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1

An aerial radiological survey of the Nevada Test Site  

SciTech Connect

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

Aerial radiological surveys of Steed Pond, Savannah River Site: Dates of surveys, 1984--1989  

SciTech Connect

From June 1984 to August 1985, three aerial radiological surveys were conducted over Steed Pond at the Savannah River Site in South Carolina. In addition, Steed Pond was included in larger-area surveys of the Savannah River Site in subsequent years. The surveys were conducted by the Remote Sensing Laboratory of EG&G Energy Measurements, Inc., Las Vegas, Nevada, for the US Department of Energy. Airborne measurements were obtained for both natural and man-made gamma radiation over Steed Pond and surrounding areas. The first survey was conducted when the pond was filled to normal capacity for the time of the year. On September 1, 1984, the Steed Pond dam spillway failed causing the pond to drain. The four subsequent surveys were conducted with the pond drained. The second survey and the third were conducted to study silt deposits exposed by the drop in water level after the spillway`s opening. Steed Pond data from the February 1987 and April 1989 Savannah River Site surveys have been included to bring this study up to date.

Fritzsche, A.E.; Jobst, J.E.

1993-09-01T23:59:59.000Z

3

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

Office of Legacy Management (LM)

COT"IPREITENS IVE RADIOLOGICAL COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE LEWISTON, NEW YORK Prepared for U.S. DePartment of EnergY as part of the Formerly Utilized Sites - Remedial ActLon Program J . D . B e r g e r P r o j e c t S t a f f J. Burden* w.L. Smlth* R.D. Condra T.J. Sowell J.S . Epler* G.M. S tePhens P.Iil. Frame L.B. Taus* W . 0 . H e l t o n C . F . W e a v e r R . C . G o s s l e e B . S . Z a c h a r e k d I I Prepared bY Radiological Slte Assessoent Progran Manpower Educailon Research, and Training Dlvision Oak Ridge Assoclated Universlties Oak Ridge, Tennessee 3783f-0117 I FINAL REPORT March 1984 Thts report ls based on work performed under contract number DE-AC05-760R00033 wiLh the DePartment of EnergY. *Evaluatlon Research Corporatlon, Oak Ridge, Tennessee TABLE OF CONTENTS L i s t o f F i g u

4

PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE  

Office of Legacy Management (LM)

pJ y, 22/4 pJ y, 22/4 PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE (ARCHER-DANIELS MIOLANO COMPANY) AT PORT RICHMOND, NEW YORK ./ Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 . . ' October 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Former1 y Uti 1 i ted Sites-- Remedial Action Program PRELIMINARY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLANI I WAREHOUSE SITE (ARCHER-OANIELS MIDLAND COMPANY) AT PORT RICHMOND, NEW YORK B. A. Berven and C. Clark Introduction A number of buildings located at the site of the former Staten Island Warehouse in Port Richmond, New York, were used by Union Minie're

5

I COMPREHENSIVE RADIOLOGICAL SURVEY I  

Office of Legacy Management (LM)

im im I COMPREHENSIVE RADIOLOGICAL SURVEY I Prepared by Oak Ridge Associated Universities Prprd* OFF-SITE PROPERTY H' | Prepared for Office of Operational FORMER LAKE ONTARIO ORDNANCE WORKS SITE Safety U.S. Department LEWISTON, NEW YORK I of Energy i J.D. BERGER i Radiological Site Assessment Program Manpower Education, Research, and Training Division I l*~~~~~~ ~~~~DRAFT REPORT January 1983 I I I ------- COMPREHENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY H' FORMER LAKE ONTARIO ORDNANCE WORKS SITE LEWISTON, NEW YORK Prepared for U.S. Department of Energy as part of the Formerly Utilized Sites -- Remedial Action Program J. D. Berger Project Staff L.W. Cole W.O. Helton R.D. Condra T.J. Sowell P.R. Cotten C.F. Weaver G.R. Foltz T.S. Yoo R.C. Gosslee Prepared by Radiological Site Assessment Program

6

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

SciTech Connect

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

7

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

SciTech Connect

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

8

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

SciTech Connect

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

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

SciTech Connect

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

10

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

SciTech Connect

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

11

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

SciTech Connect

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

12

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

SciTech Connect

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

13

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

14

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

SciTech Connect

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

15

Nevada Test Site Radiological Control Manual  

SciTech Connect

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

16

A mobile autonomous robot for radiological surveys  

SciTech Connect

The Robotics Development Group at the Savannah River Site is developing an autonomous robot (SIMON) to perform radiological surveys of potentially contaminated floors. The robot scans floors at a speed of one-inch/second and stops, sounds an alarm, and flashes lights when contamination in a certain area is detected. The contamination of interest here is primarily alpha and beta-gamma. The robot, a Cybermotion K2A base, is radio controlled, uses dead reckoning to determine vehicle position, and docks with a charging station to replenish its batteries and calibrate its position. It uses an ultrasonic ranging system for collision avoidance. In addition, two safety bumpers located in the front and the back of the robot will stop the robots motion when they are depressed. Paths for the robot are preprogrammed and the robots motion can be monitored on a remote screen which shows a graphical map of the environment. The radiation instrument being used is an Eberline RM22A monitor. This monitor is microcomputer based with a serial I/0 interface for remote operation. Up to 30 detectors may be configured with the RM22A.

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

1992-01-01T23:59:59.000Z

17

A mobile autonomous robot for radiological surveys  

SciTech Connect

The Robotics Development Group at the Savannah River Site is developing an autonomous robot (SIMON) to perform radiological surveys of potentially contaminated floors. The robot scans floors at a speed of one-inch/second and stops, sounds an alarm, and flashes lights when contamination in a certain area is detected. The contamination of interest here is primarily alpha and beta-gamma. The robot, a Cybermotion K2A base, is radio controlled, uses dead reckoning to determine vehicle position, and docks with a charging station to replenish its batteries and calibrate its position. It uses an ultrasonic ranging system for collision avoidance. In addition, two safety bumpers located in the front and the back of the robot will stop the robots motion when they are depressed. Paths for the robot are preprogrammed and the robots motion can be monitored on a remote screen which shows a graphical map of the environment. The radiation instrument being used is an Eberline RM22A monitor. This monitor is microcomputer based with a serial I/0 interface for remote operation. Up to 30 detectors may be configured with the RM22A.

