complex for Remote Measurements of Radioactivity - 12069  

SciTech Connect (OSTI)

Decontamination and decommissioning of the research reactors MR (Testing Reactor) and RFT (Reactor of Physics and Technology) has recently been initiated in the National Research Center (NRC) 'Kurchatov institute', Moscow. These research reactors have a long history and many installations - nine loop facilities for experiments with different kinds of fuel. When decommissioning nuclear facilities it is necessary to measure the distribution of radioactive contamination in the rooms and at the equipment at high levels of background radiation. At 'Kurchatov Institute' some special remote control measuring systems were developed and they are applied during dismantling of the reactors MR and RFT. For a survey of high-level objects a radiometric system mounted on the robotic Brokk vehicle is used. This system has two (4? and collimated) dose meters and a high resolution video camera. Maximum measured dose rate for this system is ?8.5 Sv/h. To determine the composition of contaminants, a portable spectrometric system is used. It is a remotely controlled, collimated detector for scanning the distribution of radioactive contamination. To obtain a detailed distribution of contamination a remote-controlled gamma camera is applied. For work at highly contaminated premises with non-uniform background radiation, another camera is equipped with rotating coded mask (coded aperture imaging). As a result, a new system of instruments for remote radioactivity measurements with wide range of sensitivity and angular resolution was developed. The experience and results of measurements in different areas of the reactor and at its loop installations, with emphasis on the radioactive survey of highly-contaminated samples, are presented. These activities are conducted under the Federal Program for Nuclear and Radiation Safety of Russia. Adaptation of complex remote measurements of radioactivity and survey of contaminated installations of research reactor before dismantling in high dose conditions has proven successful. The radioactivity measuring devices for operation at high, non-uniform dose background were tested in the field and a new data of measurement of contamination distribution in the premises and installations were obtained. (authors)

Danilovich, Alexey; Ivanov, Oleg; Lemus, Alexey; Smirnov, Sergey; Stepanov, Vyacheslav; Volkovich, Anatoly [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)

2012-07-01T23:59:59.000Z

239

Survey of Potential Hanford Site Contaminants in the Upper Sediment for the Reservoirs at McNary, John Day, The Dalles, and Bonneville Dams, 2003  

SciTech Connect (OSTI)

This report presents the results from a multi-agency cooperative environmental surveillance study. of the study looked at sediment from the pools upstream from dams on the Columbia River that are downstream from Hanford Site operations. The radiological and chemical conditions existing in the upper-level sediment found in the pools upstream from McNary Dam, John Day Dam, The Dalles Lock and Dam, and Bonneville Dam were evaluated. This study also evaluated beach sediment where available. Water samples were collected at McNary Dam to further evaluate potential Hanford contaminants in the lower Columbia River. Samples were analyzed for radionuclides, chemicals, and physical parameters. Results from this study were compared to background values from sediment and water samples collect from the pool upstream of Priest Rapids Dam (upstream of the Hanford Site) by the Hanford Site Surface Environmental Surveillance Project.

Patton, Gregory W.; Priddy, M; Yokel, Jerel W.; Delistraty, Damon A.; Stoops, Thomas M.

2005-02-01T23:59:59.000Z

240

Siting landfills and incinerators in areas of historic unpopularity: Surveying the views of the next generation  

SciTech Connect (OSTI)

Highlights: • Opinions and knowledge of young people in Italy about waste were studied. • Historic opposition to construction of waste facilities is difficult to overcome. • Awareness of waste management develops with knowledge of environmental issues. • Many stakeholders’ views are needed when siting a new waste management facility. • Respondents’ opinions were influenced by their level of environmental knowledge. - Abstract: The Campania Region in Southern Italy has suffered many problems with municipal solid waste management since the mid-1990s, leading to significant public disturbances and subsequent media coverage. This paper reports on the current views and knowledge of young people (university students) in this region about waste management operations and facilities, specifically the siting of landfills and incinerators. By means of a structured questionnaire, opinion and knowledge were systematically examined by degree type and course year. The study took place in 2011 at the University of Salerno campus. A sample of 900 students, comprising 100 students for each of the nine considered faculties, and 20 students for every academic course year, was randomly selected. Only about a quarter of respondents were not opposed to the siting of a landfill or an incinerator in their city. This clearly highlights that historic opposition to the construction of waste facilities is difficult to overcome and that distrust for previous poor management or indiscretions is long-lived and transcends generations. Students from technical faculties expressed the most reasonable opinion; opinion and knowledge were statistically related (Chi-square test, p < 0.05) to the attended faculty, and the knowledge grew linearly with progression through the university. This suggests that awareness of waste management practices develops with experience and understanding of environmental issues. There is general acceptance that many stakeholders – technicians, politicians and citizens – all have to be part of the decision process when siting a new waste management facility. The opinions of the young respondents were significantly influenced by their level of environmental knowledge.

De Feo, Giovanni, E-mail: g.defeo@unisa.it [Department of Industrial Engineering, University of Salerno, Via Giovanni Paolo II 132, 84084 Fisciano (Italy); Williams, Ian D. [Waste Management Research Group, Faculty of Engineering and the Environment, University of Southampton, Highfield, Southampton SO17 1BJ (United Kingdom)

2013-12-15T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Survey of Potential Geothermal Exploration Sites at Newberry Volcano Deschutes County, Oregon.  

SciTech Connect (OSTI)

The study summarizes the current data, generates some new data, and recommends further steps which should be taken to investigate the electrical power production potential of Newberry volcano. The objective was to concentrate on data from the developable flanks of the volcano. All previous data on the geology, hydrology, and geophysics were summarized. A soil-mercury survey focused on the flanks of the volcano was conducted. Samples from 1000 km/sup 2/ of the volcano were analyzed for mercury content. All this information was utilized to evaluate (1) the likelihood of future discovery of electrical-quality geothermal fluids on the flanks, and (2) the most cost-effective means of improving the quality of available power generation estimates for the volcano. 37 figures.

Priest, George R.; Vogt, Beverly F.; Black, Gerald L.

1983-01-01T23:59:59.000Z

242

Radiological Assistance Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish Department of Energy (DOE) policy, procedures, authorities, and responsibilities for its Radiological Assistance Program. Canceled by DOE O 153.1.

1992-04-10T23:59:59.000Z

243

Results of a baseflow tritium survey of surface water in Georgia across from the Savannah River Site  

SciTech Connect (OSTI)

In October 1991 the Georgia Department of Natural Resources (GDNR) issued a press release notifying the public that tritium had been measured in elevated levels (1,200 - 1,500 pCi/1) in water samples collected from drinking water wells in Georgia across from the Savannah River Site in Aiken Co. South Carolina. None of the elevated results were above the Primary Drinking Water Standard for tritium of 20,000 pCi/l. The GDNR initiated 2 surveys to determine the source and extent of elevated tritium: (1) baseflow survey of surface water quality, and (2) well evaluation program. Results from the 2 surveys indicate that the tritium measured in groundwater wells in Georgia is not the result of a groundwater flow from South Carolina under the Savannah River and into Georgia. Atmospheric transport and consequent rainout and infiltration has resulted in an increase of tritium in the water-table aquifer in the vicinity. Water samples collected from drinking water wells believed to have been installed in the aquifer beneath the water-table aquifer were actually from the shallower water-table aquifer. Water samples collected from the wells contain the amount of tritium expected for the water-table aquifer in the sample area. The measured tritium levels in the well samples and baseflow samples do not exceed Primary Drinking Water Standards. Tritium levels in the water-table in Georgia will decline as the atmospheric releases from SRS decline, tritium undergoes natural decay, and infiltration water with less tritium flushes through the subsurface.

Nichols, R.L.

1993-03-03T23:59:59.000Z

244

Environmental control technology survey of selected US strip mining sites. Volume 2B. Alabama. Water quality impacts and overburden chemistry of Alabama study site  

SciTech Connect (OSTI)

As part of a program to examine the ability of existing control technologies to meet federal guidelines for the quality of aqueous effluents from coal mines, an intensive study of water, coal, and overburden chemistry was conducted at a surface coal mine in Alabama from May 1976 through July 1977. Sampling sites included the pit sump, a stream downgrade from the mine, the discharge from the water treatment facility, and a small stream outside the mine drainage. Water samples were collected every two weeks by Argonne subcontractors at the Alabama Geological Survey and analysed for the following parameters: specific conductance, pH, temperature, acidity, bicarbonate, carbonate, chloride, total dissolved solids, suspended solids, sulfate, and 20 metals. Analysis of the coal and overburden shows that no potential acid problem exists at this mine. Water quality is good in both streams sampled, and high levels of dissolved elements are found only in water collected from the pit sump. The mine effluent is in compliance with Office of Surface Mining water quality standards.

Henricks, J D; Bogner, J E; Olsen, R D; Schubert, J P; Sobek, A A; Johnson, D O

1980-05-01T23:59:59.000Z

245

Ground penetrating radar surveys over an alluvial DNAPL site, Paducah Gaseous Diffusion Plant, Kentucky  

SciTech Connect (OSTI)

Ground penetrating radar (GPR) surveys were used to map shallow sands and gravels which are DNAPL migration pathways at the Paducah Gaseous Diffusion Plant in western Kentucky. The sands and gravels occur as paleochannel deposits, at depths of 17-25 ft, embedded in Pleistocene lacustrine clays. More than 30 GPR profiles were completed over the Drop Test Area (DTA) to map the top and base of the paleochannel deposits, and to assess their lateral continuity. A bistatic radar system was used with antenna frequencies of 25 and 50 MHz. An average velocity of 0.25 ft/ns for silty and clayey materials above the paleochannel deposits was established from radar walkaway tests, profiles over culverts of known depth, and comparison of radar sections with borings. In the south portion of the DTA, strong reflections corresponded to the water table at approximately 9-10 ft, the top of the paleochannel deposits at approximately 18 ft, and to gravel horizons within these deposits. The base of these deposits was not visible on the radar sections. Depth estimates for the top of the paleochannel deposits (from 50 records) were accurate to within 2 ft across the southern portion of the DTA. Continuity of these sands and gravels could not be assessed due to interference from air-wave reflections and lateral changes in signal penetration depth. However, the sands and gravels appear to extend across the entire southern portion of the DTA, at depths as shallow as 17 ft. Ringing, air-wave reflections and diffractions from powerlines, vehicles, well casings, and metal equipment severly degraded GPR profiles in the northern portion of the DTA; depths computed from reflection times (where visible) were accurate to within 4 ft in this area. The paleochannel deposits are deeper to the north and northeast where DNAPL has apparently pooled (DNAPL was not directly imaged by the GPR, however). Existing hydrogeological models of the DTA will be revised.

Carpenter, P.J. [Northern Illinois Univ., DeKalb, IL (United States). Dept. of Geology]|[Oak Ridge National Lab., TN (United States); Doll, W.E. [Oak Ridge National Lab., TN (United States); Phillips, B.E. [Paducah Gaseous Diffusion Plant, KY (United States)

1994-09-01T23:59:59.000Z

246

Results of radiological measurements taken in the Niagara Falls, New York, area (NF002)  

SciTech Connect (OSTI)

The results of a radiological survey of 100 elevated gamma radiation anomalies in the Niagara Falls, New York, area are presented. These radiation anomalies were identified by a mobile gamma scanning survey during the period October 3-16, 1984, and were recommended for an onsite survey to determine if the elevated levels of radiation may be related to the transportation of radioactive waste material to the Lake Ontario Ordnance Works for storage. In this survey, radiological measurements included outdoor gamma exposure rates at 1 m above the surface; outdoor gamma exposure rates at the surface, range of gamma exposure rates during scan; and uranium, radium, and thorium concentrations in biased surface soil samples. The results show 38 anomalies (35 located along Pletcher Road and 3 associated with other unreleated locations) were found to exceed Formerly Utilized Sites Remedial Action Program (FUSRAP) remedial action guidelines and were recommended for formal characterization surveys. (Since the time of this survey, remedial actions have been conducted on the 38 anomalies identified as exceeding FUSRAP guidelines, and the radioactive material above guidelines has been removed.) The remaining 62 anomalies are associated with asphalt driveways and parking lots, which used a phosphate slag material (previously identified as cyclowollastonite, synthetic CaSiO/sub 3/). This rocky-slag waste material was used for bedding under asphalt surfaces and in general gravel applications. Most of the contaminated soil and rock samples collected at the latter anomalies had approximately equal concentrations of /sup 226/Ra and /sup 238/U and, therefore, are not related to materials connected with the Niagara Falls Storage Site (NFSS), including material that was transported to the NFSS. 13 refs., 7 figs., 14 tabs.

Williams, J.K.; Berven, B.A.

1986-11-01T23:59:59.000Z

247

Interim Letter Report - Verification Survey of Partial Grid E9, David Witherspoon, Inc. 1630 Site Knoxville, Tennessee  

SciTech Connect (OSTI)

Conduct verification surveys of available grids at the DWI 1630 in Knoxville, Tennessee. A representative with the Independent Environmental Assessment and Verification (IEAV) team from ORISE conducted a verification survey of a partial area within Grid E9.

P.C. Weaver

2008-06-12T23:59:59.000Z

248

Radiological Habits Survey, Rosyth Business Park, 2005  

E-Print Network [OSTI]

;2 #12;3 SUMMARY 5 1. BACKGROUND 5 1.1 Regulation of radioactive waste discharges 5 1.2 The critical area (kg/y) Table 15. Adults' consumption rates of potato in the Rosyth area (kg/y) Table 16. Adults rates of root vegetables in the Rosyth area (kg/y) Table 29. Children's consumption rates of potato

249

DOE standard: Radiological control  

SciTech Connect (OSTI)

The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs. DOE has established regulatory requirements for occupational radiation protection in Title 10 of the Code of Federal Regulations, Part 835 (10 CFR 835), ``Occupational Radiation Protection``. Failure to comply with these requirements may lead to appropriate enforcement actions as authorized under the Price Anderson Act Amendments (PAAA). While this Standard does not establish requirements, it does restate, paraphrase, or cite many (but not all) of the requirements of 10 CFR 835 and related documents (e.g., occupational safety and health, hazardous materials transportation, and environmental protection standards). Because of the wide range of activities undertaken by DOE and the varying requirements affecting these activities, DOE does not believe that it would be practical or useful to identify and reproduce the entire range of health and safety requirements in this Standard and therefore has not done so. In all cases, DOE cautions the user to review any underlying regulatory and contractual requirements and the primary guidance documents in their original context to ensure that the site program is adequate to ensure continuing compliance with the applicable requirements. To assist its operating entities in achieving and maintaining compliance with the requirements of 10 CFR 835, DOE has established its primary regulatory guidance in the DOE G 441.1 series of Guides. This Standard supplements the DOE G 441.1 series of Guides and serves as a secondary source of guidance for achieving compliance with 10 CFR 835.

Not Available

1999-07-01T23:59:59.000Z

250

Background report for the formerly utilized Manhattan Engineer District/Atomic Energy Commission sites program  

SciTech Connect (OSTI)

The Department of Energy is conducting a program to determine radiological conditions at sites formerly used by the Army Corps of Engineers' Manhattan Engineer District and the Atomic Energy Commission in the early years of nuclear energy development. Also included in the program are sites used in the Los Alamos plutonium development program and the Trinity atomic bomb test site. Materials, equipment, buildings, and land became contaminated, primarily with naturally occurring radioactive nuclides. They were later decontaminated in accordance with the standards and survey methods in use at that time. Since then, however, radiological criteria, and proposed guidelines for release of such sites for unrestricted use have become more stringent as research on the effects of low-level radiation has progressed. In addition, records documenting some of these decontamination efforts cannot be found, and the final radiological conditions of the sites could not be adequately determined from the records. As a result, the Formerly Utilized Sites Program was initiated in 1974 to identify these formerly used sites and to reevaluate their radiological status. This report covers efforts through June 1980 to determine the radiological status of sites for which the existing conditions could not be clearly defined. Principal contractor facilities and associated properties have already been identified and activities are continuing to identify additional sites. Any new sites located will probably be subcontractor facilities and areas used for disposal of contractor waste or equipment; however, only limited information regarding this equipment and material has been collected to date. As additional information becomes available, supplemental reports will be published.