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

1992-10-01T23:59:59.000Z

18

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

SciTech Connect

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

19

Nevada National Security Site Radiological Control Manual  

SciTech Connect

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

20

Survey of radiologic practices among dental practitioners  

SciTech Connect

The purpose of this study was to determine the factors that influence and contribute to patient exposure in radiologic procedures performed in the offices of 132 staff members within the dental department of a teaching hospital. A questionnaire was prepared in which data were requested on brands of film used, type of x-ray unit used, processing, and use of leaded apron, cervical shield, and film holder. Offices were also visited to evaluate performance of existing dental x-ray equipment. Both the Dental Radiographic Normalizing and Monitoring Device and the Dental Quality Control Test Tool were evaluated. The average exposure was equivalent to the class D film (220 mR), but only 13% of those surveyed used the faster class E film, which would reduce patient exposure in half. The survey indicates that dentists are not using the newer low-exposure class E film in their practices.

Goren, A.D.; Sciubba, J.J.; Friedman, R.; Malamud, H. (Long Island Jewish Medical Center, New Hyde Park, NY (USA))

1989-04-01T23:59:59.000Z

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.


21

Solar Site Survey Toolkit  

Energy.gov (U.S. Department of Energy (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.

22

Autonomous mobile robot for radiologic surveys  

SciTech Connect

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

23

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

SciTech Connect

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

24

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

25

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

SciTech Connect

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

26

The Northern Marshall Islands radiological survey: Data and dose assessments  

SciTech Connect

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

27

Nevada Test Site Radiological Control Manual  

SciTech Connect

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

28

RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO, ILLINOIS  

Office of Legacy Management (LM)

RADIOLOGICAL SURVEY RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO, ILLINOIS Prepared by M.R. LANDIS Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. Berger R.C. Gosslee E.A. Powell G.R. Foltz M.J. Laudeman A. Wallo* C.F. Weaver Prepared for U.S. Department of Energy as part of the Formerly Utilized Sites - Remedial Action Program FINAL REPORT OCTOBER 1989 This report is based on work performed under contract number DE-AC05-760RC0033 with the U.S. Department of Energy. *with the U.S. Department of Energy, Division of Facility and Site Decommissioning -- LIST OF FIGURES Page FIGURE 1: Map of Chicago, Illinois Indicating the Location of the Facility at

29

Radiological Survey Data for 38 Grove Avenue, Rochelle Park,...  

Office of Legacy Management (LM)

K e l l e r , D i r e c t o r T e c h n i c a l S e r v i c e s D i v i s i o n 0ak Ridge Operations 0ffice The radiological survey data for the subject vicinity property has been...

30

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

SciTech Connect

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

31

ORISE: Multi-Agency Radiation Survey and Site Investigation Manual  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Investigation Manual (MARSSIM) Site Investigation Manual (MARSSIM) As greater attention is being directed toward the decontamination and decommissioning (D&D) of nuclear facilities, the need for a standardized approach for implementing the necessary radiological surveys has become increasingly important. A multi-agency committee representing the U.S. Department of Defense (DOD), U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), and U.S. Nuclear Regulatory Commission (NRC) has addressed this need by producing a guidance document known as the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). Published in December 1997, MARSSIM provides detailed guidance for planning, implementing and evaluating environmental and facility radiological surveys to demonstrate compliance with a dose- or risk-based

32

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

Office of Legacy Management (LM)

A" 917 A" 917 RADIOLOGICAL SURVEY OF A PORTION OF PROPERTY OWNED BY MODERN LANDFILL, INC. - FORMER LOOW SITE Summary Report Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1981 OAK RIDGE NATIONAL LABORATORY operated by UNION. CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program CONTENTS Page LIST OF FIGURES .. .. . .. . . . . . . . ......... iii LIST OF TABLES ......... .. iv INTRODUCTION .. ......... 1 OBJECTIVE .................... 1 SURVEY TECHNIQUES . . ............. ...... 1 RESULTS ..... 2 Gamma-Ray Exposure Rates . . . . . . 2 Beta-Gamma Dose Rate ............. 2 226Ra in Soil ............ 3 CONCLUSIONS .. . . . . . . . . . . . .. .. . .. .. 3 REFERENCES . . . . . . . . .

33

I RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES  

Office of Legacy Management (LM)

-I a.d *4dk *-f--l- -I a.d *4dk *-f--l- --- I. ,e-- - .- --_ -- -. ;,. -* " . I . RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES (Unit XII and W a rehouse) DAYTON, OHIO Report Date: 4 September 1997 Survey Dak 27 Aitgust 1991 Prepared by: Mark L. Mays, Chief Radiation Safety Branch Sponsored by: M iamisburg Environmental Matigement Reject Office Ohio FTekl Ofice U.S.. Department of Energy Conducted by: %diation Safety Branch Of&e of Environmental Management ggtb Air Base W ing U.S. Departmtnt of the Air Force In Cooperation W ith: Southwest District Office Ohio Environmental Protection Agency - O h io Cnvironmwhl Protection Agenty Bureau of Radiological Health Ohio Department of Health. I Lb ^U .L*-u i-.-r- --- , .., II ,.--(_ ~_ -_- --- -_ _.. ;

34

An aerial radiological survey of the Pilgrim Station Nuclear Power Plant and surrounding area, Plymouth, Massachusetts  

SciTech Connect

Terrestrial radioactivity surrounding the Pilgrim Station Nuclear Power Plant was measured using aerial radiolog- ical survey techniques. The purpose of this survey was to document exposure rates near the plant and to identify unexpected, man-made radiation sources within the survey area. The surveyed area included land areas within a three-mile radius of the plant site. Data were acquired using an airborne detection system that employs sodium iodide, thallium-activated detectors. Exposure rate and photopeak counts were computed from these data and plotted on aerial photographs of the survey area. Several ground-based exposure measurements were made for comparison with the,aerial survey results. Exposure rates in areas surrounding the plant site varied from 6 to 10 microroentgens per hour, with exposure rates below 6 microroentgens per hour occurring over bogs and marshy areas. Man-made radiation was found to be higher than background levels at the plant site. Radation due to nitrogen-1 6, which is produced in the steam cycle of a boiling-water reactor, was the primaty source of activity found at the plant site. Cesium-137 activity at levels slightly above those expected from natural fallout was found at isolated locations inland from the plant site. No other detectable sources of man-made radioactivity were found.

Proctor, A.E.

1997-06-01T23:59:59.000Z

35

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

36

Northern Marshall Islands radiological survey: sampling and analysis summary  

SciTech Connect

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

37

RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY  

Office of Legacy Management (LM)

SURVEY SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY ITHACA, NEW YORK T. J. VITKUS AND J. L. PAYNE Prepared for the Office of Erivironmental Restoration U.S.' Department of Energy ORISE 95/K-1 3 RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY ITHACA, NEW YORK Prepared by T. J. Vi&us and J. L. Payne Environme& Survey and Site Assessment Program Envirotiental and Health Sciences Group Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for the U.S. Department of Energy Offke of Environmental Restoration FINAL REPORT OCTOBER 1995 This report is based on work performed under contract number DE-AC05-760R00033 with the U.S. Department of Energy. .I I I I I I I I 1 I I I ' I

38

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

SciTech Connect

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

39

Depleted uranium residual radiological risk assessment for Kosovo sites  

Science Journals Connector (OSTI)

During the recent conflict in Yugoslavia, depleted uranium rounds were employed and were left in the battlefield. Health concern is related to the risk arising from contamination of areas in Kosovo with depleted uranium penetrators and dust. Although chemical toxicity is the most significant health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict. Uranium munitions are considered to be a source of radiological contamination of the environment. Based on measurements and estimates from the recent Balkan Task Force UNEP mission in Kosovo, we have estimated effective doses to resident populations using a well-established food-web mathematical model (RESRAD code). The UNEP mission did not find any evidence of widespread contamination in Kosovo. Rather than the actual measurements, we elected to use a desk assessment scenario (Reference Case) proposed by the UNEP group as the source term for computer simulations. Specific applications to two Kosovo sites (Planeja village and Vranovac hill) are described. Results of the simulations suggest that radiation doses from water-independent pathways are negligible (annual doses below 30 ?Sv). A small radiological risk is expected from contamination of the groundwater in conditions of effective leaching and low distribution coefficient of uranium metal. Under the assumptions of the Reference Case, significant radiological doses (>1 mSv/year) might be achieved after many years from the conflict through water-dependent pathways. Even in this worst-case scenario, DU radiological risk would be far overshadowed by its chemical toxicity.

Marco Durante; Mariagabriella Pugliese

2003-01-01T23:59:59.000Z

40

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

SciTech Connect

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

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

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

SciTech Connect

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

42

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

SciTech Connect

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

43

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

SciTech Connect

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

44

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

SciTech Connect

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

45

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

SciTech Connect

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

46

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

SciTech Connect

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

47

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

SciTech Connect

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

48

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

SciTech Connect

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

49

Off-site consequences of radiological accidents: methods, costs and schedules for decontamination  

SciTech Connect

This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs.

Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

1985-08-01T23:59:59.000Z

50

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

SciTech Connect

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

51

Uncertainty analyses for radiological assessments of St. Louis FUSRAP Sites  

SciTech Connect

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

52

An Aerial Radiological Survey of Selected Areas of the City of North Las Vegas  

SciTech Connect

As part of the proficiency training for the Radiological Mapping mission of the Aerial Measuring System (AMS), a survey team from the Remote Sensing Laboratory-Nellis (RSL-Nellis) conducted an aerial radiological survey of selected areas of the city of North Las Vegas for the purpose of mapping natural radiation background and locating any man-made radioactive sources. Survey areas were selected in collaboration with the City Manager's office and included four separate areas: (1) Las Vegas Motor Speedway (10.6 square miles); (2) North Las Vegas Downtown Area (9.2 square miles); (3) I-15 Industrial Corridor (7.4 square miles); and (4) Future site of University of Nevada Las Vegas campus (17.4 square miles). The survey was conducted in three phases: Phase 1 on December 11-12, 2007 (Areas 1 and 2), Phase 2 on February 28, 2008 (Area 3), and Phase 3 on March 19, 2008 (Area 4). The total completed survey covered a total of 44.6 square miles. The flight lines (without the turns) over the surveyed areas are presented in Figures 1, 2, 3, and 4. A total of eight 2.5-hour-long flights were performed at an altitude of 150 ft above ground level (AGL) with 300 feet of flight-line spacing. Water line and test line flights were conducted over the Lake Mead and Government Wash areas to ensure quality control of the data. The data were collected by the AMS data acquisition system (REDAR V) using an array of twelve 2-inch x 4-inch x 16-inch sodium iodide (NaI) detectors flown on-board a twin-engine Bell 412 helicopter. Data, in the form of gamma energy spectra, were collected continually (every second) over the course of the survey and were geo-referenced using a differential Global Positioning System. Collection of spectral data allows the system to distinguish between ordinary fluctuations in natural background radiation levels and the signature produced by man-made radioisotopes. Spectral data can also be used to identify specific radioactive isotopes. As a courtesy service, with the approval of the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office, RSL-Nellis is providing this summary to the office of the Mayor of the City of North Las Vegas along with the gross-count-based exposure rate and man-made count contour maps and GIS shape files in electronic format on a compact disk.

Piotr Wasiolek

2008-06-01T23:59:59.000Z

53

Review of radiological surveys of the General Services Administration's Raritan Depot in Edison, New Jersey  

SciTech Connect

This report reviews two recent radiological surveys of the General Services Administration (GSA) Raritan Depot in Edison, New Jersey, that were conducted after somewhat elevated levels of radiation were detected within a depot building. The first survey indicated gamma radiation levels were higher than natural background levels in some buildings and identified the probable source of the radiation as gypsum-like building tiles that contained natural uranium-chain radionuclides at a level 20 times higher than other materials. Elevated levels of radon and radon decay products also were detected in some buildings. A follow-on survey was conducted to confirm the January measurements and to measure radiation levels at other locations: additional buildings at the depot, buildings on the Middlesex County College campus, and a possible outdoor disposal site. EPA measurements established that ceiling material is the primary source of the radiation. Radioisotope analysis of the ceiling tile material from buildings with elevated radiation levels showed the presence of radium-226 at levels of approximately 25 picocuries per gram (pCi/g); this material would thus have to be treated as hazardous waste, should it be removed. This report critiques the methodology and results of the two surveys and recommends further action.

Herzenberg, C.L.; Winter, R.C.