None

1980-09-01T23:59:59.000Z

251

Radiological standards and calibration laboratory capabilities  

SciTech Connect (OSTI)

The Radiological Standards and Calibrations Laboratory, a part of Pacific Northwest Laboratory (PNL), performs calibrations and upholds reference standards necessary to maintain traceability to national radiological standards. The facility supports U.S. Department of Energy (DOE) programs at the Hanford Site, programs sponsored by DOE Headquarters and other federal agencies, radiological protection programs at other DOE sites, and research programs sponsored through the commercial sector. The laboratory is located in the 318 Building of the Hanford Site`s 300 Area. The facility contains five major exposure rooms and several laboratories used for exposure work preparation, low-activity instrument calibrations, instrument performance evaluations, instrument maintenance, instrument design and fabrication work, and thermoluminescent and radiochromic dosimetry. The major exposure facilities are a low-scatter room used for neutron and photon exposures, a source well room used for high-volume instrument calibration work, an x-ray facility used for energy response studies, a high-exposure facility used for high-rate photon calibration work, and a beta standards laboratory used for beta energy response studies and beta reference calibrations. Calibrations are routinely performed for personnel dosimeters, health physics instrumentations, photon transfer standards and alpha, beta and gamma field sources used throughout the Hanford Site. This report describes the standards and calibrations laboratory. Photographs that accompany the text appear in the Appendix and are designated Figure A.1 through A.29.

Goles, R.W.

1995-01-01T23:59:59.000Z

252

Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York  

SciTech Connect (OSTI)

On May 9, 2011, ORISE conducted verification survey activities including scans, sampling, and the collection of smears of the remaining soils and off-gas pipe associated with the 802 Fan House within the HFBR (High Flux Beam Reactor) Complex at BNL. ORISE is of the opinion, based on independent scan and sample results obtained during verification activities at the HFBR 802 Fan House, that the FSS (final status survey) unit meets the applicable site cleanup objectives established for as left radiological conditions.

Harpeneau, Evan M. [Oak Ridge Institute for Science and Education, Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program

2011-06-24T23:59:59.000Z

253

NEVADA TEST SITE RADIOLOGICAL CONTROL MANUAL  

Office of Scientific and Technical Information (OSTI)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinan antagonist Journal Article: CrystalFG36-08GO18149 Revision: - Date: 06/15/10 ABENGOA

254

Radiological worker training  

SciTech Connect (OSTI)

This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance.

NONE

1998-10-01T23:59:59.000Z

255

2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

mike lewis

2011-02-01T23:59:59.000Z

256

2013 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

Mike Lewis

2014-02-01T23:59:59.000Z

257

2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

Mike Lewis

2013-02-01T23:59:59.000Z

258

324 Building Baseline Radiological Characterization  

SciTech Connect (OSTI)

This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building.

R.J. Reeder, J.C. Cooper

2010-06-24T23:59:59.000Z

259

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

SciTech Connect (OSTI)

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

DIEDIKER, L.P.

1999-07-29T23:59:59.000Z

260

NV/YMP RADIOLOGICAL CONTROL MANUAL  

SciTech Connect (OSTI)

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

2004-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

ORISE: Radiological program assessment services  

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

Environmental monitoring programs Operational environments Decontamination and decommissioning projects Compliance assessments Radiological release programs ORISE is actively...

262

INDEPENDENT CONFIRMATORY SURVEY OF THE NUCLEAR RESEARCH LABORATORY AT THE UNIVERSITY OF ILLINOIS URBANA-CHAMPAIGN, ILLINOIS  

SciTech Connect (OSTI)

ORAU conducted confirmatory survey activities within the NRL at the University during the week of May 7, 2012. The survey activities included visual inspections/ assessments, surface activity measurements, and volumetric concrete sampling activities. During the course of the confirmatory activities, ORAU noted several issues with the survey-for-release activities performed at the University. Issues included inconsistencies with: survey unit classifications were not designated according to Multi-Agency Radiation Survey and Site Investigation Manual guidance; survey instrument calibrations were not representative of the radionuclides of concern; calculations for instrumentation detection capabilities did not align with the release criteria discussed in the licensee’s survey guidance documents; total surface activity measurements were in excess of the release criteria; and Co-60 and Eu-152 concentrations in the confirmatory concrete samples were above their respective guidelines. Based on the significant programmatic issues identified, ORAU cannot independently conclude that the NRL satisfied the requirements and limits for release of materials without radiological restrictions.

EVAN M. HARPENAU

2012-06-28T23:59:59.000Z

263

Radiology of thoracic diseases  

SciTech Connect (OSTI)

This book presents the essential clinical and radiologic findings of a wide variety of thoracic diseases. The authors include conventional, CT and MR images of each disease discussed. In addition, they present practical differential diagnostic considerations for most of the radiographic findings or patterns portrayed.

Swensen, S.J.; Pugatch, R.D.

1989-01-01T23:59:59.000Z

264

CONFIRMATORY SURVEY RESULTS FOR PORTIONS OF THE ABB COMBUSTION ENGINEERING SITE IN WINDSOR, CONNECTICUT DURING THE FALL OF 2011  

SciTech Connect (OSTI)

From the mid-1950s until mid-2000, the Combustion Engineering, Inc. (CE) site in Windsor, Connecticut (Figure A-1) was involved in the research, development, engineering, production, and servicing of nuclear fuels, systems, and services. The site is currently undergoing decommissioning that will lead to license termination and unrestricted release in accordance with the requirements of the License Termination Rule in 10 CFR Part 20, Subpart E. Asea Brown Boveri Incorporated (ABB) has been decommissioning the CE site since 2001.

Wade C. Adams

2011-12-09T23:59:59.000Z

265

Closure Report for Corrective Action Unit 547: Miscellaneous Contaminated Waste Sites, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 547 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 547 consists of the following three Corrective Action Sites (CASs), located in Areas 2, 3, and 9 of the Nevada National Security Site: (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; AND (3) CAS 09-99-06, Gas Sampling Assembly Closure activities began in August 2011 and were completed in June 2012. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for CAU 547 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The recommended corrective action for the three CASs in CAU 547 was closure in place with administrative controls. The following closure activities were performed: (1) Open holes were filled with concrete; (2) Steel casings were placed over vertical expansion joints and filled with cement; (3) Engineered soil covers were constructed over piping and exposed sections of the gas sampling system components; (4) Fencing, monuments, Jersey barriers, radiological postings, and use restriction (UR) warning signs were installed around the perimeters of the sites; (5) Housekeeping debris was picked up from around the sites and disposed; and (6) Radiological surveys were performed to confirm final radiological postings. UR documentation is included in Appendix D. The post-closure plan was presented in detail in the CADD/CAP for CAU 547 and is included as Appendix F of this report. The requirements are summarized in Section 5.2 of this report. The proposed post-closure requirements consist of visual inspections to determine the condition of postings and radiological surveys to verify contamination has not migrated. NNSA/NSO requests the following: (1) A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 547; and (2) The transfer of CAU 547 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO.

NSTec Environmental Restoration

2012-07-17T23:59:59.000Z

266

Nuclear & Radiological Activity Center (NRAC)  

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

Nuclear & Radiological Activity Center (NRAC) Where nuclear research and deployment capabilities come together to solve nuclear nonproliferation challenges. Skip Navigation Links...

267

Smart Radiological Dosimeter  

DOE Patents [OSTI]

A radiation dosimeter providing an indication of the dose of radiation to which the radiation sensor has been exposed. The dosimeter contains features enabling the monitoring and evaluating of radiological risks so that a user can concentrate on the task at hand. The dosimeter provides an audible alarm indication that a predetermined time period has elapsed, an audible alarm indication reminding the user to check the dosimeter indication periodically, an audible alarm indicating that a predetermined accumulated dose has been prematurely reached, and an audible alarm indication prior or to reaching the 3/4 scale point.

Kosslow, William J.; Bandzuch, Gregory S.

2004-07-20T23:59:59.000Z

268

Radiological Control Technician Training  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More Documents &DOE.F 1325.8 (08-93) Radiological

269

National survey of crystalline rocks and recommendations of regions to be explored for high-level radioactive waste repository sites  

SciTech Connect (OSTI)

A reconnaissance of the geological literature on large regions of exposed crystalline rocks in the United States provides the basis for evaluating if any of those regions warrant further exploration toward identifying potential sites for development of a high-level radioactive waste repository. The reconnaissance does not serve as a detailed evaluation of regions or of any smaller subunits within the regions. Site performance criteria were selected and applied insofar as a national data base exists, and guidelines were adopted that relate the data to those criteria. The criteria include consideration of size, vertical movements, faulting, earthquakes, seismically induced ground motion, Quaternary volcanic rocks, mineral deposits, high-temperature convective ground-water systems, hydraulic gradients, and erosion. Brief summaries of each major region of exposed crystalline rock, and national maps of relevant data provided the means for applying the guidelines and for recommending regions for further study. It is concluded that there is a reasonable likelihood that geologically suitable repository sites exist in each of the major regions of crystalline rocks. The recommendation is made that further studies first be conducted of the Lake Superior, Northern Appalachian and Adirondack, and the Southern Appalachian Regions. It is believed that those regions could be explored more effectively and suitable sites probably could be found, characterized, verified, and licensed more readily there than in the other regions.

Smedes, H.W.

1983-04-01T23:59:59.000Z

270

Idaho National Engineering Laboratory Radiological Environmental Surveillance Program 1995 annual report  

SciTech Connect (OSTI)

This report describes calendar year 1995 environmental surveillance activities of Environmental Monitoring and Water Resources of Lockheed Martin Idaho Technologies Company, performed at the following Waste Management Facilities: the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and tow surplus facilities. Results of the sampling performed by the Radiological Environmental Surveillance Program, Site Environmental Surveillance Program, and the United States Geological Survey at these facilities are included in this report. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standards and to ensure protection of human health and the environment. This report compares 1995 environmental surveillance data with US DOE Derived Concentration Guides and with data form previous years.

Miles, M.; Wilhelmsen, R.N.; Borsella, B.W.; Wright, K.C.

1996-08-01T23:59:59.000Z

271

Operation Cornerstone onsite radiological safety report for announced nuclear tests, October 1988--September 1989  

SciTech Connect (OSTI)

Cornerstone was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site (NTS) from October 1, 1988, through September 30, 1989. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Radiation Protection Technicians (RPT) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage were provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined.

Not Available

1990-08-01T23:59:59.000Z

272

Supplementary radiological and beryllium characterization of the facility at 425 Peek Street, Schenectady, New York  

SciTech Connect (OSTI)

At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a radiological survey of the Peek Street industrial facility, the adjacent state-owned bike path, and two nearby residential properties was conducted by Oak Ridge National Laboratory (ORNL) in November 1989. The results indicated small isolated areas that exceeded DOE guidelines. These areas totaled approximately 0.2 m{sup 2} of floor area and approximately 3 m{sup 2} of wall area inside the building, and two small areas totaling approximately 5 m{sup 2} outside the building. A small section of one of these areas extended beyond the fence on the east side of the industrial property onto the state-owned property. No residual radioactive material or elevated radiation levels were detected on any portion of the paved section of the bike path or the residential properties adjacent to the site. Because the elevated radiation levels were localized and limited in extent, any credible use scenario, including current use conditions, indicated that no significant radiation exposures would accrue to individuals frequenting the area. Samples were also analyzed for elemental beryllium since that material had formerly been used at the site. In conjunction with the planned remediation at the facility, a supplementary characterization survey was performed to further define the areas containing beryllium in excess of the identified guidelines. Additional radiological characterization of Ra-226, Th-232, and U-238 was also performed in areas that were largely inaccessible prior to the remediation efforts.

Foley, R.D.; Allred, J.F.; Carrier, R.F.

1994-10-01T23:59:59.000Z

273

Radiological Work Planning and Procedures  

E-Print Network [OSTI]

Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In add...

Kurtz, J E

2000-01-01T23:59:59.000Z

274

Radiological Release Accident Investigation Report - Phase 1...  

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

Radiological Release Accident Investigation Report - Phase 1 Radiation Report Radiological Release Accident Investigation Report - Phase 1 Radiation Report Phase 1 of this accident...

275

Independent Verification Final Summary Report for the David Witherspoon, Inc. 1630 Site Knoxville, Tennessee  

SciTech Connect (OSTI)

The primary objective of the independent verification was to determine if BJC performed the appropriate actions to meet the specified “hot spot” cleanup criteria of 500 picocuries per gram (pCi/g) uranium-238 (U-238) in surface soil. Specific tasks performed by the independent verification team (IVT) to satisfy this objective included: 1) performing radiological walkover surveys, and 2) collecting soil samples for independent analyses. The independent verification (IV) efforts were designed to evaluate radioactive contaminants (specifically U-238) in the exposed surfaces below one foot of the original site grade, given that the top one foot layer of soil on the site was removed in its entirety.

P.C. Weaver

2009-04-29T23:59:59.000Z

276

Radiological Electron Microprobe | EMSL  

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

from the Hanford Site provide complementary data to ongoing activities in EMSL's microfluidics and Subsurface Flow and Transport capabilities. User Portal Name: Electron...

277

Radiological characterization of main cooling reservoir bottom sediments at The South Texas Project Electrical Generating Station  

E-Print Network [OSTI]

The South Texas Project Electrical Generating Station (STPEGS operating license directs that an effective radiological environmental monitoring program be established. Site- specific data should then augment the generation of an accurate dose model...

Blankinship, David Randle

1993-01-01T23:59:59.000Z

278

LETTER REPORT. INDEPENDENT CONFIRMATORY SURVEY RESULTS OF SOILS ASSOCIATED WITH THE ARGYLE STREET SEWER LINE AT THE UNITED NUCLEAR CORPORATION NAVAL PRODUCTS SITE, NEW HAVEN, CONNECTICUT  

SciTech Connect (OSTI)

Oak Ridge Institute for Science and Education (ORISE) personnel visited the United Nuclear Corporation (UNC) Naval Products site on three separate occasions during the months of October and November 2011. The purpose of these visits was to conduct confirmatory surveys of soils associated with the Argyle Street sewer line that was being removed. Soil samples were collected from six different, judgmentally determined locations in the Argyle Street sewer trench. In addition to the six soil samples collected by ORISE, four replicate soil samples were collected by Cabrera Services, Inc. (CSI) for analysis by the ORISE laboratory. Replicate samples S0010 and S0011 were final status survey (FSS) bias samples; S0012 was an FSS systematic sample; and S0015 was a waste characterization sample. Six soil samples were also collected for background determination. Uranium-235 and uranium-238 concentrations were determined via gamma spectroscopy; the spectra were also reviewed for other identifiable photopeaks. Radionuclide concentrations for these soil samples are provided. In addition to the replicate samples and the samples collected by ORISE, CSI submitted three soil samples for inter-laboratory comparison analyses. One sample was from the background reference area, one was from waste characterization efforts (material inside the sewer line), and one was a FSS sample. The inter-laboratory comparison analyses results between ORISE and CSI were in agreement, except for one sample collected in the reference area. Smear results For Argyle Street sewer pipes are tabulated.

Adams, Wade C.