1986-10-01T23:59:59.000Z

54

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

SciTech Connect

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

55

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

SciTech Connect

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

56

MULTI-AGENCY RADIATION SURVEY AND SITE INVESTIGATION MANUAL  

NLE Websites -- All DOE Office Websites (Extended Search)

MULTI-AGENCY MULTI-AGENCY RADIATION SURVEY AND SITE INVESTIGATION MANUAL (MARSSIM) NUREG-1575, Rev. 1 EPA 402-R-97-016, Rev. 1 Rev. 1 AUGUST 2000 REVISION 1 DOE/EH-0624, ABSTRACT 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

57

An aerial radiological survey of Project Gasbuggy and surrounding area, Rio Arriba County, New Mexico. Date of survey: October 27, 1994  

SciTech Connect

An aerial radiological survey was conducted over the Project Gasbuggy site, 55 miles (89 kilometers) east of Farmington, New Mexico, on October 27, 1994. Parallel lines were flown at intervals of 300 feet (91 meters) over a 16-square-mile (41-square-kilometer) area at a 150-foot (46-meter) altitude centered on the Gasbuggy site. The gamma energy spectra obtained were reduced to an exposure rate contour map overlaid on a high altitude aerial photograph of the area. The terrestrial exposure rate varied from 14 to 20 {micro}R/h at 1 meter above ground level. No anomalous or man-made isotopes were found.

NONE

1995-08-01T23:59:59.000Z

58

RADIOLOGICAL SURVEY STATION DEVELOPMENT FOR THE PIT DISASSEMBLY AND CONVERSION PROJECT  

SciTech Connect

The Savannah River National Laboratory (SRNL) has developed prototype equipment to demonstrate remote surveying of Inner and Outer DOE Standard 3013 containers for fixed and transferable contamination in accordance with DOE Standard 3013 and 10 CFR 835 Appendix B. When fully developed the equipment will be part of a larger suite of equipment used to package material in accordance with DOE Standard 3013 at the Pit Disassembly and Conversion Project slated for installation at the Savannah River Site. The prototype system consists of a small six-axis industrial robot with an end effector consisting of a force sensor, vacuum gripper and a three fingered pneumatic gripper. The work cell also contains two alpha survey instruments, swipes, swipe dispenser, and other ancillary equipment. An external controller interfaces with the robot controller, survey instruments and other ancillary equipment to control the overall process. SRNL is developing automated equipment for the Pit Disassembly and Conversion (PDC) Project that is slated for the Savannah River Site (SRS). The equipment being developed is automated packaging equipment for packaging plutonium bearing materials in accordance with DOE-STD-3013-2004. The subject of this paper is the development of a prototype Radiological Survey Station (RSS). Other automated equipment being developed for the PDC includes the Bagless transfer System, Outer Can Welder, Gantry Robot System (GRS) and Leak Test Station. The purpose of the RSS is to perform a frisk and swipe of the DOE Standard 3013 Container (either inner can or outer can) to check for fixed and transferable contamination. This is required to verify that the contamination levels are within the limits specified in DOE-STD-3013-2004 and 10 CFR 835, Appendix D. The surface contamination limit for the 3013 Outer Can (OC) is 500 dpm/100 cm2 (total) and 20 dpm/100 cm2 (transferable). This paper will concentrate on the RSS developments for the 3013 OC but the system for the 3013 Inner Can (IC) is nearly identical.

Dalmaso, M.; Gibbs, K.; Gregory, D.

2011-05-22T23:59:59.000Z

59

An aerial radiological survey of the neutron products company and surrounding area  

SciTech Connect

An aerial radiological survey was conducted from November 1-10, 1993, over the Neutron Products Company and neighboring areas. The company, located in Dickerson, Maryland, has two major operations involving the radioisotope cobalt-60 ({sup 60}Co)-the manufacture of commercial {sup 60}Co sources and the sterilization of medical products by exposure to radiation. The sterilization facility consists of two {sup 60}Co sources with activities of approximately 500,000 and 1,500,000 Ci, respectively. The purpose of the aerial survey was to detect and document any anomalous gamma-emitting radionuclides in the environment which may have resulted from operations of the Neutron Products Company. The survey covered two areas: the first was a 6.5- by 6.5-kilometer area centered over the Neutron Products facility; the second area was a 2- by 2.5-kilometer region surrounding a waste pumping station on Muddy Branch in Gaithersburg, Maryland. This site is approximately fifteen kilometers southeast of the Neutron Products facility and was included because sanitary and other liquid waste materials from the plant site are being disposed of at the pumping station. Contour maps showing gamma radiation exposure rates at 1 meter above ground level, overlaid on an aerial photo of the area, were constructed from the data measured during the flights. The exposure rates measured within the survey regions were generally uniform and typical of rates resulting from natural background radiation. Only one area showed an enhanced exposure rate not attributable to natural background. This area, located directly over the Neutron Products facility, was analyzed and identified as {sup 60}Co, the radioisotope used in the irradiation and source production operations conducted at the Neutron Products Company. The measurements over the Muddy Branch area in Gaithersburg were typical of natural background radiation and showed no evidence of {sup 60}Co or any other man-made radionuclide.

Vojtech, R.J.

1994-12-01T23:59:59.000Z

60

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

Energy.gov (U.S. Department of Energy (DOE))

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program (March 2012)

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

Results of the radiological survey at Interstate 80, North Right of Way at Lodi Brook, Lodi, New Jersey (LJ077)  

SciTech Connect

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 oil sampling for radionuclide analyses. The survey of this site, on the North Right of Way of Interstate 80 at Lodi Brook, Lodi, New Jersey (LJ077), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 3 figs., 3 tabs.

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

1989-06-01T23:59:59.000Z

62

Radiological Conditions at Bikini Atoll: Prospects for ResettlementRadiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary assessment and recommendations for further study  

Science Journals Connector (OSTI)

Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary assessment and recommendations for further study Radiological Assessment Reports Series 1998 (Vienna: IAEA) 43 pp 200 Austr. Sch. ISBN 92 0 104098 9 These two reports stem from requests to the IAEA, from the local Government Authorities, for help and advice in assessing the radiological situations at two former nuclear weapons testing sites. Both reports have similar general structures - a discussion of the geographical context of the sites; a summary of the weapon tests, and their continuing impacts on the local populations; the basis for the IAEA programme; radiological concepts and criteria in the context of the residual contamination arising from the tests, and specifically the bases for intervention and remediation; assessments of the present and future radiation exposures of the actual/potential residents of the areas; and conclusions and recommendations. Because the indigenous Bikinian population is at present relocated elsewhere in the Marshall Islands archipelago, the report for Bikini Atoll is essentially concerned with an assessment of the current radiological situation, the prospects for resettlement, and the justification and available strategies for remedial action to reassure the Bikinians that it would be safe to return. Since the cessation of testing at the atoll in July 1958, there have been continuing radiological surveys of the local environment - the latest being the Marshall Islands Nationwide Radiological Study under an International Scientific Advisory Panel. The Panel report was not accepted by the Marshall Islands Government, who then requested the IAEA to carry out an independent peer review. The IAEA assessment (with some corroboratory data from a monitoring mission) confirmed the estimate of 15 mSv a-1 for the total potential dose rate to individuals relying entirely on locally produced foodstuffs, mainly from 137Cs in coconuts and other fruits. An examination of existing guidelines and practice concluded that 10 mSv a-1 is an appropriate generic action level to trigger consideration of remediation strategies prior to resettlement. From five potential remedial measures, two were considered in more detail - removal and disposal of the surface 40 cm of the topsoil, and treatment of the soil with high potassium fertilizers. It was concluded that the former, although reducing the dose rate from the residual contamination to less than 0.1 mSv a-1, would entail unacceptable environmental and social consequences. Experimental investigation of the latter showed that it would reduce the uptake of 137Cs significantly, with the total dose rate rapidly declining to about 1.2 mSv a-1; it was also found that the application of fertilizer would have to be repeated every 4-5 years to sustain the reduction. The latter was, therefore, the preferred option together with some localised soil removal in the living areas of the village to reduce both the external exposure and the inhalation pathway. The sole remaining concern of the Bikinians appears to relate to the identification of a reliable authority to assume responsibility for maintaining the implementation of the countermeasure to reduce the 137Cs uptake into foodstuffs for the foreseeable future. If this concern can be resolved, it appears that the way is open for the resettlement of the Bikinian people on the atoll. The situation at Semipalatinsk is somewhat different in one respect - the site, although large, has unrestricted access and small numbers of people already live within the boundaries. After the request to the IAEA from the Kazakhstan Government for assistance, the initial objective was to determine the magnitude of the problem. This was achieved on the first mission to the site when the main areas of contamination were identified using information available from the local authorities, and radiation measurements and sample collections were made at identified places both within, and external to, the site. A second mission extended the range of measurements and sample

Dennis Woodhead

1999-01-01T23:59:59.000Z

63

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

64

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

65

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

SciTech Connect

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

66

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

SciTech Connect

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

67

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

SciTech Connect

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

68

Radiological Dose Assessment 8 2005 Site environmental report8-  

E-Print Network (OSTI)

) at off-site locations. Both measurements include contributions from natural background and cosmic radiation sources. A statistical comparison of the average doses measured at 47 on-site and 16 off-site. This is achieved by mea- suring direct penetrating radiation exposures both on and off site. The direct

69

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

70

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

71

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

SciTech Connect

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

72

Radiological Dose Assessment 8 2009 Site environmental report8-  

E-Print Network (OSTI)

-site dose measurements include the contribution from natural terrestrial and cosmic background radiation-site areas known to have radiation dose slightly elevated above the natural background radiation. The results was calculated as 7.20E-02 mrem (0.72 Sv) to the MEI. The dose from the ingestion pathway was estimated as 7

73

Finding of No Significant Impact Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

RADIOLOGICAL/NUCLEAR COUNTERMEASURES TEST AND EVALUATION COMPLEX, NEVADA TEST SITE The U.S. Department of Homeland Security (DHS) is the Federal organization charged with defending the borders of the United States under the authority the Homeland Security Act of 2002 (Public Law 107-296). The DHS requested the National Nuclear Security Administration (NNSA) to develop at the Nevada Test Site (NTS) a complex for testing and evaluating countermeasures for interdicting potential terrorist attacks using radiological and/or nuclear weapons of mass destruction. In response to that request, NNSA proposes to construct, operate, and maintain the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC). NNSA has prepared an Environmental Assessment (DOE/EA-1499) (EA) which analyzes the potential

74

Health and Safety Research Division RESULTS FROM A RADIOLOGICAL SURVEY ON YARDEORO AVENUE,  

Office of Legacy Management (LM)

Health and Safety Research Division Health and Safety Research Division RESULTS FROM A RADIOLOGICAL SURVEY ON YARDEORO AVENUE, ALBANY, AND CENTRAL AVENUE,, COLONIE, NEW YORK PROPERTIES AL013 - AL028 July 1984 Work performed as part of the RADIOLOGICAL SURVEY ACTIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U.S. DEPARTMENT OF ENERGY under Contract No. DE-AC05840R21400 _- _^." .-. ..-.- _---.--_ -... .- Fk. 3 ,=. Y)*cx gs 1 XEC @ d +I? ,%r $ g .&- _-.. .iTL--- d= m k m t Y iT 5 tn + a UT + t- 7 T? Y 0 + z cd (f c 0 W -7 0 9 0 oc !. __ g b a is d oJ F ig. 1. G a m m a exposure rates measured at the surface at grid points at 50 Yardboro Avenue, Albany, New York (AL013). . EE ?I 0 Es . m: 4 a I .r

75

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

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

76

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

SciTech Connect

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

77

"Speak Up" Survey Results - Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

in the survey. The goal is to use the results to continuously improve Hanford's safety culture and work environment. Results for the "Speak Up" Survey An Organizational...

78

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

SciTech Connect

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

79

DOE - Office of Legacy Management -- South Valley Superfund Site...  

Office of Legacy Management (LM)

Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Department of Energy is one of seven Potentially Responsible Parties (PRP) for...