2012-01-24T23:59:59.000Z

279

LITERATURE SURVEY FOR GROUNDWATER TREATMENT OPTIONS FOR NITRATE IODINE-129 AND URANIUM 200-ZP-1 OPERABLE UNIT HANFORD SITE  

SciTech Connect (OSTI)

This literature review presents treatment options for nitrate, iodine-129, and uranium, which are present in groundwater at the 200-ZP-I Groundwater Operable Unit (OU) within the 200 West Area of the Hanford Site. The objective of this review is to determine available methods to treat or sequester these contaminants in place (i.e., in situ) or to pump-and-treat the groundwater aboveground (i.e., ex situ). This review has been conducted with emphasis on commercially available or field-tested technologies, but theoretical studies have, in some cases, been considered when no published field data exist. The initial scope of this literature review included only nitrate and iodine-I 29, but it was later expanded to include uranium. The focus of the literature review was weighted toward researching methods for treatment of nitrate and iodine-129 over uranium because of the relatively greater impact of those compounds identified at the 200-ZP-I OU.

BYRNES ME

2008-06-05T23:59:59.000Z

280

Stanford Radiology LPCH Fast Pediatric MRI  

E-Print Network [OSTI]

Stanford Radiology LPCH Fast Pediatric MRI Shreyas Vasanawala, MD/PhD Stanford University Lucile Radiology LPCH Thank you Par Lab Briefer, lighter, safer anesthesia for pediatric MRI #12; practice #12;Stanford Radiology LPCH #12;Stanford Radiology LPCH Current Solution INVASIVE LIMITS ACCESS

California at Berkeley, University of

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Verification survey report of the south waste tank farm training/test tower and hazardous waste storage lockers at the West Valley demonstration project, West Valley, New York  

SciTech Connect (OSTI)

A team from ORAU's Independent Environmental Assessment and Verification Program performed verification survey activities on the South Test Tower and four Hazardous Waste Storage Lockers. Scan data collected by ORAU determined that both the alpha and alpha-plus-beta activity was representative of radiological background conditions. The count rate distribution showed no outliers that would be indicative of alpha or alpha-plus-beta count rates in excess of background. It is the opinion of ORAU that independent verification data collected support the site?s conclusions that the South Tower and Lockers sufficiently meet the site criteria for release to recycle and reuse.

Weaver, Phyllis C.

2012-08-29T23:59:59.000Z

282

Radiation Shielding and Radiological Protection  

E-Print Network [OSTI]

Radiation Shielding and Radiological Protection J. Kenneth Shultis Richard E. Faw Department@triad.rr.com Radiation Fields and Sources ................................................ . Radiation Field Variables........................................................... .. Direction and Solid Angle Conventions ......................................... .. Radiation Fluence

Shultis, J. Kenneth

283

Radiological Emergency Response Plan (Vermont)  

Broader source: Energy.gov [DOE]

This legislation establishes a radiological emergency response plan fund, into which any entity operating a nuclear reactor or storing nuclear fuel and radioactive waste in this state (referred to...

284

Radiological Protection for DOE Activities  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes radiological protection program requirements that, combined with 10 CFR 835 and its associated implementation guidance, form the basis for a comprehensive program for protection of individuals from the hazards of ionizing radiation in controlled areas. Extended by DOE N 441.3. Cancels DOE 5480.11, DOE 5480.15, DOE N 5400.13, DOE N 5480.11; please note: the DOE radiological control manual (DOE/EH-0256T)

1995-09-29T23:59:59.000Z

285

Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action alternatives.

Wickline, Alfred

2005-12-01T23:59:59.000Z

286

Radiological assessment. A textbook on environmental dose analysis  

SciTech Connect (OSTI)

Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

Till, J.E.; Meyer, H.R. (eds.)

1983-09-01T23:59:59.000Z

287

Recent Developments in Field Response for Mitigation of Radiological...  

Energy Savers [EERE]

of technologies and methods to detect, prepare, or manage radiological incidents or accidents . With any radiological accident, radiological dispersal device (RDD), or improvised...

288

Environmental Survey preliminary report  

SciTech Connect (OSTI)

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Sandia National Laboratories conducted August 17 through September 4, 1987. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with Sandia National Laboratories-Albuquerque (SNLA). The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at SNLA, and interviews with site personnel. 85 refs., 49 figs., 48 tabs.

Not Available

1988-04-01T23:59:59.000Z

289

Radiological Work Planning and Procedure  

SciTech Connect (OSTI)

Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD.

KURTZ, J.E.

2000-01-01T23:59:59.000Z

290

Interim Letter Report - Verification Survey Results for Activities Performed in March 2009 for the Vitrification Test Facility Warehouse at the West Valley Demonstration Project, Ashford, New York  

SciTech Connect (OSTI)

The objective of the verification activities was to provide independent radiological surveys and data for use by the Department of Energy (DOE) to ensure that the building satisfies the requirements for release without radiological controls.

B.D. Estes

2009-04-24T23:59:59.000Z

291

How to deal with radiologically contaminated vegetation  

SciTech Connect (OSTI)

This report describes the findings from a literature review conducted as part of a Department of Energy, Office of Technology Development Biomass Remediation Task. The principal objective of this project is to develop a process or group of processes to treat radiologically contaminated vegetation in a manner that minimizes handling, processing, and treatment costs. Contaminated, woody vegetation growing on waste sites at SRS poses a problem to waste site closure technologies that are being considered for these sites. It is feared that large sections of woody vegetation (logs) can not be buried in waste sites where isolation of waste is accomplished by capping the site. Logs or large piles of woody debris have the potential of decaying and leaving voids under the cap. This could lead to cap failure and entrance of water into the waste. Large solid objects could also interfere with treatments like in situ mixing of soil with grout or other materials to encapsulate the contaminated sediments and soils in the waste sites. Optimal disposal of the wood includes considerations of volume reduction, treatment of the radioactive residue resulting from volume reduction, or confinement without volume reduction. Volume reduction consists primarily of removing the carbon, oxygen, and hydrogen in the wood, leaving an ash that would contain most of the contamination. The only contaminant that would be released by volume reduction would by small amounts of the radioactive isotope of hydrogen, tritium. The following sections will describe the waste sites at SRS which contain contaminated vegetation and are potential candidates for the technology developed under this proposal. The description will provide a context for the magnitude of the problem and the logistics of the alternative solutions that are evaluated later in the review. 76 refs.

Wilde, E.W.; Murphy, C.E.; Lamar, R.T.; Larson, M.J.

1996-12-31T23:59:59.000Z

292

Final Report - Independent Confirmatory Survey Summary and Results for the Hematite Decommissioning Project  

SciTech Connect (OSTI)

The objectives of the confirmatory surveys were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee’s procedures and survey results.

E.N. Bailey

2009-03-18T23:59:59.000Z

293

BASF's Energy Survey Methodology  

E-Print Network [OSTI]

and cost breakdowns by utility types are identified to further analyze trends. Consideration is given to the review of the various energy supply contracts for alternative options that may exist. The consumption history is used to create a distribution...BASF?s Energy Survey Methodology Thomas R. Theising BASF Corporation operates several dozen manufacturing Sites within NAFTA and periodically conducts Energy Surveys at each Site. Although these manufacturing sites represent a variety...

Theising, T. R.

2005-01-01T23:59:59.000Z

294

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

Radiological Threat Task Force Established | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

295

Mobile autonomous robotic apparatus for radiologic characterization  

DOE Patents [OSTI]

A mobile robotic system that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console.

Dudar, Aed M. (Dearborn, MI); Ward, Clyde R. (Aiken, SC); Jones, Joel D. (Aiken, SC); Mallet, William R. (Cowichan Bay, CA); Harpring, Larry J. (North Augusta, SC); Collins, Montenius X. (Blackville, SC); Anderson, Erin K. (Pleasanton, CA)

1999-01-01T23:59:59.000Z

296

Mobile autonomous robotic apparatus for radiologic characterization  

DOE Patents [OSTI]

A mobile robotic system is described that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console. 4 figs.

Dudar, A.M.; Ward, C.R.; Jones, J.D.; Mallet, W.R.; Harpring, L.J.; Collins, M.X.; Anderson, E.K.

1999-08-10T23:59:59.000Z

297

Corrective Action Site 02-37-02 Background Information and Comparison to Corrective Action Site 09-99-06  

SciTech Connect (OSTI)

Corrective Action Site (CAS) 02-37-02, Gas Sampling Assembly, is associated with nuclear test MULLET. MULLET was an underground safety test conducted on October 17, 1963. The experiment also involved prompt sampling of particulate material from the detonation, similar to CAS 09-99-06, Gas Sampling Assembly, which is associated with PLAYER/YORK. The sampling system at MULLET was similar to that of PLAYER/YORK and was used to convey gas from the MULLET emplacement hole (U2ag) to a sampling assembly. Beyond the sampling assembly, the system had a 'Y' junction with one branch running to a filter unit and the other running to a scrubber unit. The total system length was approximately 250 feet and is depicted on the attached drawing. According to the available background information, retrieval of the sample material from the MULLET event caused significant alpha (plutonium) contamination, limited to an area near ground zero (GZ). Test support Radiological Control Technicians did not detect contamination outside the immediate GZ area. In addition, vehicles, equipment, and workers that were contaminated were decontaminated on site. Soil contamination was addressed through the application of oil, and the site was decommissioned after the test. Any equipment that could be successfully decontaminated and had a future use was removed from the site. The contaminated equipment and temporary buildings erected to support the test were buried on site, most likely in the area under the dirt berm. The exact location of the buried equipment and temporary buildings is unknown. No information was found describing the disposition of the filter and scrubber, but they are not known to be at the site. The COMMODORE test was conducted at U2am on May 20, 1967, and formed the crater next to CAS 02-37-02. The COMMODORE test area had been surveyed prior to the test, and alpha contamination was not identified. Furthermore, alpha contamination was not identified during the COMMODORE re-entry survey, and routine surveys around the crater lip did not identify alpha contamination. Background information includes several radiological surveys conducted after these two tests. The MULLET area has been surveyed frequently. The early surveys indicate the area as both contaminated and containing buried radioactive material. A survey conducted in 1970 found the radiological/chemical piping partially intact, including the 'Y' junction, and shows two runs of intact piping running past the U2am crater lip. The survey focused on the piping system itself and detected alpha contamination from 4 counts per minute (cpm) to 900,000 cpm. The highest value was at a pipe flange between a dirt pile and a dirt berm within the current site fence line. All readings were direct, and no smears were taken. A 1972 survey was essentially a repeat of the 1970 survey; however, it does not show the 'Y' junction nor does it show piping extending past the U2am crater lip. It also shows a new fence line separating the radiological/chemical piping from the U2am crater area with all piping within the fence. Alpha contamination was detected on pipe flanges during the survey, but alpha contamination was not detected on the dirt pile or the dirt berm. All readings were direct, and no smears were taken. Additional surveys were conducted in 1986, 1990, 1992, 1993, and 1996. One of the surveys focused on determining the extent of soil contamination around GZ. An alpha contamination plume extending approximately 200 feet south of GZ was detected in a swath approximately 100 feet wide. The maximum measurement was 15,000 cpm alpha. All surveys show the piping within the fence line. Recent surveys (2007 and 2008) were performed around the current fence line by the demarcation group. No removable contamination was identified during these surveys. In late 2008, a visual inspection of the site was conducted by the National Security Technologies, LLC, Environmental Restoration group. All piping is within the fence line. Photos taken during this site visit are attached.

none,

2012-06-26T23:59:59.000Z

298

Best practice techniques for environmental radiological monitoring  

E-Print Network [OSTI]

Best practice techniques for environmental radiological monitoring Science Report ­ SC030308/SR SCHO0407BMNL-E-P #12;ii Science Report Best Practice Techniques for Environmental Radiological #12;iv Science Report Best Practice Techniques for Environmental Radiological Monitoring Executive

299

International Data on Radiological Sources  

SciTech Connect (OSTI)

ABSTRACT The mission of radiological dispersal device (RDD) nuclear forensics is to identify the provenance of nuclear and radiological materials used in RDDs and to aid law enforcement in tracking nuclear materials and routes. The application of databases to radiological forensics is to match RDD source material to a source model in the database, provide guidance regarding a possible second device, and aid the FBI by providing a short list of manufacturers and distributors, and ultimately to the last legal owner of the source. The Argonne/Idaho National Laboratory RDD attribution database is a powerful technical tool in radiological forensics. The database (1267 unique vendors) includes all sealed sources and a device registered in the U.S., is complemented by data from the IAEA Catalogue, and is supported by rigorous in-lab characterization of selected sealed sources regarding physical form, radiochemical composition, and age-dating profiles. Close working relationships with global partners in the commercial sealed sources industry provide invaluable technical information and expertise in the development of signature profiles. These profiles are critical to the down-selection of potential candidates in either pre- or post- event RDD attribution. The down-selection process includes a match between an interdicted (or detonated) source and a model in the database linked to one or more manufacturers and distributors.

Martha Finck; Margaret Goldberg

2010-07-01T23:59:59.000Z

300

RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT  

E-Print Network [OSTI]

RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT: Minors in Research Laboratories or Animal Facilities Page 1 of 4 PURPOSE: The purpose of this document is to provide guidance for Purdue sponsored programs which are designed for youth under the age of 15 and which have documented

Holland, Jeffrey

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Departmental Radiological Emergency Response Assets  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The order establishes requirements and responsibilities for the DOE/NNSA national radiological emergency response assets and capabilities and Nuclear Emergency Support Team assets. Cancels DOE O 5530.1A, DOE O 5530.2, DOE O 5530.3, DOE O 5530.4, and DOE O 5530.5.

2007-06-27T23:59:59.000Z

302

A review of the radiological treatment  

SciTech Connect (OSTI)

The Draft Waste Management Programmatic Environmental Impact Statement (WM PEIS) was released by the U.S. Department of Energy (DOE) for public comment on September 22, 1995. Prepared in accordance with the National Environmental Policy Act (NEPA), the Final WM PEIS is currently scheduled for release in late summer 1996. The Draft WM PEIS was published after about 3 years of effort to select and evaluated the best alternatives for treating, storing, and disposing of the 50-year legacy of radioactive and chemically hazardous wastes existing within the DOE complex. The evaluation examined the potential health and environmental impacts of integrated waste management alternatives for five categories of waste types at 54 DOE sites. A primary consideration as a potential source of human health impacts at all sites is that of radiological releases resulting from postulated accidents involving facilities used to treat radioactive wastes. This paper first provides a brief, updated summary of the approach used to define and perform treatment facility accident analyses in the Draft WM PEIS. It reviews the selection of dominant sequences for the major sites most affected by the preferred waste management alternatives and highlights the salient accident analysis results. Finally, it summarizes and addresses key public and state and federal agency comments relating to accident analysis that were received in the public comment process.

Mueller, C.J.; Folga, S.; Nabelssi, B.; Kohout, E.

1996-07-01T23:59:59.000Z

303

Corrective Action Investigation Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric Test Site T-7C; (2) 07-23-04, Atmospheric Test Site T7-1; (3) 07-23-05, Atmospheric Test Site; (4) 07-23-06, Atmospheric Test Site T7-5a; (5) 07-23-07, Atmospheric Test Site - Dog (T-S); (6) 07-23-08, Atmospheric Test Site - Baker (T-S); (7) 07-23-09, Atmospheric Test Site - Charlie (T-S); (8) 07-23-10, Atmospheric Test Site - Dixie; (9) 07-23-11, Atmospheric Test Site - Dixie; (10) 07-23-12, Atmospheric Test Site - Charlie (Bus); (11) 07-23-13, Atmospheric Test Site - Baker (Buster); (12) 07-23-14, Atmospheric Test Site - Ruth; (13) 07-23-15, Atmospheric Test Site T7-4; (14) 07-23-16, Atmospheric Test Site B7-b; (15) 07-23-17, Atmospheric Test Site - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) to the dose-based final action level (FAL). The presence of TED exceeding the FAL is considered a radiological contaminant of concern (COC). Anything identified as a COC will require corrective action. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters will be used to measure external radiological dose. Based on process knowledge of the releases associated with the nuclear tests and radiological survey information about the location and shape of the resulting contamination plume, it was determined that the releases from the nuclear tests are co-located and will be investigated concurrently. A field investigation will be performed to define areas where TED exceeds the FAL and to determine whether other COCs are present at the site. The investigation will also collect information to determine the presence and nature of contamination associated with migration and excavation, as well as any potential releases discovered during the investigation. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Patrick Matthews

2011-08-01T23:59:59.000Z

304

Remaining Sites Verification Package for the 126-F-2, 183-F Clearwells, Waste Site Reclassification Form 2006-017  

SciTech Connect (OSTI)

The 126-F-2 site is the clearwell facility formerly used as part of the reactor cooling water treatment at the 183-F facility. During demolition operations in the 1970s, potentially contaminated debris was disposed in the eastern clearwell structure. The site has been remediated by removing all debris in the clearwell structure to the Environmental Restoration Disposal Facility. The results of radiological surveys and visual inspection of the remediated clearwell structure show neither residual contamination nor the potential for contaminant migration beyond the clearwell boundaries. The results of verification sampling at the remediation waste staging area demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

R. A. Carlson

2006-05-04T23:59:59.000Z

305

Trench sampling report Salmon Site Lamar County, Mississippi  

SciTech Connect (OSTI)

This report describes trench excavation and sample-collection activities conducted by IT Corporation (IT) as part of the ongoing Remedial Investigation and Feasibility Study at the Salmon Site, Lamar County, Mississippi (DOE, 1992). During construction, operation, and closure of the site wastes of unknown composition were buried in pits on site. Surface-geophysical field investigations were conducted intermittently between November 1992 and October 1993 to identify potential waste-burial sites and buried metallic materials. The geophysical investigations included vertical magnetic gradient, electromagnetic conductivity, electromagnetic in-phase component, and ground-penetrating radar surveys. A number of anomalies identified by the magnetic gradiometer survey in the Reynolds Electrical & Engineering Co., Inc., (REECo) pits area indicated buried metallic objects. All of the anomalies were field checked to determine if any were caused by surface features or debris. After field checking, 17 anomalies were still unexplained; trenching was planned to attempt to identify their sources. Between December 8, 1993, and December 17, 1993, 15 trenches were excavated and soil samples were collected at the anomalies. Samples were collected, placed in 250- and 500-milliliter (m{ell}) amber glass containers, and shipped on ice to IT Analytical Services (ITAS) in St. Louis, Missouri, using standard IT chain-of-custody procedures. The samples were analyzed for various chemical and radiological parameters. Data validation has not been conducted on any of the samples. During excavation and sampling, soil samples were also collected by IT for the MSDEQ and the Mississippi Department of Radiological Health, in accordance with their instructions, and delivered into their custody.

Not Available

1994-07-01T23:59:59.000Z

306

Annual Site Environmental Report for Calendar Years 2005-2006  

SciTech Connect (OSTI)

Contained in the following report are data for radioactivity in the environment collected and analyzed by Princeton Plasma Physics Laboratory's Princeton Environmental, Analytical, and Radiological Laboratory (PEARL). The PEARL is located on-site and is certified for analyzing radiological and non-radiological parameters through the New Jersey Department of Environmental Protection's Laboratory Certification Program, Certification Number 12471. Non-radiological surface and ground water samples are analyzed by NJDEP certified subcontractor laboratories - QC, Inc. and Accutest Laboratory. To the best of our knowledge, these data, as contained in the "Annual Site Environmental Report for 2005 and 2006," are documented and certified to be correct.

Virginia L. Finley

2010-01-25T23:59:59.000Z

307

Understanding Mechanisms of Radiological Contamination  

SciTech Connect (OSTI)

Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel, spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining these different types of contamination (and subsequent decontamination processes), which have included several different radionuclides and substrates, sheds light on contamination processes that occur throughout the nuclear industry and in the urban environment.

Rick Demmer; John Drake; Ryan James, PhD

2014-03-01T23:59:59.000Z

308

Robotic Surveying  

SciTech Connect (OSTI)

ZAPATA ENGINEERING challenged our engineers and scientists, which included robotics expertise from Carnegie Mellon University, to design a solution to meet our client's requirements for rapid digital geophysical and radiological data collection of a munitions test range with no down-range personnel. A prime concern of the project was to minimize exposure of personnel to unexploded ordnance and radiation. The field season was limited by extreme heat, cold and snow. Geographical Information System (GIS) tools were used throughout this project to accurately define the limits of mapped areas, build a common mapping platform from various client products, track production progress, allocate resources and relate subsurface geophysical information to geographical features for use in rapidly reacquiring targets for investigation. We were hopeful that our platform could meet the proposed 35 acres per day, towing both a geophysical package and a radiological monitoring trailer. We held our breath and crossed our fingers as the autonomous Speedrower began to crawl across the playa lakebed. We met our proposed production rate, and we averaged just less than 50 acres per 12-hour day using the autonomous platform with a path tracking error of less than +/- 4 inches. Our project team mapped over 1,800 acres in an 8-week (4 days per week) timeframe. The expertise of our partner, Carnegie Mellon University, was recently demonstrated when their two autonomous vehicle entries finished second and third at the 2005 Defense Advanced Research Projects Agency (DARPA) Grand Challenge. 'The Grand Challenge program was established to help foster the development of autonomous vehicle technology that will some day help save the lives of Americans who are protecting our country on the battlefield', said DARPA Grand Challenge Program Manager, Ron Kurjanowicz. Our autonomous remote-controlled vehicle (ARCV) was a modified New Holland 2550 Speedrower retrofitted to allow the machine-actuated functions to be controlled by an onboard computer. The computer-controlled Speedrower was developed at Carnegie Mellon University to automate agricultural harvesting. Harvesting tasks require the vehicle to cover a field using minimally overlapping rows at slow speeds in a similar manner to geophysical data acquisition. The Speedrower had demonstrated its ability to perform as it had already logged hundreds of acres of autonomous harvesting. This project is the first use of autonomous robotic technology on a large-scale for geophysical surveying.

Suzy Cantor-McKinney; Michael Kruzic

2007-03-01T23:59:59.000Z

309

Operations Improvement Surveys  

E-Print Network [OSTI]

-1981 timeframe. The first 20% of energy savings, versus the 1972 reference, had already been captured or was in progress via conventional energy conservation methods. The site energy surveys identified attractive investments to save a second 20% of energy use...

Guide, J. J.; O'Brien, W. J.

1984-01-01T23:59:59.000Z

310

Radioactive Waste Management Complex low-level waste radiological performance assessment  

SciTech Connect (OSTI)

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01T23:59:59.000Z

311

Hanford radiological protection support services annual report for 1988  

SciTech Connect (OSTI)

The report documents the performance of certain radiological protection sitewide services during calendar year (CY) 1988 by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy-Richland Operations Office (DOE-RL) and contractor activities on the Hanford Site. The routine program for each service is discussed along with any significant program changes and tasks, investigations, and studies performed in support of each program. Other related activities such as publications, presentations, and memberships on standard or industry committees are also listed. The programs covered provide services in the areas of (1) internal dosimetry, (2) in vivo measurements, (3) external dosimetry, (4) instrument calibration and evaluation, (5) calibration of radiation sources traceable to the National Institute of Standards and Technology (NIST) (formerly the National Bureau of Standards), and (6) radiological records. 23 refs., 15 figs., 15 tabs.

Lyon, M.; Fix, J.J.; Kenoyer, J.L.; Leonowich, J.A.; Palmer, H.E.; Sula, M.J.

1989-06-01T23:59:59.000Z

312

CONSULTANT REPORT APPLIANCE MARKET SURVEY  

E-Print Network [OSTI]

found at retail/wholesale stores, Internet sites, and in catalogs. This report delineates the degree.....................................................................................................................5 Retail/Wholesale Store Surveys ..........................................................................................................5 Retail/Wholesale Store Site Selection ..................................

313

Physics Division ESH Bulletin 2007-03 Radiological Survey Requirements  

E-Print Network [OSTI]

and found to contain no other radioactive material or contamination. The direct cause of this incident Area Airborne Radioactivity Area High Contamination Area Contamination Area Contamination Buffer Awareness Program (OAP) inspection, a small, unlabeled plastic bag that was emitting radioactivity

314

I RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$ EGcG ENERGYELIkNATIONHEALXH: l ._ .r.,--I Is ILwrgv

315

Letter: Katy Trail Radiological Survey at Southeast Drainage.  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$ EGcG ENERGYELIkNATIONHEALXH:LTS Plan WorkshopI9 I

316

Roadmap: Radiologic Technology Radiology Department Management Technology Associate of Technical Study  

E-Print Network [OSTI]

Roadmap: Radiologic Technology ­ Radiology Department Management Technology ­ Associate-Nov-13/LNHD This roadmap is a recommended semester-by-semester plan of study for this major. However

Sheridan, Scott

317

Radiological Triage | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Data results provided back to the field within 30-60 minutes. All NNSA teams that conduct search, detection and identification operations, to include the Radiological...

318

ORISE Resources: Radiological and Nuclear Terrorism: Medical...  

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

Training Clinicians for Response to a Radiological or Nuclear Terrorism Attack The Centers for Disease Control and Prevention and its Radiation Studies Branch in the National...

319

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

(trained personnel and equipment) to evaluate, assess, advise, isotopically identify, search for, and assist in the mitigation of actual or perceived nuclear or radiological...

320

NV/YMP radiological control manual, Revision 2  

SciTech Connect (OSTI)

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

Gile, A.L. [comp.] [comp.

1996-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Hanford site near-facility environmental monitoring annual report, calendar year 1996  

SciTech Connect (OSTI)

This document summarizes the results of the near-facility environmental monitoring results for 1996 in the 100, 200/600, and 300/400 areas of the Hanford Site in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. The monitoring implements applicable portions of DOE Orders 5400.1 (DOE 1988a), 5400.5 (DOE 1990), and 5820.2A (DOE 1988b); Washington Administrative Code (WAC) 246-247; and Title 40 Code of Federal Regulations (CFR) Part 61, Subpart H (EPA 1989). In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels were slightly elevated when compared to offsite locations, the differences are less than in previous years.

Perkins, C.J.

1997-08-05T23:59:59.000Z

322

Site Environmental Report for 2001  

SciTech Connect (OSTI)

The mission of Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) is to continue the long tradition of outstanding research that has made it a premier national and international multiprogram laboratory. In order to provide the highest degree of protection for the public and the environment, Berkeley Lab employs Integrated Safety Management (ISM). ISM is a comprehensive U.S. Department of Energy management system that involves five core functions (work planning, hazard and risk analysis, establishment of controls, work performance, and feedback and improvement). These five core functions are applied to all activities at Berkeley Lab. Laboratory activities are planned and conducted with full regard to protecting the public and the environment and complying with appropriate environmental laws and regulations. Both radiological and nonradiological activities are thoroughly monitored to assess their potential impact on public health and the environment. This annual Site Environmental Report covers activities for calendar year (CY) 2001. Volume I summarizes environmental protection performance and environmental monitoring activities. Volume II contains individual analytical data summarized in the first volume. Volume II is available on request. (For details, see the Preface.) Data are presented in the report using the International System of Units measuring system, more commonly referred to as the metric system. For the convenience of readers, both volumes of this report can be accessed on the Web from the Berkeley Lab Environmental Services home page, which is located at http://www.lbl.gov/ehs/esg. Readers are encouraged to comment on this report by completing either the survey card included with the distributed hard copy of the report or the survey form in the Web version of the report. The format and content of this report satisfy the requirements of United States Department of Energy (DOE) Order 231.1, Environment, Safety and Health Reporting,1 and the operating contract between the University of California Office of the President (UCOP) and DOE.

Pauer, Ron

2002-07-01T23:59:59.000Z

323

The inspection of a radiologically contaminated pipeline using a teleoperated pipe crawler  

SciTech Connect (OSTI)

In the 1950s, the Savannah River Site built an open, unlined retention basin to temporarily store potentially radionuclide contaminated cooling water from a chemical separations process and storm water drainage from a nearby waste management facility that stored large quantities of nuclear fission byproducts in carbon steel tanks. The retention basin was retired from service in 1972 when a new, lined basin was completed. In 1978, the old retention basin was excavated, backfilled with uncontaminated dirt, and covered with grass. At the same time, much of the underground process pipeline leading to the basin was abandoned. Since the closure of the retention basin, new environmental regulations require that the basin undergo further assessment to determine whether additional remediation is required. A visual and radiological inspection of the pipeline was necessary to aid in the remediation decision making process for the retention basin system. A teleoperated pipe crawler inspection system was developed to survey the abandoned sections of underground pipelines leading to the retired retention basin. This paper will describe the background to this project, the scope of the investigation, the equipment requirements, and the results of the pipeline inspection.

Fogle, R.F.; Kuelske, K.; Kellner, R.A.

1995-08-01T23:59:59.000Z

324

2012-2013 Diagnostic Radiology Fellows Cardiovascular Imaging  

E-Print Network [OSTI]

dbweinreb@ Pediatric Radiology Body Imaging 1st yr. Neuroradiology NCI Body Mammography Sonya Edwards 149042012-2013 Diagnostic Radiology Fellows Cardiovascular Imaging Nuclear Medicine David Weinreb 14895 14909 laxpati@ Michael Kim 14961 mjjkim@ Vascular and Interventional Radiology Charles Kosydar 14908

Sonnenburg, Justin L.

325

Federal Radiological Monitoring and Assessment Center  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish Department of Energy (DOE) policy, procedures, authorities, and requirements for the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC), as set forth in the Federal Radiological Emergency Response Plan (FRERP). This directive does not cancel another directive. Canceled by DOE O 153.1.

1992-12-02T23:59:59.000Z

326

Memorandum, Reporting of Radiological Sealed Sources Transactions  

Broader source: Energy.gov [DOE]

The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed Sources. The data reported in accordance with DOE N 234.1 are maintained in the DOE Radiological Source Registry and Tracking (RSRT) database by the Office of Information Management, within the Office of Environment, Health, Safety and Security.

327

INL@Work Radiological Search & Response Training  

ScienceCinema (OSTI)

Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

Turnage, Jennifer

2013-05-28T23:59:59.000Z

328

Siting evaluations for the ignitor fusion experiment: Preliminary radiological assessments  

E-Print Network [OSTI]

Ignitor is a proposed compact high-magnetic field tokamak aimed at studying plasma burning conditions in Deuterium-Tritium plasmas. Localisation of this experiment in Italy has seen growing attention during the last years. ...

Coppi, Bruno

329

Radiological Dose Assessment 8 2005 Site environmental report8-  

E-Print Network [OSTI]

energy state, emit- ting photon energy (light), which is measured with a photomultiplier tube; the light-term projects conducted in 2005, such as remediation work and waste management disposal activities, were

330

RADIOLOGICAL DOSE ASSESSMENT 1997 BNL Site Environmental Report 9 -1  

E-Print Network [OSTI]

of Title 40 CFR Part 61, Subpart H, National Emission Standards for Hazardous Air Pollutants (NESHAPs to the location of interest. The program supplies both the calculated EDE to the maximally exposed individual of the Long Island Lighting Company. For modeling the dose to the maximally exposed individual (MEI), all

331

Work plan for monitor well installation water and sediment sample collection aquifer testing and topographic surveying at the Riverton, Wyoming, UMTRA Project Site  

SciTech Connect (OSTI)

Investigations conducted during preparation of the site observational work plan (SOWP) at the Uranium Mill Tailings Remedial Action (UMTRA) Project site support a proposed natural flushing ground water compliance strategy, with institutional controls. However, additional site-specific data are needed to reduce uncertainties in order to confirm the applicability and feasibility of this proposed compliance strategy option. This proposed strategy will be analyzed in the site-specific environmental assessment. The purpose of this work plan is to summarize the data collection objectives to fill those data needs, describe the data collection activities that will be undertaken to meet those objectives, and elaborate on the data quality objectives which define the procedures that will be followed to ensure that the quality of these data meet UMTRA Project needs.