80

DISS/ET modernization site/user survey details  

SciTech Connect

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

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.
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81

Designation Survey - Palmerton, Pa. Ore Storage Site William Bibb  

Office of Legacy Management (LM)

Designation Survey - Palmerton, Pa. Ore Storage Site Designation Survey - Palmerton, Pa. Ore Storage Site William Bibb Oak Ridge Operations Office Based on the information furnished in Aerospace's Review of the.subject site (Attachment 1) and the ORKL/RASA (Attachment 2), it Is requested that designation survey of the Palmerton Ore Storage Pennsylvania. The survey should be detailed to and subsurface data to make up for the lack of the previous AEC surveys and in keeping with ORNL/RASA group should furnish a draft survey approval prior to conducting any survey activities. If there are any questions, please call Edward DeLaney 04 FTS 253-4716. Arthur J. Whitman / '/ Division of Facility and Site ' Deconrnissioning P,rojects Office of Nuclear Energy : 2 Attachments I bee: I E. Keller, OR, w/attachs:

82

Environmental Survey preliminary report, Hanford Site, Richland, Washington  

SciTech Connect

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

83

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

SciTech Connect

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

84

Radiological Assistance Program (RAP)- Nuclear Engineering Division  

NLE Websites -- All DOE Office Websites (Extended Search)

Major Programs > Radiological Major Programs > Radiological Assistance Program Radiological Assistance Program Overview Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Radiological Assistance Program Bookmark and Share Survey equipment is used to detect and measure radiation Survey equipment is used to detect and measure radiation. Click on image to view larger image. The Radiological Assistance Program (RAP) team at Argonne can provide assistance in the event of a radiological accident or incident. Support ranges from giving technical information or advice over the telephone, to sending highly trained team members and state-of-the-art equipment to the accident site to help identify and minimize any radiological hazards. The

85

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

SciTech Connect

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

86

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

SciTech Connect

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

87

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

SciTech Connect

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

88

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

SciTech Connect

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

89

ORNL/luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT  

Office of Legacy Management (LM)

luSA-85/6 luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT OF TEE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT May 1985 Work performed as part of the RADIOLOGICAL SURVEY ACCIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U. S. DEPARTMENT OF ENERGY under Contract No. DE-AC05-840R21400 \ .-l__--.-- -- PRELIMINARY RADIOLOGICAL SURVEY OF THE FORMER HAVENS PLAEJT OF THE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT INTRODUCI' ION The Bridgeport Brass Company' s Havens plant located at Kossath and Pulaski Streets, Bridgeport, Connecticut. was used under contract with the Atomic Energy Commission (AEC) to process uranium during the period

90

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

SciTech Connect

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

91

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

SciTech Connect

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

92

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

SciTech Connect

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

93

ORNL/TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORATED,  

Office of Legacy Management (LM)

TM-11118 TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORATED, 1 MALCOLM AVENUE, TETERBORO, NEW JERSEY (TJOO3) FL D. Foley L. M. Floyd, Printed in the United States of America. Available from National Technical Information Serwce U.S. Department of Commerce I 5265 Port Royal Road. Springfield, Virginia 22161 NTIS price codes-Printed Copy:A03 Microfiche A01 This report was prepared as an account of work sponsored by an 8ge"cy of the UnitedSlaterGovernmenl.NeithertheUnitedStatesGovernmen~no,anyagency thereof. nor any 01 their employees. makes any warranty. express 0, implied. 0, assumes any legal liabhty or responsibility lo, the accuracy. completeness. 0, UJB~U~WSJ of any information. apparatus. product. or process disClosed. or represents that its use would not infringe privately owned rights. Reference herein

94

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

SciTech Connect

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

95

2011 Annual Ecological Survey: Pacific Northwest National Laboratory Site  

SciTech Connect

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

96

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

SciTech Connect

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

97

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

SciTech Connect

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

98

Results of the radiological survey at the Niagara-Mohawk property, Railroad Avenue, Colonie, New York (AL218)  

SciTech Connect

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The Niagara-Mohawk property on Railroad Avenue in Colonie, New York, was the subject of a radiological investigation initiated June 11, 1987. This commercial property is an irregularly shaped lot partially occupied by an electric power substation and associated transmission lines. Portions of the property that were swampy and heavily vegetated were inaccessible to the survey team. There are no buildings on the property. A diagram showing the approximate boundaries and the 15-m grid network established for measurements on the property is shown. The lot included in the radiological survey was /approximately/45 m wide by 246 m deep. Two views of the property are shown. 13 refs., 6 figs., 4 tabs.

Marley, J.L.; Carrier, R.F.

1987-12-01T23:59:59.000Z

99

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

SciTech Connect

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

100

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

SciTech Connect

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

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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101

An aerial radiological survey of the Kennedy Space Center and Cape Canaveral Air Force Station and surrounding area, Titusville, Florida: Date of survey: October 1985  

SciTech Connect

An aerial radiological survey of the entire Kennedy Space Center (KSC) and Cape Canaveral Air Force Station (CCAFS) was performed during the period 9 through 23 October 1985. This survey was conducted in three parts. First, a low resolution, low sensitivity background survey was performed that encompassed the entire KSC and CCAFS area. Next, two smaller, high resolution, high sensitivity surveys were conducted: the first focused on Launch Complexes 39A and 39B, and the second on the Shuttle Landing Facility. The areas encompassed by the surveys were 200, 5.5, and 8.5 square miles (500, 14, and 22 sq km), respectively. The purpose of these surveys was to provide information useful for an emergency response to a radiological accident. Results of the background survey are presented as isoradiation contour maps of both total exposure rate and man-made gross count superimposed on a mosaic of recent aerial photographs. Results of the two small, detailed surveys are also presented as an isoradiation contour map of exposure rate on the aerial photograph base. These data were evaluated to establish sensitivity limits for mapping the presence of plutonium-238. Natural background exposure rates at the Kennedy Space Center and Cape Canaveral Air Force Station are very low, generally ranging from 4 to 6.5 microroentgens per hour (..mu..R/h) and less than 4 ..mu..R/h in wet areas. However, exposure rates in developed areas were observed to be higher due to the importation of construction materials not characteristic of the area. 8 refs., 3 figs., 4 tabs.

Not Available

1988-01-01T23:59:59.000Z

102

Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1  

SciTech Connect

This report describes the survey and removal of radioactive surface contamination at Sandia`s Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope.