NONE

1995-06-01T23:59:59.000Z

332

CRAD, Radiological Controls - Oak Ridge National Laboratory TRU...  

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

Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A...

333

Unified Resolve 2014: A Proof of Concept for Radiological Support...  

Office of Environmental Management (EM)

Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders...

334

Hanford radiological protection support services annual report for 1990  

SciTech Connect (OSTI)

Various Hanford site-wide radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy-Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1990. These activities include internal dosimetry measurements and evaluations, in vivo measurements, external dosimetry measurements and evaluations, instrument calibration and evaluation, radiation source calibration, and radiological records keeping. For each of these activities, the routine program, program changes and enhancements, associated tasks, investigations and studies, and related publications, presentations, and other staff professional activities are discussed as applicable. 22 refs., 10 figs., 19 tabs.

Lyon, M; Bihl, D E; Fix, J J; Piper, R K; Freolich, T J; Leonowich, J A; Lynch, T P

1991-07-01T23:59:59.000Z

335

Hanford Radiological Protection Support Services annual report for 1993  

SciTech Connect (OSTI)

Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1993. These activities include internal dosimetry measurements and evaluations, in vivo measurements, external dosimetry measurements and evaluations, instrument calibration and evaluation, radiation source calibration, and radiological record keeping. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

Lyon, M.; Bihl, D.E.; Fix, J.J.; Froelich, T.J.; Piper, R.K.; Olsen, P.C.

1994-07-01T23:59:59.000Z

336

Hanford Radiological Protection Support Services annual report for 1992  

SciTech Connect (OSTI)

Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Field Office and Hanford contractors are described in this annual report of calendar year 1992. These activities include internal dosimetry measurements and evaluations, in vivo measurements, external dosimetry measurements and evaluations, instrument calibration and evaluation, radiation source calibration, and radiological record keeping. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

Lyon, M; Bihl, D E; Fix, J J; Piper, R K; Froelich, T J; Lynch, T P

1993-07-01T23:59:59.000Z

337

Hanford radiological protection support services annual report for 1997  

SciTech Connect (OSTI)

Various Hanford Site radiation protection services provided by the Pacific Northwest National Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1997. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological exposure record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

Lyon, M.; Bihl, D.E.; Fix, J.J.; Johnson, M.L.; Lynch, T.P.; Piper, R.K.

1998-06-01T23:59:59.000Z

338

Hanford radiological protection support services. Annual report for 1995  

SciTech Connect (OSTI)

Various Hanford Site radiation protection services provided by the Pacific Northwest National Laboratory for the U.S. Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1995. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

Lyon, M.; Bihl, D.E.; Carbaugh, E.H. [and others

1996-05-01T23:59:59.000Z

339

Hanford radiological protection support services annual report for 1996  

SciTech Connect (OSTI)

Various Hanford Site radiation protection services provided by the Pacific Northwest National Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for calendar year 1996. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological exposure record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program-related publications, presentations, and other staff professional activities are also described.

Lyon, M.; Bihl, D.E.; Fix, J.J.; Froelich, T.J.; Piper, R.K.; Schulze, S.A.

1997-06-01T23:59:59.000Z

340

Hanford radiological protection support services annual report for 1994  

SciTech Connect (OSTI)

Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for the calendar year 1994. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program- related publications, presentations, and other staff professional activities are also described.

Lyon, M.; Bihl, D.E.; Fix, J.J.; Piper, R.K.; Froelich, T.J.; Olsen, P.C.

1995-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Hanford Site Regional Population - 2010 Census  

SciTech Connect (OSTI)

The U.S. Department of Energy conducts radiological operations in south-central Washington State. Population dose estimates must be performed to provide a measure of the impact from site radiological releases. Results of the U.S. 2010 Census were used to determine counts and distributions for the residential population located within 50-miles of several operating areas of the Hanford Site. Year 2010 was the first census year that a 50-mile population of a Hanford Site operational area exceeded the half-million mark.

Hamilton, Erin L.; Snyder, Sandra F.

2011-08-12T23:59:59.000Z

342

St. Louis Sites Fact Sheet RADIATION BASICS  

E-Print Network [OSTI]

of Engineers, FUSRAP Project Office, 8945 Latty Avenue, Berkeley, Missouri 63134 #12;Rad Basics - 081202St. Louis Sites Fact Sheet RADIATION BASICS "Gateway to Excellence" U.S. Army Corps of Engineers St), St. Louis District, is conducting a radiological cleanup program for four Missouri sites (SLDS, SLAPS

US Army Corps of Engineers

343

REVISED FINAL REPORT – INDEPENDENT VERIFICATION SURVEY ACTIVITIES AT THE SEPARATIONS PROCESS RESEARCH UNIT SITES, NISKAYUNA, NEW YORK – DCN 0496-SR-06-1  

SciTech Connect (OSTI)

The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

Evan Harpenau

2011-10-10T23:59:59.000Z

344

Integrating pathology and radiology disciplines: an emerging opportunity?  

E-Print Network [OSTI]

Pediatric vascular malformations: pathophysiology, diagnosis, and the role of interventional radiology.

Sorace, James; Aberle, Denise R; Elimam, Dena; Lawvere, Silvana; Tawfik, Ossama; Wallace, W Dean

2012-01-01T23:59:59.000Z

345

The Health Physics and Radiological Health  

E-Print Network [OSTI]

of the nuclear data required to compute this constant is available (Kocher 1981) for approximately 500 nuclides important to dosimetry and radiological assessment applications, and it has been used to compute a table

346

Radiological safety training for uranium facilities  

SciTech Connect (OSTI)

This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

NONE

1998-02-01T23:59:59.000Z

347

Apparatus for safeguarding a radiological source  

DOE Patents [OSTI]

A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

Bzorgi, Fariborz M

2014-10-07T23:59:59.000Z

348

CRAD, Radiological Controls - Idaho Accelerated Retrieval Project...  

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

Accelerated Retrieval Project Phase II CRAD, Radiological Controls - Idaho Accelerated Retrieval Project Phase II February 2006 A section of Appendix C to DOE G 226.1-2 "Federal...

349

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network [OSTI]

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

A. Petraglia; C. Sabbarese; M. De Cesare; N. De Cesare; F. Quinto; F. Terrasi; A. D'Onofrio; P. Steier; L. K. Fifield; A. M. Esposito

2012-07-17T23:59:59.000Z

350

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network [OSTI]

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

Petraglia, A; De Cesare, M; De Cesare, N; Quinto, F; Terrasi, F; D'Onofrio, A; Steier, P; Fifield, L K; Esposito, A M; 10.1051/radiopro/2012010

2012-01-01T23:59:59.000Z

351

Benchmarking survey for recycling.  

SciTech Connect (OSTI)

This report describes the methodology, analysis and conclusions of a comparison survey of recycling programs at ten Department of Energy sites including Sandia National Laboratories/New Mexico (SNL/NM). The goal of the survey was to compare SNL/NM's recycling performance with that of other federal facilities, and to identify activities and programs that could be implemented at SNL/NM to improve recycling performance.

Marley, Margie Charlotte; Mizner, Jack Harry

2005-06-01T23:59:59.000Z

352

US Department of Energy Radiological Control Manual  

SciTech Connect (OSTI)

This manual establishes practices for the conduct of radiological control activities. The Manual states DOE`s positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. (VC)

Not Available

1992-06-01T23:59:59.000Z

353

US Department of Energy Radiological Control Manual  

SciTech Connect (OSTI)

This manual establishes practices for the conduct of radiological control activities. The Manual states DOE's positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. (VC)

Not Available

1992-06-01T23:59:59.000Z

354

Contained radiological analytical chemistry module  

DOE Patents [OSTI]

A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

Barney, David M. (Scotia, NY)

1989-01-01T23:59:59.000Z

355

Contained radiological analytical chemistry module  

DOE Patents [OSTI]

A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

Barney, David M. (Scotia, NY)

1990-01-01T23:59:59.000Z

356

Nevada Test Site Environmental Report 2004  

SciTech Connect (OSTI)

The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders.

BECHTEL NEVADA

2005-10-01T23:59:59.000Z

357

Authorized Limits for the Release of a 25 Ton Locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly Facility, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This document contains process knowledge and radiological data and analysis to support approval for release of the 25-ton locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly (EMAD) Facility, located on the Nevada Test Site (NTS). The 25-ton locomotive is a small, one-of-a-kind locomotive used to move railcars in support of the Nuclear Engine for Rocket Vehicle Application project. This locomotive was identified as having significant historical value by the Nevada State Railroad Museum in Boulder City, Nevada, where it will be used as a display piece. A substantial effort to characterize the radiological conditions of the locomotive was undertaken by the NTS Management and Operations Contractor, National Security Technologies, LLC (NSTec). During this characterization process, seven small areas on the locomotive had contamination levels that exceeded the NTS release criteria (limits consistent with U.S. Department of Energy [DOE] Order DOE O 5400.5, “Radiation Protection of the Public and the Environment”). The decision was made to perform radiological decontamination of these known accessible impacted areas to further the release process. On February 9, 2010, NSTec personnel completed decontamination of these seven areas to within the NTS release criteria. Although all accessible areas of the locomotive had been successfully decontaminated to within NTS release criteria, it was plausible that inaccessible areas of the locomotive (i.e., those areas on the locomotive where it was not possible to perform radiological surveys) could potentially have contamination above unrestricted release limits. To access the majority of these inaccessible areas, the locomotive would have to be disassembled. A complete disassembly for a full radiological survey could have permanently destroyed parts and would have ruined the historical value of the locomotive. Complete disassembly would also add an unreasonable financial burden for the contractor. A decision was reached between the NTS regulator and NSTec, opting for alternative authorized limits from DOE Headquarters. In doing so, NSTec personnel performed a dose model using the DOE-approved modeling code RESRAD-BUILD v3.5 to evaluate scenarios. The parameters used in the dose model were conservative. NSTec’s Radiological Engineering Calculation, REC-2010-001, “Public Dose Estimate from the EMAD 25 Ton Locomotive,” concluded that the four scenarios evaluated were below the 25-millirem per year limit, the “likely” dose scenarios met the “few millirem in a year” criteria, and that the EMAD 25-ton locomotive met the radiological requirements to be released with residual radioactivity to the public.

Jeremy Gwin and Douglas Frenette

2010-04-08T23:59:59.000Z

358

CONFIRMATORY SURVEY OF THE DEFENSE LOGISTICS AGENCY, DEFENSE NATIONAL STOCKPILE CENTER NEW HAVEN DEPOT, NEW HAVEN, INDIANA  

SciTech Connect (OSTI)

The objectives of the radiological confirmatory survey were to collect adequate radiological data for use in evaluating the radiological condition of NHD land areas, warehouses, and support buildings. The data generated from the confirmatory survey activities were used to evaluate the results of the Final Status Survey Report (FSSR) submitted by Cabrera Services (Cabrera 2009). Cabrera has stated that all radioactive materials have been removed and that remediation of the open land areas and structure surfaces was complete, and that the NHD meets the criteria for unrestricted use.

E.M. Harpenau

2010-02-19T23:59:59.000Z

359

Nevada Test Site Environmental Report 2005  

SciTech Connect (OSTI)

The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

Cathy A. Wills

2006-10-01T23:59:59.000Z

360

Reducing Contingency through Sampling at the Luckey FUSRAP Site - 13186  

SciTech Connect (OSTI)

Typically, the greatest risk in developing accurate cost estimates for the remediation of hazardous, toxic, and radioactive waste sites is the uncertainty in the estimated volume of contaminated media requiring remediation. Efforts to address this risk in the remediation cost estimate can result in large cost contingencies that are often considered unacceptable when budgeting for site cleanups. Such was the case for the Luckey Formerly Utilized Sites Remedial Action Program (FUSRAP) site near Luckey, Ohio, which had significant uncertainty surrounding the estimated volume of site soils contaminated with radium, uranium, thorium, beryllium, and lead. Funding provided by the American Recovery and Reinvestment Act (ARRA) allowed the U.S. Army Corps of Engineers (USACE) to conduct additional environmental sampling and analysis at the Luckey Site between November 2009 and April 2010, with the objective to further delineate the horizontal and vertical extent of contaminated soils in order to reduce the uncertainty in the soil volume estimate. Investigative work included radiological, geophysical, and topographic field surveys, subsurface borings, and soil sampling. Results from the investigative sampling were used in conjunction with Argonne National Laboratory's Bayesian Approaches for Adaptive Spatial Sampling (BAASS) software to update the contaminated soil volume estimate for the site. This updated volume estimate was then used to update the project cost-to-complete estimate using the USACE Cost and Schedule Risk Analysis process, which develops cost contingencies based on project risks. An investment of $1.1 M of ARRA funds for additional investigative work resulted in a reduction of 135,000 in-situ cubic meters (177,000 in-situ cubic yards) in the estimated base volume estimate. This refinement of the estimated soil volume resulted in a $64.3 M reduction in the estimated project cost-to-complete, through a reduction in the uncertainty in the contaminated soil volume estimate and the associated contingency costs. (authors)

Frothingham, David; Barker, Michelle; Buechi, Steve [U.S. Army Corps of Engineers Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States)] [U.S. Army Corps of Engineers Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States); Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)] [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Recovery Act-Funded Study Assesses Contamination at Former Test Site in California  

Broader source: Energy.gov [DOE]

Workers in a study funded by $38 million from the American Recovery and Reinvestment Act to assess radiological contamination have collected more than 600 soil samples and surveyed 120 acres of...

362

Nevada Test Site probable maximum flood study, part of US Geological Survey flood potential and debris hazard study, Yucca Mountain Site for US Department of Energy, Office of Civilian Radioactive Waste Management  

SciTech Connect (OSTI)

The US Geological Survey (USGS), as part of the Yucca Mountain Project (YMP), is conducting studies at Yucca Mountain, Nevada. The purposes of these studies are to provide hydrologic and geologic information to evaluate the suitability of Yucca Mountain for development as a high-level nuclear waste repository, and to evaluate the ability of the mined geologic disposal system (MGDS) to isolate the waste in compliance with regulatory requirements. In particular, the project is designed to acquire information necessary for the Department of Energy (DOE) to demonstrate in its environmental impact statement (EIS) and license application whether the MGDS will meet the requirements of federal regulations 10 CFR Part 60, 10 CFR Part 960, and 40 CFR Part 191. Complete study plans for this part of the project were prepared by the USGS and approved by the DOE in August and September of 1990. The US Bureau of Reclamation (Reclamation) was selected by the USGS as a contractor to provide probable maximum flood (PMF) magnitudes and associated inundation maps for preliminary engineering design of the surface facilities at Yucca Mountain. These PMF peak flow estimates are necessary for successful waste repository design and construction. The PMF technique was chosen for two reasons: (1) this technique complies with ANSI requirements that PMF technology be used in the design of nuclear related facilities (ANSI/ANS, 1981), and (2) the PMF analysis has become a commonly used technology to predict a ``worst possible case`` flood scenario. For this PMF study, probable maximum precipitation (PMP) values were obtained for a local storm (thunderstorm) PMP event. These values were determined from the National Weather Services`s Hydrometeorological Report No. 49 (HMR 49).

Bullard, K.L.

1994-08-01T23:59:59.000Z

363

DOE - Office of Legacy Management -- Sandia National Laboratories...  

Office of Legacy Management (LM)

Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

364

DOE - Office of Legacy Management -- Fernald Environmental Management...  

Office of Legacy Management (LM)

Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

365

DOE - Office of Legacy Management -- Battelle Columbus Laboratories...  

Office of Legacy Management (LM)

Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

366

DOE - Office of Legacy Management -- Commercial (Burial) Disposal...  

Office of Legacy Management (LM)

Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

367

DOE - Office of Legacy Management -- Battelle Memorial Institute...  

Office of Legacy Management (LM)

Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status:...

368

Waste-ACC: A computer model for radiological analysis of waste management  

SciTech Connect (OSTI)

WASTE-ACC, a computational framework and integrated PC-based database system, has been developed by Argonne National Laboratory to assess radiological atmospheric releases from facility accidents in support of the U.S. Department of Energy`s (DOE`s) Waste Management (WM) Programmatic Environmental. Impact Statement, (PEIS). WASTE-ACC facilitates the many calculations required in the accident analyses by the numerous combinations of waste types, treatment technologies, facility locations, and site consolidation strategies in the WM PEIS alternatives for each waste type across the DOE complex. This paper focuses on the computational framework used to assess atmospheric releases and health risk impacts from potential waste management accidents that may affect on-site workers and off-site members of the public. The computational framework accesses several relational databases as needed to calculate radiological releases for the risk dominant accidents. The databases contain throughput volumes, treatment process parameters, radionuclide characteristics, radiological profiles of the waste, site-specific dose conversion factors, and accident data such as frequencies of initiators, conditional probabilities of subsequent events, and source term release parameters of the various waste forms under accident stresses.

Nabelssi, B.K.; Folga, S.; Kohout, E. [Argonne National Laboratory, IL (United States)] [and others

1996-06-01T23:59:59.000Z

369

Independent Confirmatory Survey Report for the University of Arizona Nuclear Reactor Laboratory, Tucson, Arizona  

SciTech Connect (OSTI)

The University of Arizona (University) research reactor is a TRIGA swimming pool type reactor designed by General Atomics and constructed at the University in 1958. The reactor first went into operation in December of 1958 under U.S. Nuclear Regulatory Commission (NRC) license R-52 until final shut down on May 18, 2010. Initial site characterization activities were conducted in February 2009 during ongoing reactor operations to assess the radiological status of the Nuclear Reactor Laboratory (NRL) excluding the reactor tank, associated components, and operating systems. Additional post-shutdown characterization activities were performed to complete characterization activities as well as verify assumptions made in the Decommissioning Plan (DP) that were based on a separate activation analysis (ESI 2009 and WMG 2009). Final status survey (FSS) activities began shortly after the issuance of the FSS plan in May 2011. The contractor completed measurement and sampling activities during the week of August 29, 2011.

Nick A. Altic

2011-11-11T23:59:59.000Z

370

ASPECT Emergency Response Chemical and Radiological Mapping  

ScienceCinema (OSTI)

A unique airborne emergency response tool, ASPECT is a Los Alamos/U.S. Environmental Protection Agency project that can put chemical and radiological mapping tools in the air over an accident scene. The name ASPECT is an acronym for Airborne Spectral Photometric Environmental Collection Technology. Update, Sept. 19, 2008: Flying over storm-damaged refineries and chemical factories, a twin-engine plane carrying the ASPECT (Airborne Spectral Photometric Environmental Collection Technology) system has been on duty throughout the recent hurricanes that have swept the Florida and Gulf Coast areas. ASPECT is a project of the U.S. U.S. Environmental Protection Agencys National Decontamination Team. Los Alamos National Laboratory leads a science and technology program supporting the EPA and the ASPECT aircraft. Casting about with a combination of airborne photography and infrared spectroscopy, the highly instrumented plane provides emergency responders on the ground with a clear concept of where danger lies, and the nature of the sometimes-invisible plumes that could otherwise kill them. ASPECT is the nations only 24/7 emergency response aircraft with chemical plume mapping capability. Bob Kroutil of Bioscience Division is the project leader, and while he said the team has put in long hours, both on the ground and in the air, its a worthwhile effort. The plane flew over 320 targeted sites in four days, he noted. Prior to the deployment to the Gulf Coast, the plane had been monitoring the Democratic National Convention in Denver, Colorado. Los Alamos National Laboratory Divisions that are supporting ASPECT include, in addition to B-Division, CTN-5: Networking Engineering and IRM-CAS: Communication, Arts, and Services. Leslie Mansell, CTN-5, and Marilyn Pruitt, IRM-CAS, were recognized the the U.S. EPA for their outstanding support to the hurricane response of Gustav in Louisiana and Ike in Texas. The information from the data collected in the most recent event, Hurricane Ike, was sent to the EPA Region 6 Rapid Needs Assessment and the State of Texas Joint Field Office in Austin, Texas. It appears that though there is considerable damage in Galveston and Texas City, there are fewer chemical leaks than during either hurricanes Katrina or Rita. Specific information gathered from the data was reported out to the U.S. Environmental Protection Agency Headquarters, the Federal Emergency Management Agency, the Department of Homeland Security, and the State of Texas Emergency Management Agency.

LANL

2009-09-01T23:59:59.000Z

371

Corrective Action Investigation Plan for Corrective Action Unit 557: Spills and Tank Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 557 is located in Areas 1, 3, 6, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada, and is comprised of the four corrective action sites (CASs) listed below: • 01-25-02, Fuel Spill • 03-02-02, Area 3 Subdock UST • 06-99-10, Tar Spills • 25-25-18, Train Maintenance Bldg 3901 Spill Site These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 3, 2008, by representatives of the Nevada Division of Environmental Protection (NDEP); U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 557. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 557 includes the following activities: • Move surface debris and/or materials, as needed, to facilitate sampling. • Conduct radiological survey at CAS 25-25-18. • Perform field screening. • Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern are present. • If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. • Collect samples of investigation-derived waste, as needed, for waste management purposes.

Alfred Wickline

2008-07-01T23:59:59.000Z

372

Non-Operational Property Evaluation for the Hanford Site River Corridor - 12409  

SciTech Connect (OSTI)

The Hanford Site River Corridor consists of the former reactor areas of the 100 Areas and the former industrial (fuel processing) area in the 300 Area. Most of the waste sites are located close to the decommissioned reactors or former industrial facilities along the Columbia River. Most of the surface area of the River Corridor consists of land with little or no subsurface infrastructure or indication of past or present releases of hazardous constituents, and is referred to as non-operational property or non-operational area. Multiple lines of evidence have been developed to assess identified fate and transport mechanisms and to evaluate the potential magnitude and significance of waste site-related contaminants in the non-operational area. Predictive modeling was used for determining the likelihood of locating waste sites and evaluating the distribution of radionuclides in soil based on available soil concentration data and aerial radiological surveys. The results of this evaluation indicated: 1) With the exception of stack emissions, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas, 2) Stack emissions that may have been associated with Hanford Site operations generally emitted short-lived and/or gaseous radionuclides, and (3) the likelihood of detecting elevated radionuclide concentrations or other waste sites in non-operational area soils is very small. The overall conclusions from the NPE evaluation of the River Corridor are: - With the exception of stack emissions to the air, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas. While pathways such as windblown dust, overland transport and biointrusion have the potential for dispersing waste site contaminants, the resulting transport is unlikely to result in substantial contamination in non-operational areas. - Stack emissions that may have been associated with Hanford Site operations generally emitted short-lived and/or gaseous radionuclides; these radionuclides either would have decayed and would be undetectable in soil, or likely would not have deposited onto Hanford Site soils. A small fraction of the total historical emissions consisted of long-lived particulate radionuclides, which could have deposited onto the soil. Soil monitoring studies conducted as part of surveillance and monitoring programs do not indicate a build-up of radionuclide concentrations in soil, which might indicate potential deposition impacts from stack emissions. Aerial radiological surveys of the Hanford Site, while effective in detecting gamma-emitting nuclides, also do not indicate deposition patterns in soil from stack emissions. - The surveillance and monitoring programs also have verified that the limited occurrence of biointrusion observed in the River Corridor has not resulted in a spread of contamination into the non-operational areas. - Monitoring of radionuclides in ambient air conducted as part of the surveillance and monitoring programs generally show a low and declining trend of detected concentrations in air. Monitoring of radionuclides in soil and vegetation correspondingly show declining trends in concentrations, particularly for nuclides with short half lives (Cs-137, Co-60 and Sr-90). - Statistical analysis of the geographical distribution of waste sites based on man -made features and topography describes the likely locations of waste sites in the River Corridor. The results from this analysis reinforce the findings from the Orphan Site Evaluation program, which has systematically identified any remaining waste sites within the River Corridor. - Statistical analysis of the distribution of radionuclide concentrations observable from aerial surveys has confirmed that the likelihood of detecting elevated radionuclide concentrations in non-operational area soils is very small; the occurrences and locations where potentially elevated concentrations may be found are discussed below. In

Lowe, John [CH2M HILL, Richland, Washington 99354 (United States); Aly, Alaa [CH2M HILL Plateau Remediation Company and INTERA Incorporated, Richland, Washington 99354 (United States)

2012-07-01T23:59:59.000Z

373

CONFIRMATORY SURVEY REPORT FOR THE SECTION 4 AREA AT THE RIO ALGOM AMBROSIA LAKE FACILITY NEW MEXICO  

SciTech Connect (OSTI)

The objectives of the confirmatory survey were to verify that remedial actions were effective in meeting established release criteria and that documentation accurately and adequately described the final radiological conditions of the RAM Ambrosia Lake, Section 4 Areas.

W.C. Adams

2010-02-12T23:59:59.000Z

374

GTRI's Nuclear and Radiological Material Removal | National Nuclear...  

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

and permanently disposing of excess, disused, unwanted, or abandoned radiological material overseas. This includes the recovery of Russian radioisotope thermoelectric...

375

E-Print Network 3.0 - arms aerial radiological Sample Search...  

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

General Diagnostic Radiology * Clinical Rotation Breast Imaging... * Clinical Rotation Pediatric Radiology * Clinical Rotation Nuclear Medicine Semester ... Source: VandeVord,...

376

E-Print Network 3.0 - anticipated radiological dose Sample Search...  

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

- thropomorphic models. II. Organ doses from computed tomographic examinations in pediatric radiology. Neuherberg... dose at CT in pediatric patients. Radiology...

377

Corrective Action Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This Corrective Action Plan has been prepared for Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO, 1996 as amended). CAU 366 consists of the following six Corrective Action Sites (CASs) located in Area 11 of the Nevada National Security Site: · CAS 11-08-01, Contaminated Waste Dump #1 · CAS 11-08-02, Contaminated Waste Dump #2 · CAS 11-23-01, Radioactively Contaminated Area A · CAS 11-23-02, Radioactively Contaminated Area B · CAS 11-23-03, Radioactively Contaminated Area C · CAS 11-23-04, Radioactively Contaminated Area D Site characterization activities were performed in 2011 and 2012, and the results are presented in Appendix A of the Corrective Action Decision Document (CADD) for CAU 366 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2012a). The following closure alternatives were recommended in the CADD: · No further action for CAS 11-23-01 · Closure in place for CASs 11-08-01, 11-08-02, 11-23-02, 11-23-03, and 11-23-04 The scope of work required to implement the recommended closure alternatives includes the following: · Non-engineered soil covers approximately 3 feet thick will be constructed at CAS 11-08-01 over contaminated waste dump (CWD) #1 and at CAS 11-08-02 over CWD #2. · FFACO use restrictions (URs) will be implemented for the areas where the total effective dose (TED) exceeds the final action level (FAL) of 25 millirems per Occasional Use Area year (mrem/OU-yr). The FAL is based on an assumption that the future use of the site includes occasional work activities and that workers will not be assigned to the area on a regular basis. A site worker under this scenario is assumed to be on site for a maximum of 80 hours per year for 5 years. The FFACO UR boundaries will encompass the areas where a worker would be exposed to 25 millirems of radioactivity per year if they are present for 80 hours per year. These boundaries will be defined as follows: – It is assumed that radiological contaminants are present at CAS 11-08-01 and CAS 11-08-02 within CWDs #1 and #2 at levels exceeding the FAL. Therefore, UR boundaries will be established around the perimeters of the soil covers that will be constructed at CWD #1 and CWD #2. A geophysical survey revealed buried metallic debris outside the fence and adjacent to CWD #1. Therefore, the UR boundary for CWD #1 will be expanded to include the mound containing buried material. – It is assumed that radiological contaminants are present at CAS 11-23-02, CAS 11-23-03, and CAS 11-23-04, within the three High Contamination Area (HCA) boundaries associated with the 11b, 11c, and 11d test areas at levels exceeding the FAL. Therefore, the UR boundaries will be established around the perimeters of the HCAs. The TED at an area of soil impacted by radiological debris outside the fence and adjacent to the 11c test area HCA exceeds the FAL of 25 mrem/OU-yr. Because the radiological impact from the debris at this location is visible on the aerial flyover radiological survey, all other areas within this isopleth of the flyover survey are conservatively also assumed to exceed the FAL. Therefore, the UR boundaries for the 11b, 11c, and 11d test areas will be expanded to include the areas within this isopleth. · The FFACO URs will all be located within the large Contamination Area (CA) that encompasses Plutonium Valley. Because access to the CA is limited and entry into the CA for post-closure inspections and maintenance would be impractical, UR warning signs will be posted along the existing CA fence. In accordance with the Soils Risk-Based Corrective Action Evaluation Process (NNSA/NSO, 2012b), an administrative UR will be implemented as a best management practice for the areas where the TED exceeds 25 millirems per Industrial Area year. This limit is based on continuous industrial use of the site and addresses exposure to industrial workers who would regularly be assigned to the work area for an entire career (250 days

none,

2013-04-30T23:59:59.000Z

378

Geophex airborne unmanned survey system  

SciTech Connect (OSTI)

The purpose of this effort is to design, construct, and evaluate a portable, remotely-piloted, airborne, geophysical survey system. This nonintrusive system will provide {open_quotes}stand-off{close_quotes} capability to conduct surveys and detect buried objects, structures, and conditions of interest at hazardous locations. This system permits two operators to rapidly conduct geophysical characterization of hazardous environmental sites. During a survey, the operators remain remote from, but within visual distance, of, the site. The sensor system never contacts the Earth, but can be positioned near the ground so that weak anomalies can be detected.

Won, I.J.; Taylor, D.W.A.

1995-03-01T23:59:59.000Z

379

Environmental Health & Safety Office of Radiological Safety  

E-Print Network [OSTI]

Environmental Health & Safety Office of Radiological Safety Page 1 of 2 FORM LU-1 Revision 01 1 safety training and submit this registration to the LSO prior to use of Class 3B or 4 lasers. A copy will be returned to the Laser Supervisor to be filed in the Laboratory Laser Safety Notebook. Both the Laser

Houston, Paul L.

380

Nuclear Engineering Catalog 2013 Radiological Concentration  

E-Print Network [OSTI]

Nuclear Engineering Catalog 2013 Radiological Concentration Fall Math 141 or 147 (4) FA, SP, SU-approved by the department. Courses in Nuclear Engineering other than 500, 502 or 598 may also be used as technical electives on academic performance. Factors considered include overall grade point average, performance in selescted

Tennessee, University of

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Nuclear Engineering Catalog 2014 Radiological Concentration  

E-Print Network [OSTI]

Nuclear Engineering Catalog 2014 Radiological Concentration Fall Math 141 or 147 (4) FA, SP, SU-approved by the department. Courses in Nuclear Engineering other than 500, 502 or 598 may also be used as technical electives. No more than four (4) credit hours of nuclear engineering courses in which a C- or lower is the highest

Grissino-Mayer, Henri D.