Lambert, K.A.; Mitchell, M.M. [Brown and Root Environmental, Albuquerque, NM (United States); Jean, D. [MDM/Lamb, Inc., Albuquerque, NM (United States); Brown, C. [Environmental Dimensions, Inc., Albuquerque, NM 87109 (United States); Byrd, C.S. [Sandia National Labs., Albuquerque, NM (United States)

1997-09-01T23:59:59.000Z

103

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

SciTech Connect

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

104

Microsoft Word - SPR Site Subsidence Surveys 2013-2017.docx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Subsidence Surveys, 2013-2017 Subsidence Surveys, 2013-2017 Description: Subcontractor shall provide all labor, supervision, materials, equipment, transportation, and services necessary to perform a subsidence survey of the Bayou Choctaw, Big Hill, Bryan Mound and West Hackberry SPR sites. Regulatory Requirements: NEPA Implementing Procedures (10 CFR 1021) 10 CFR 1021.410 (Application of Categorical Exclusions) (a) The actions listed in Appendices A and B of Subpart D are classes of actions that DOE has determined do not individually or cumulatively have a significant effect on the human environment (categorical exclusions). (b) To find that a proposal is categorically excluded, DOE shall determine the following: (1) The proposed action fits within a class of actions that is listed in Appendix A or B of Subpart D;

105

Aerial radiological survey of the area surrounding the UNC Recovery Systems Facility, Wood River Junction, Rhode Island  

SciTech Connect

An aerial radiological survey to measure terrestrial gamma radiation was carried out over the United Nuclear Corporation (UNC) Recovery Systems Facility located near Wood River Junction, Rhode Island. At the time of the survey (August 1979) materials were being processed at the facility. Gamma ray data were collected over a 3.28 km/sup 2/ area centered on the facility by flying north-south lines spaced 60 m apart. Processed data indicated that detected radioisotopes and their associated gamma ray exposure rates were consistent with those expected from normal background emitters, except directly over the UNC Facility. Average exposure rates 1 m above the ground, as calculated from the aerial data, are presented in the form of an isopleth map. No ground sample data were taken at the time of the aerial survey.

Bluitt, C.M.

1981-05-01T23:59:59.000Z

106

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

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

107

Introduction to MARSSIM The Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) provides  

E-Print Network (OSTI)

ROADMAP Introduction to MARSSIM The Multi-Agency Radiation Survey and Site Investigation Manual, characterization, and any necessary remedial actions. The process of planning the survey, implementing the survey in the Radiation Survey and Site Investigation Process, combined with references to sections in MARSSIM where

108

Seismic refraction survey of the ANS preferred site  

SciTech Connect

Between September 19, 1991 and October 8, 1991 personnel from Martin Marietta Energy Systems, Inc. (Energy Systems), Automated Sciences Group, Inc., and Marrich, Inc. performed a seismic refraction survey at the Advanced Neutron Source (ANS) preferred site. The purpose of this survey was to provide estimates of top-of-rock topography, based on seismic velocities, and to delineate variations in rock and soil velocities. Forty-four seismic refraction spreads were shot to determine top-of-rock depths at 42 locations. Nine of the seismic spreads were shot with long offsets to provide 216 top-of-rock depths for 4 seismic refraction profiles. The refraction spread locations were based on the grid for the ANS Phase I drilling program. Interpretation of the seismic refraction data supports the assumption that the top-of-rock surface generally follows the local topography. The shallow top-of-rock interface interpreted from the seismic refraction data is also supported by limited drill information at the site. Some zones of anomalous data are present that could be the result of locally variable weathering, a localized variation in shale content, or depth to top-of-rock greater than the site norm.

Davis, R.K. (Automated Sciences Group, Inc., Oak Ridge, TN (United States)); Hopkins, R.A. (Marrich, Inc., Knoxville, TN (United States)); Doll, W.E. (Oak Ridge National Lab., TN (United States))

1992-02-01T23:59:59.000Z

109

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

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

110

Analysis of the Variability of Classsified and Unclassified Radiological Source term Inventories in the Frenchman Flat Area, Nevada test Site  

SciTech Connect

It has been proposed that unclassified source terms used in the reactive transport modeling investigations at NTS CAUs should be based on yield-weighted source terms calculated using the average source term from Bowen et al. (2001) and the unclassified announced yields reported in DOE/NV-209. This unclassified inventory is likely to be used in unclassified contaminant boundary calculations and is, thus, relevant to compare to the classified inventory. They have examined the classified radionuclide inventory produced by 10 underground nuclear tests conducted in the Frenchman Flat (FF) area of the Nevada Test Site. The goals were to (1) evaluate the variability in classified radiological source terms among the 10 tests and (2) compare that variability and inventory uncertainties to an average unclassified inventory (e.g. Bowen 2001). To evaluate source term variability among the 10 tests, radiological inventories were compared on two relative scales: geometric mean and yield-weighted geometric mean. Furthermore, radiological inventories were either decay corrected to a common date (9/23/1992) or the time zero (t{sub 0}) of each test. Thus, a total of four data sets were produced. The date of 9/23/1992 was chosen based on the date of the last underground nuclear test at the Nevada Test Site.

Zhao, P; Zavarin, M

2008-06-04T23:59:59.000Z

111

Project RU LlSON COPY ON-SITE RADIOLOGICAL PROGRAMS DURING REENTRY DISILLING THROUGH PRODUCTION TESTING  

Office of Legacy Management (LM)

RU LlSON RU LlSON COPY ON-SITE RADIOLOGICAL PROGRAMS DURING REENTRY DISILLING THROUGH PRODUCTION TESTING FINAL REPOAT EBERLlNE INSTRUMENT CORPORATION Santa Fe, New Mexico Date Published - December 1973 PREPARED FOR THE U. S. ATOMIC ENERGY COMMISSION N E V A D A OPERATIONS OFFICE UNDER CONTRACT NO. AT(26-11-294 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. Project RULISON ON-S1l'E RADIOLOGICAL PROGRAMS D U R I N G R E E N T R Y D R I L L I N G THROUGH PRODUCTION TESTING \ F I N A L REPORT EBERLINE INSTRUMENT CORPORATION . Santa Fe, New Mexico 1 Date Published - December 1973 NEVADA OPERATIONS OFFICE . UNDER CONTRACT NO. AT(26-11-294 NOTICE ~~~~ This report was prepared as an account of work sponsored by the United

112

Selection criteria for dental implant site imaging: A position paper of the American Academy of Oral and Maxillofacial Radiology  

Science Journals Connector (OSTI)

The American Academy of Oral and Maxillofacial Radiology (AAOMR) has reviewed the implant imaging literature and issues this position paper for preoperative assessment of the dental implant site. The history of dental implant radiology and basic imaging principles are reviewed. An overview is presented of anatomically salient features in the maxilla and mandible germane to implant imaging, specifically to cross-sectional or transverse imaging for endosseous implants. All current modalities, including intraoral, panoramic, cephalometric, tomographic, and computed tomography, are discussed in light of the imaging data needed to select optimum implant solutions. After reviewing the current literature, the AAOMR recommends that some form of cross-sectional imaging be used for implant cases and that conventional cross-sectional tomography be the method of choice for gaining this information for most patients receiving implants.