382

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Tuba City, Arizona. Apendix D, Site characteriztion  

SciTech Connect (OSTI)

This appendix assesses the present conditions and data for the inactive uranium mill site near Tuba City, Arizona. It consolidates available engineering, radiological, geotechnical, hydrological, meterological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill and tailings site so that the Remedial Action Contractor (RAC) may complete final designs of the remedial actions.

Not Available

1987-05-01T23:59:59.000Z

383

The Idaho National Engineering Laboratory site environmental report for calendar year 1989  

SciTech Connect (OSTI)

To verify that exposures resulting from operations at the Department of Energy (DOE) nuclear facilities have remained very small, each site at which nuclear activities are underway operates an environmental surveillance program to monitor the air, water and any other pathway where radionuclides from operations might conceivably reach workers or members of the public. This report presents data collected in 1989 for the routine environmental surveillance program conducted by the Radiological and Environmental Sciences Laboratory (RESL) of DOE and the US Geological Survey (USGS) at the Idaho National Engineering Laboratory (INEL) site. The environmental surveillance program for the INEL and vicinity for 1989 included the collection and analysis of samples from potential exposure pathways. Three basic groups of samples were collected. Those collected within the INEL boundaries will be referred to as onsite samples. Samples collected outside, but near, the Site boundaries will be referred to as boundary samples or part of a group of offsite samples. Samples collected from locations considerably beyond the Site boundaries will be referred to as distant samples or part of the offsite group. With the exception of Craters of the Moon National Monument, the distant locations are sufficiently remote from the Site to ensure that detectable radioactivity is primarily due to natural background sources or sources other than INEL operations. 35 refs., 14 figs., 13 tabs.

Hoff, D.L.; Mitchell, R.G.; Bowman, G.C.; Moore, R.

1990-06-01T23:59:59.000Z

384

Remaining Sites Verification Package for the 600-111, P-11 Critical Mass Laboratory Crib, and UPR-600-16, Fire and Contamination Spread Waste Sites, Waste Site Reclassification Form 2008-045  

SciTech Connect (OSTI)

The UPR-600-16, Fire and Contamination Spread waste site is an unplanned release that occurred on December 4, 1951, when plutonium contamination was spread by a fire that ignited inside the 120 Experimental Building. The 120 Experimental Building was a laboratory building that was constructed in 1949 and used for plutonium criticality studies as part of the P-11 Project. In November 1951, a criticality occurred in the 120 Experimental Building that resulted in extensive plutonium contamination inside the building. The confirmatory evaluation supports a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of the extensive radiological survey of the surface soil and the confirmatory and verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

J. M. Capron

2008-10-28T23:59:59.000Z

385

Nevada Test Site Environmental Report 2003  

SciTech Connect (OSTI)

The Nevada Test Site Environmental Report 2003 was prepared by Bechtel Nevada to meet the requirements and guidelines of the U.S. Department of Energy and the information needs of the public. This report is meant to be useful to members of the public, public officials, regulators, and Nevada Test Site contractors. The Executive Summary strives to present in a concise format the purpose of the document, the NTS mission and major programs, a summary of radiological releases and doses to the public resulting from site operations, a summary of non-radiological releases, and an overview of the Nevada Test Site Environmental Management System. The Executive Summary, combined with the following Compliance Summary, are written to meet all the objectives of the report and to be stand-alone sections for those who choose not to read the entire document.

Bechtel Nevada

2004-10-01T23:59:59.000Z

386

Preliminary Site Characterization Report, Rulsion Site, Colorado  

SciTech Connect (OSTI)

This report is a summary of environmental information gathered during a review of the documents pertaining to Project Rulison and interviews with personnel who worked on the project. Project Rulison was part of Operation Plowshare (a program designed to explore peaceful uses for nuclear devices). The project consisted of detonating a 43-kiloton nuclear device on September 10, 1969, in western Colorado to stimulate natural gas production. Following the detonation, a reentry well was drilled and several gas production tests were conducted. The reentry well was shut-in after the last gas production test and was held in standby condition until the general cleanup was undertaken in 1972. A final cleanup was conducted after the emplacement and testing wells were plugged in 1976. However, some surface radiologic contamination resulted from decontamination of the drilling equipment and fallout from the gas flaring during drilling operations. With the exception of the drilling effluent pond, all surface contamination at the Rulison Site was removed during the cleanup operations. All mudpits and other excavations were backfilled, and both upper and lower drilling pads were leveled and dressed. This report provides information regarding known or suspected areas of contamination, previous cleanup activities, analytical results, a review of the regulatory status, the site`s physical environment, and future recommendations for Project Ruhson. Based on this research, several potential areas of contamination have been identified. These include the drilling effluent pond and mudpits used during drilling operations. In addition, contamination could migrate in the gas horizon.

NONE

1996-08-01T23:59:59.000Z

387

Results of the independent verification survey at the Old Betatron Building, Granite City, Illinois  

SciTech Connect (OSTI)

A team from the Measurement Applications and Development Group, Oak Ridge National Laboratory (ORNL), conducted an independent verification of the radiological condition of the Old Betatron Building, Granite City, Illinois, at the request of the Department of Energy in June of 1993. The building is owned by the National Steel Corporation. The contamination present resulted from the handling of uranium slabs of metal during the time the betatron facility was used to x-ray the slabs for metallurgical defects. The designation survey did not characterize the entire floor space because of obstructing equipment and debris. Therefore, prior to remediation by Bechtel National, Incorporated (BNI), a thorough characterization of the floor was conducted, and the results were immediately conveyed to on-site staff of BNI. An independent verification assessment was also performed after the cleanup activities were performed under the direction of BNI. The process of characterization, remediation, and verification was accomplished within a five-day period. Based on results of the independent verification assessment, the Old Betatron Building was determined to meet the DOE radiological guidelines for unrestricted use.

Murray, M.E.; Brown, K.S.

1994-07-01T23:59:59.000Z

388

Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 106 is located in Area 5 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 106 comprises the five corrective action sites (CASs) listed below: •05-23-02, GMX Alpha Contaminated Area •05-23-05, Atmospheric Test Site - Able •05-45-01, Atmospheric Test Site - Hamilton •05-45-04, 306 GZ Rad Contaminated Area •05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from a weapons-effect tower test (CAS 05-45-01), a weapons-related airdrop test (CAS 05-23-05), “equation of state” experiments (CAS 05-23-02), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). Surface-deposited radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample plot locations to the dose-based final action level. The TED will be calculated as the total of separate estimates of internal and external doses. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample plot will be used to measure external radiological dose. The presence and nature of contamination from other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 106 includes the following activities: •Conduct radiological surveys. •Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. •If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where TED at the site exceeds final action levels (i.e., corrective action boundary). •Collect samples of investigation-derived waste, as needed, for waste management purposes.

Patrick Matthews

2010-04-01T23:59:59.000Z

389

Paint for detection of radiological or chemical agents  

DOE Patents [OSTI]

A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, Sumner Daniel (Danville, CA)

2010-08-24T23:59:59.000Z

390

Independent Confirmatory Survey Summary and Results for the Plum Brook Reactor Facility Sandusky OH  

SciTech Connect (OSTI)

The objectives of the confirmatory survey activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the Nuclear Regulatory Commission (NRC) in evaluating the adequacy and accuracy of the licensee’s procedures and final status survey (FSS) results.

E.N. Bailey

2008-05-06T23:59:59.000Z

391

Proposed Drill Sites  

SciTech Connect (OSTI)

Proposed drill sites for intermediate depth temperature gradient holes and/or deep resource confirmation wells. Temperature gradient contours based on shallow TG program and faults interpreted from seismic reflection survey are shown, as are two faults interpreted by seismic contractor Optim but not by Oski Energy, LLC.

Lane, Michael

2013-06-28T23:59:59.000Z

392

Proposed Drill Sites  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

Proposed drill sites for intermediate depth temperature gradient holes and/or deep resource confirmation wells. Temperature gradient contours based on shallow TG program and faults interpreted from seismic reflection survey are shown, as are two faults interpreted by seismic contractor Optim but not by Oski Energy, LLC.

Lane, Michael

393

Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit 106 comprises the four corrective action sites (CASs) listed below: • 05-20-02, Evaporation Pond • 05-23-05, Atmospheric Test Site - Able • 05-45-04, 306 GZ Rad Contaminated Area • 05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from groundwater pumping during the Radionuclide Migration study program (CAS 05-20-02), a weapons-related airdrop test (CAS 05-23-05), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). The presence and nature of contamination from surface-deposited radiological contamination from CAS 05-23-05, Atmospheric Test Site - Able, and other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) from the remaining three CASs will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 106 includes the following activities: • Conduct radiological surveys. • Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. • If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where the total effective dose at the site exceeds final action levels (i.e., corrective action boundary). • Collect samples of investigation-derived waste, as needed, for waste management purposes.

Patrick Matthews

2011-07-01T23:59:59.000Z

394

Fixation of Radiological Contamination; International Collaborative Development  

SciTech Connect (OSTI)

A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdom’s National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

Rick Demmer

2013-03-01T23:59:59.000Z

395

ORISE: Radiological Assessment and Monitoring System (RAMS)  

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

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

396

GTRI's Nuclear and Radiological Material Protection | National...  

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

at civilian sites worldwide; Provide specialized alarm response training for on-site security and local law enforcement agencies responsible for monitoring and responding to...

397

Closure Report for Corrective Action Unit 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada with ROTC 1, Revision 0  

SciTech Connect (OSTI)

This CR provides documentation and justification for the closure of CAU 118 without further corrective action. This justification is based on process knowledge and the results of the investigative and closure activities conducted in accordance with the CAU 118 SAFER Plan: Streamlined Approach for Environmental Restoration (SAFER) Plan for CAU 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada (NNSA/NSO, 2006). The SAFER Plan provides information relating to site history as well as the scope and planning of the investigation. This CR also provides the analytical and radiological survey data to confirm that the remediation goals were met as specified in the CAU 118 SAFER Plan (NNSA/NSO, 2006). The Nevada Division of Environmental Protection (NDEP) approved the CAU 118 SAFER Plan (Murphy, 2006), which recommends closure in place with use restrictions (URs).

Mark Burmeister

2007-09-01T23:59:59.000Z

398

Hazelwood Interim Storage Site environmental monitoring summary, Hazelwood, Missouri, calendar year 1984  

SciTech Connect (OSTI)

The Hazelwood Interim Storage Site (HISS) is located at 9200 Latty Avenue, Hazelwood, Missouri. The property on which the HISS is situated is owned by the Jarboe Realty and Investment Company and is leased to Futura Coatings, Inc. Radiological surveys in 1977 and 1982 indicated uranium and thorium contamination and elevated radiation levels in the soil on this property and several others in the immediate vicinity. As part of the research and development program authorized by Congress under the 1984 Energy and Water Appropriations Act, Bechtel National, Inc. (BNI) is conducting remedial action on-site and at the vicinity properties. The work is being performed as part of the US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). Jarboe Realty and Investment Company has agreed to permit DOE to store contaminated material from the FY 1984 and 1985 Latty Avenue cleanup on its property. The contaminated material will be added to the existing pile created during the earlier site cleanup. The pile will then be covered to prevent erosion or migration of contamination. The property will be maintained as the HISS by DOE until final disposition for these materials is determined. BNI is conducting a surveillance monitoring program at the HISS during the interim storage period to detect potential migration of contaminants from the storage pile via air, water, and sediment. This summary provides these monitoring data for calendar year 1984. 6 refs., 4 tabs.

Not Available

1985-07-01T23:59:59.000Z

399

2013 Environmental/Radiological Assistance Directory (ERAD) Presentations  

Broader source: Energy.gov [DOE]

November 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site May 2013 THE MARSAME METHODOLOGY Fundamentals, Benefits, and Applications March 2013 Working to Keep our Shipments Safe, Secure and Economical ANL Facility Decommissioning Training Program January 2013 DOE Corporate Operating Experience Program Radiological Reporting Annual Site Environmental Reports (ASERs) & HSS Environmental and Radiation Protection Performance Dashboards November 2012 Environmental Measurements in an Emergency: This is not a Drill! BGRR D&D Presentation for the DOE ERAD Working Group September 2012 Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Clearance of Real and Personal Property Under DOE Radiation Protection Directive DOE Order 458.1 June 2012 RESRAD Codes for ERAD June 27, 2012 Florida International University (FIU) D&D Knowledge Management Information Tool, June 27, 2012 May 2012 Integrated Cloud Based Environmental Data Management System DOE Order 458.1, Radiation Protection of the Public and the Environment

400

Analysis of concentrating PV-T systems for the commercial/industrial sector. Volume II. PV-T state-of-the-art survey and site/application pair selection and analysis  

SciTech Connect (OSTI)

As part of a project to develop feasibility assessments, design procedures, and reference designs for total energy systems that could use actively cooled concentrating photovoltaic collectors, a survey was conducted to provide an overview of available photovoltaic-thermal (PV-T) technology. General issues associated with the design and installation of a PV-T system are identified. Electrical and thermal efficiencies for the line-focus Fresnel, the linear parabolic trough, and the point-focus Fresnel collectors are specified as a function of operating temperature, ambient temperature, and insolation. For current PV-T technologies, the line-focus Fresnel collector proved to have the highest thermal and electrical efficiencies, lowest array cost, and lowest land area requirement. But a separate feasibility analysis involving 11 site/application pairs showed that for most applications, the cost of the photovoltaic portion of a PV-T system is not recovered through the displacement of an electrical load, and use of a thermal-only system to displace the thermal load would be a more economical alternative. PV-T systems are not feasible for applications that have a small thermal load, a large steam requirement, or a high load return temperature. SAND82-7157/3 identifies the technical issues involved in designing a photovoltaic-thermal system and provides guidance for resolving such issues. Detailed PV-T system designs for three selected applications and the results of a trade-off study for these applications are presented in SAND82-7157/4. A summary of the major results of this entire study and conclusions concerning PV-T systems and applications is presented in SAND82-7157/1.

Schwinkendorf, W.E.

1984-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Nevada Test Site Environmental Report 2007  

SciTech Connect (OSTI)

The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report.

Cathy Wills

2008-09-01T23:59:59.000Z

402

Weld Repair of a Stamped Pressure Vessel in a Radiologically Controlled Zone  

SciTech Connect (OSTI)

In September 2012 an ASME B&PVC Section VIII stamped pressure vessel located at the DOE Hanford Site Effluent Treatment Facility (ETF) developed a through-wall leak. The vessel, a steam/brine heat exchanger, operated in a radiologically controlled zone (by the CH2MHill PRC or CHPRC), had been in service for approximately 17 years. The heat exchanger is part of a single train evaporator process and its failure caused the entire system to be shut down, significantly impacting facility operations. This paper describes the activities associated with failure characterization, technical decision making/planning for repair by welding, logistical challenges associated with performing work in a radiologically controlled zone, performing the repair, and administrative considerations related to ASME code requirements.

Cannell, Gary L. [Fluor Enterprises, Inc.; Huth, Ralph J. [CH2MHill Plateau Remediation Company; Hallum, Randall T. [Fluor Government Group

2013-08-26T23:59:59.000Z

403

Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations  

SciTech Connect (OSTI)

The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

NSTec Aerial Measurement Systems

2012-07-31T23:59:59.000Z

404

Radiological and Nuclear Security in A Global Context  

E-Print Network [OSTI]

This paper considers the state of nuclear and radiological security in the UK and abroad and reports on the methods that could be employed by terrorists with radiological or nuclear material to cause destruction. It is shown that despite current safeguards that problems arise due to materials that are unaccounted for and poor implementation of detection regimes in some geographical regions. The prospect of a future terrorist event that involves nuclear or radiological materials seems likely despite best efforts of prevention.

Jones, Nick

2010-01-01T23:59:59.000Z

405

Site Feeds - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled System OutagesNewsMaterialsX-rayOur‹Simulation,Site

406

Site Screening, Site Selection,  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administrationcontroller systemsBi (2)Sharing Smartversatileplatform chemical.OfficeScreening, Site

407

Rev. 04/2014: JAB Environmental and Radiological Health Sciences  

E-Print Network [OSTI]

Rev. 04/2014: JAB Environmental and Radiological Health Sciences Academic Policies, Guidelines....................................................................................................................... 3 Plan A Master of Science Program......................................................................................... 3 Plan B Master of Science Program

408

CRAD, Radiological Controls - Oak Ridge National Laboratory High...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C...

409

Model Annex for Preparedness and Response to Radiological Transportati...  

Office of Environmental Management (EM)

Response to Radiological Transportation Incidents.docx More Documents & Publications TEPP Model Needs Assessment Document First Responder Initial Response Procedure Hazardous...

410

Savannah River Site environmental report for 1993 summary pamphlet  

SciTech Connect (OSTI)

This pamphlet summarizes the impact of 1993 Savannah River Site operations on the environment and the off-site public. It includes an overview of site operations; the basis for radiological and nonradiological monitoring; 1993 radiological releases and the resulting dose to the off-site population; and results of the 1993 nonradiological program. The Savannah River Site Environmental Report for 1993 describes the findings of the environmental monitoring program for 1993. The report contains detailed information about site operations,the environmental monitoring and surveillance programs, monitoring and surveillance results, environmental compliance activities, and special programs. The report is distributed to government officials, members of the US Congress, universities, government facilities, environmental and civic groups, the news media, and interested individuals.

Karapatakis, L.

1994-05-01T23:59:59.000Z

411

Corrective Action Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility Nevada Test Site, Nevada  

SciTech Connect (OSTI)

The Area 25 Reactor Maintenance, Assembly, and Disassembly Decontamination Facility is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Unit (CAU) 254. CAU 254 is located in Area 25 of the Nevada Test Site and consists of a single Corrective Action Site CAS 25-23-06. CAU 254 will be closed, in accordance with the FFACO of 1996. CAU 254 was used primarily to perform radiological decontamination and consists of Building 3126, two outdoor decontamination pads, and surrounding soil within an existing perimeter fence. The site was used to decontaminate nuclear rocket test-car hardware and tooling from the early 1960s through the early 1970s, and to decontaminate a military tank in the early 1980s. The site characterization results indicate that, in places, the surficial soil and building materials exceed clean-up criteria for organic compounds, metals, and radionuclides. Closure activities are expected to generate waste streams consisting of nonhazardous construction waste. petroleum hydrocarbon waste, hazardous waste, low-level radioactive waste, and mixed waste. Some of the wastes exceed land disposal restriction limits and will require off-site treatment before disposal. The recommended corrective action was revised to Alternative 3- ''Unrestricted Release Decontamination, Verification Survey, and Dismantle Building 3126,'' in an addendum to the Correction Action Decision Document.

C. M. Obi

2000-12-01T23:59:59.000Z

412

Nonintrusive subsurface surveying capability  

SciTech Connect (OSTI)

This presentation describes the capabilities of a ground-pentrating radar (GPR) system developed by EG&G Energy Measurements (EM), a prime contractor to the Department of Energy (DOE). The focus of the presentation will be on the subsurface survey of DOE site TA-21 in Los Alamos, New Mexico. EG&G EM developed the system for the Department of Defense. The system is owned by the Department of the Army and currently resides at KO in Albuquerque. EM is pursuing efforts to transfer this technology to environmental applications such as waste-site characterization with DOE encouragement. The Army has already granted permission to use the system for the waste-site characterization activities.

Tunnell, T.W.; Cave, S.P.

1994-06-01T23:59:59.000Z

413

Radiological hazards of alpha-contaminated waste  

SciTech Connect (OSTI)

The radiological hazards of alpha-contaminated wastes are discussed in this overview in terms of two components of hazard: radiobiological hazard, and radioecological hazard. Radiobiological hazard refers to human uptake of alpha-emitters by inhalation and ingestion, and the resultant dose to critical organs of the body. Radioecological hazard refers to the processes of release from buried wastes, transport in the environment, and translocation to man through the food chain. Besides detailing the sources and magnitude of hazards, this brief review identifies the uncertainties in their estimation, and implications for the regulatory process.

Rodgers, J.C.

1982-01-01T23:59:59.000Z

414

Radiological Threat Reduction | ornl.gov  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, and 323Program AccomplishmentsScienceRadiological

415

Brookhaven National Laboratory site environmental report for calendar year 1996  

SciTech Connect (OSTI)

This report documents the results of the Environmental Monitoring Program at Brookhaven National Laboratory and summarizes information about environmental compliance for 1996. To evaluate the effect of Brookhaven National Laboratory`s operations on the local environment, measurements of direct radiation, and of a variety of radionuclides and chemical compounds in the ambient air, soil, sewage effluent, surface water, groundwater, fauna, and vegetation were made at the Brookhaven National Laboratory site and at adjacent sites. The report also evaluates the Laboratory`s compliance with all applicable guides, standards, and limits for radiological and non-radiological emissions and effluents to the environment.

Schroeder, G.L.; Paquette, D.E.; Naidu, J.R.; Lee, R.J.; Briggs, S.L.K.

1998-01-01T23:59:59.000Z

416

Corrective Action Investigation Plan for Corrective Action Unit 370: T-4 Atmospheric Test Site, Nevada Test Site, Nevada with ROTC-1, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 370 is located in Area 4 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 370 is comprised of Corrective Action Site (CAS) 04-23-01, Atmospheric Test Site T-4. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and/or implement a corrective action. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for this CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The investigation results may also be used to evaluate improvements in the Soils Project strategy to be implemented. The site will be investigated based on the data quality objectives (DQOs) developed on December 10, 2007, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Desert Research Institute; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 370. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to the CAS. The scope of the CAI for CAU 370 includes the following activities: • Move surface debris and/or materials, as needed, to facilitate sampling. • Conduct radiological surveys. • Perform field screening. • Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern are present. • If contaminants of concern are present, collect samples to define the extent of the contamination. • Collect samples of investigation-derived waste including debris deemed to be potential source material, as needed, for waste management purposes.

Pat Matthews

2008-04-01T23:59:59.000Z

417

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado  

SciTech Connect (OSTI)

This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

Not Available

1992-02-01T23:59:59.000Z

418

Nuclear and Radiological Forensics and Attribution Overview  

SciTech Connect (OSTI)

The goal of the U.S. Department of Homeland Security (DHS) Nuclear and Radiological Forensics and Attribution Program is to develop the technical capability for the nation to rapidly, accurately, and credibly attribute the origins and pathways of interdicted or collected materials, intact nuclear devices, and radiological dispersal devices. A robust attribution capability contributes to threat assessment, prevention, and deterrence of nuclear terrorism; it also supports the Federal Bureau of Investigation (FBI) in its investigative mission to prevent and respond to nuclear terrorism. Development of the capability involves two major elements: (1) the ability to collect evidence and make forensic measurements, and (2) the ability to interpret the forensic data. The Program leverages the existing capability throughout the U.S. Department of Energy (DOE) national laboratory complex in a way that meets the requirements of the FBI and other government users. At the same time the capability is being developed, the Program also conducts investigations for a variety of sponsors using the current capability. The combination of operations and R&D in one program helps to ensure a strong linkage between the needs of the user community and the scientific development.

Smith, D K; Niemeyer, S

2005-11-04T23:59:59.000Z

419

Closure Report for Corrective Action Unit 566: EMAD Compound, Nevada National Security Site, Nevada with ROTC-1, Revision 0  

SciTech Connect (OSTI)

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 566: EMAD Compound, Nevada National Security Site, Nevada. Corrective Action Unit 566 comprises Corrective Action Site (CAS) 25-99-20, EMAD Compound, located within Area 25 of the Nevada National Security Site. The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CAU 566 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 566 issued by the Nevada Division of Environmental Protection. From October 2010 through May 2011, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 566: EMAD Compound, Nevada National Security Site, Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels (FALs) to determine COCs for CAU 566. Assessment of the data from collected soil samples, and from radiological and visual surveys of the site, indicates the FALs were exceeded for polychlorinated biphenyls (PCBs), semivolatile organic compounds (SVOCs), and radioactivity. Corrective actions were implemented to remove the following: • Radiologically contaminated soil assumed greater than FAL at two locations • Radiologically contaminated soil assumed greater than FAL with lead shot • PCB-contaminated soil • Radiologically contaminated filters and equipment • Fuels, lubricants, engine coolants, and oils • Lead debris • Electrical and lighting components assumed to be potential source materials, including - fluorescent light bulbs - mercury switches (thermostats) - circuit boards - PCB-containing ballasts Closure of CAU 566 was achieved through a combination of removal activities and closure in place. Corrective actions to remove COCs, and known and assumed potential source materials, were implemented as was practical. The PCBs remaining at the site are bounded laterally, but not vertically, within CAS 25-99-20 based upon step-out sampling; the sources (e.g., PCB transformer oils, diesel fuel from locomotive reservoirs) have been removed; the practice of the application of PCB-containing oils for soil stabilization has ceased; and the COCs are not readily mobile in the environment. Closure in place is necessary, and future land use of the site will be restricted from intrusive activities. This will effectively eliminate inadvertent contact by humans with the contaminated media. The DOE, National Nuclear Security Administration Nevada Site Office, provides the following recommendations: • No further corrective action is required at CAS 25-99-20. • Closure in place of CAS 25-99-20. • A use restriction is required at CAU 566. • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 566. • Corrective Action Unit 566 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

Mark Krauss

2011-06-01T23:59:59.000Z

420

FINAL REPORT FOR INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE HEMATITE DECOMMISSIONING PROJECT, FESTUS, MISSOURI  

SciTech Connect (OSTI)

ORAU conducted confirmatory surveys of the Hematite site during the period of June 12 through June 13, 2012. The survey activities included in-process inspections, document review, walkover surveys, sampling activities, and laboratory analysis of split samples. WEC was forthcoming with information relating to practices, procedures, and surface scan results. Scans performed by the WEC technician were extremely thorough and methodical. The WEC and ORAU technicians identified the same areas of elevated activity with comparable detector responses. WEC sampling of re-use soils, waste soils, sediments, and groundwater were conducted under ORAU observation. The sampling efforts observed by ORAU were performed in accordance with site-specific procedures and in a manner sufficient to provide quality supporting data. Three observations were made during groundwater sampling activities. First, the water level indicator was re-used without submitting rinse blank. Second, bubbles created during tubing extraction could indicate the presence of volatilized organic compounds. Third, samplers did not use a photo ionization detector prior to sample collection to indicate the presence of volatile organic vapors. Results of split samples indicated a high level of comparability between the WEC and ORAU/ORISE radiological laboratories. Analytical practices and procedures appear to be sufficient in providing quality radiochemical data. All concentrations from the Soil Re-Use Area and sediment samples are below Uniform radionuclide-specific derived concentration guideline level (DCGL{sub W}) limits; thus, comparisons to the less conservative stratified geometry were not required. Results were compared to individual DCGLs and using the sum of fractions approach. Both composite soil samples collected from the Waste Handling Area (Bins 1 and 4) were well below the prescribed USEI waste acceptance criteria.

Bailey, Erika N.; Lee, Jason D.

2012-09-21T23:59:59.000Z

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

THE RABIT: A RAPID AUTOMATED BIODOSIMETRY TOOL FOR RADIOLOGICAL TRIAGE  

E-Print Network [OSTI]

. Health Phys. 98(2):209­217; 2010 Key words: biological indicators; dosimetry; blood; cytogenetics-priority need in an environment of heightened concern over possible radiological or nuclear terrorist attacks of radiological injuries. A small improvised nuclear device (IND) would produce a major health emergency

422

Current Trends in Gamma Ray Detection for Radiological Emergency Response  

SciTech Connect (OSTI)

Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies.

Mukhopadhyay, S., Guss, P., Maurer, R.

2011-08-18T23:59:59.000Z

423

FRMAC Interactions During a Radiological or Nuclear Event  

SciTech Connect (OSTI)

During a radiological or nuclear event of national significance the Federal Radiological Emergency Monitoring and Assessment Center (FRMAC) assists federal, state, tribal, and local authorities by providing timely, high-quality predictions, measurements, analyses and assessments to promote efficient and effective emergency response for protection of the public and the environment from the consequences of such an event.

Wong, C T

2011-01-27T23:59:59.000Z

424

Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering  

E-Print Network [OSTI]

Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering University of Illinois at Urbana-Champaign The Department of Nuclear, Plasma, and Radiological Engineering-qualified candidates with background in areas related to reactor power engineering and other nuclear applications

Ma, Yi

425

healthcare.utah.edu/radiology What is Nuclear Medicine?  

E-Print Network [OSTI]

expensive diagnostic tests or surgery. Tissues such as intestines, muscles, and blood vessels are difficulthealthcare.utah.edu/radiology Radiology What is Nuclear Medicine? Nuclear Medicine is a specialized to visualize on a standard X-ray. In Nuclear Medicine, a radioactive tracer is used so the tissue is seen more

Feschotte, Cedric

426

Corrective Action Investigation Plan for Corrective Action Unit 565: Stored Samples, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 565 is located in Area 26 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 565 is comprised of one corrective action site (CAS) listed--CAS 26-99-04, Ground Zero Soil Samples. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend closure of CAU 565. Additional information will be obtained by conducting a corrective action investigation before evaluating closure objectives and selecting the appropriate corrective action. The results of the field investigation will support closure and waste management decisions that will be presented in the Corrective Action Decision Document/Closure Report. The site will be investigated based on the data quality objectives (DQOs) developed on June 1, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was utilized to identify and define the type, amount, and quality of data needed to develop and evaluate closure for CAU 565. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to this CAS. The scope of the corrective action investigation for CAU 565 includes the following activities: (1) Remove stored samples, shelves, and debris from the interior of Building 26-2106. (2) Perform field screening on stored samples, shelves, and debris. (3) Dispose of stored samples, shelves, and debris. (4) Collect samples of investigation-derived waste, as needed, for waste management purposes. (5) Conduct radiological surveys of Building 26-2106 in accordance with the requirements in the ''NV/YMP Radiological Control Manual'' to determine if there is residual radiological contamination that would prevent the release of the building for unrestricted use. This Corrective Action Investigation has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

Wickline, Alfred; McCall, Robert

2006-08-01T23:59:59.000Z

427

Facility Approvals, Security Surveys, and Nuclear Materials Surveys  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish the Department of Energy (DOE) requirements for granting facility approvals prior to permitting safeguards and security interests on the premises and the conduct of on-site security and/or nuclear material surveys of facilities with safeguards and security interests. Cancels DOE O 5630.7 and DOE O 5634.1. Canceled by DOE 5634.1B.

1988-02-03T23:59:59.000Z

428

Direct-Current Resistivity Survey At Lightning Dock Area (Warpinski...  

Open Energy Info (EERE)

Survey Activity Date Usefulness not indicated DOE-funding Unknown Notes As a foundation for successful siting and drilling a deep test well, additional geophysical work has...

429

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

NM; RAP Region 4 Chicago, IL; RAP Region 5 Idaho Falls, ID; RAP Region 6 Oakland, CA; RAP Region 7 Richland, WA; RAP Region 8 RAP team members surveying vehicles Each region...