American Academy of Oral; Maxillofacial Radiology; Donald A. Tyndall; Sharon L. Brooks

2000-01-01T23:59:59.000Z

113

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

114

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

115

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

E-Print Network (OSTI)

Sv) and off site was 66 ± 10 mrem (660 ± 100 mSv). Both measurements include contributions from cosmic and natural background sources. A statistical comparison of the average dose values from 41 on-site and 18 off-site measures direct penetrating radiation exposures off site with the premise that off-site exposures are true

Homes, Christopher C.

116

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

117

DESIGNATION SURVEY ADDENDUM REPORT II COMBUSTION ENGINEERING SITE  

Office of Legacy Management (LM)

,111 ,111 DESIGNATION SURVEY ADDENDUM REPORT II COMBUSTION ENGINEERING SITE *I W INDSOR, CONNECTICUT 111 E. W . ABELQUIST Prepared for the Office of Environmental Restoration U.S. Department of Energy I- II I- .:jj;jiE// .:::=::::: .ipij!li' ,:::i::.:. ..::I::::/. ,:ii~iiiiai, ..' iiiiiiiiii!!liiii~~~~,~:~:. ~i!i.~iii~' :' -' +g?' gg;; ,- ZY :i/ .:;i" .:!! .:::a .(/i?j i:/i;jl? I!kr ' -:~i~jg~;...,.;, ..,::&Si! :(j)//ji//(!: 3.. :jijiiiiiiqi:wi l~,. ,,v..::;:~/j~B/; g#;$ .;::::::::::! :::::::::: ::j/j j/i; :(/;;I . . :/:jij; ,:j:,i/; ::::::: ,i/j//:j ;igg;ij iii:::: ,;(iii$ :::::i:ii. ,,,,,, :i.;ifi;iuij;; ,,:,: ii ,,:::::::::::: .:zy,:l::... Lb. .::i:::. .,:.:::;:. ](i:iii:;!! :.:::::::p "'.'j?'~ fix&$ .ii .:::i .::i;;!jg#ggi& i///jjji_

118

ORISE: Characterization surveys  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterization surveys Characterization surveys An ORISE technicians performs a characterization survey The Oak Ridge Institute for Science and Education (ORISE) performs independent, objective characterization surveys to define the extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental aspect of all D&D projects, characterization surveys provide guidance to determine the best remediation procedures and are a cost-effective method of ensuring a site meets preliminary regulatory standards. ORISE designs characterization surveys using the data quality objectives process. This approach focuses on the particular objective of characterization, and ensures that only the data needed to address the characterization decisions are collected. Data collection efforts are

119

DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES.  

SciTech Connect

The success of this Accelerated Site Technology Deployment (ASTD) project is measured on several levels. First, the deployment of this innovative approach using in situ characterization, portable field laboratory measurements, and implementation of MARSSIM was successfully established for all three phases of D and D characterization, i.e., pre-job scoping, on-going disposition of waste, and final status surveys upon completion of the activity. Unlike traditional D and D projects, since the Brookhaven Graphite Research Reactor Decommissioning Project (BGRR-DP) is operating on an accelerated schedule, much of the work is being carried out simultaneously. Rather than complete a full characterization of the facility before D and D work begins, specific removal actions require characterization as the activity progresses. Thus, the need for rapid and cost-effective techniques for characterization is heightened. Secondly, since the approach used for this ASTD project was not thoroughly proven prior to deployment, a large effort was devoted to demonstrating technical comparability to project managers, regulators and stakeholders. During the initial phases, large numbers of replicate samples were taken and analyzed by conventional baseline techniques to ensure that BGRR-DP quality assurance standards were met. ASTD project staff prepared comparisons of data gathered using ISOCS and BetaScint with traditional laboratory methods and presented this information to BGRR-DP staff and regulators from EPA Region II, NYS Department of Environmental Conservation, and the Suffolk County Board of Health. As the results of comparability evaluations became available, approval for these methods was received and the techniques associated with in situ characterization, portable field laboratory measurements, and implementation of MARSSIM were gradually integrated into BGRR-DP procedures.

KALB,P.D.; MILIAN,L.; LUCKETT,L.; WATTERS,D.; MILLER,K.M.; GOGOLAK,C.

2001-05-01T23:59:59.000Z

120

DOE/EA-1499; Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site Final Environmental Assessment  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

499 499 Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site Final Environmental Assessment August 2004 U. S. Department of Energy National Nuclear Security Administration Nevada Site Office Las Vegas, Nevada Available for sale to the Public, in paper, from: U.S. Department of Commerce National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Phone: 800.553.6847 Fax: 703.605.6900 Email: orders@ntis..gov Online Ordering: http://www.ntis.gov/ordering.htm Available electronically at: http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors in paper from-- U.S. Department of Energy Office of Scientific and Technical Information

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121

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

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

122

Assessment of the radiological impact of gamma and radon dose rates at former U mining sites in Central Asia  

Science Journals Connector (OSTI)

An assessment of the radiological situation due to exposure to gamma radiation, radon and thoron was carried out at selected former uranium mining and processing sites in the Central Asian countries of Kazakhstan, Kyrgyzstan, Uzbekistan and Tajikistan. Gamma dose rate measurements were made using various field instruments and radon/thoron measurements were carried out using discriminative radon (222Rn)/thoron (220Rn) solid state nuclear track detectors (SSNTD). The detectors were exposed for an extended period of time, including at least three seasonal periods in a year, in different outdoor and indoor public and residential environments at the selected uranium legacy sites. The results showed that gamma, Rn and Tn doses were in general low, which consequently implies a low/relatively low radiological risk. The major radiation hazard is represented by abandoned radioactive filtration material that was being used as insulation by some Minkush residents (Kyrgyzstan) for a longer period of time. Annual radiation doses of several hundred mSv could be received as a consequence of using this material domestically. In addition, the gamma and Rn/Tn dose rates at Digmai, Tajikistan, could reach values of several 10 mSv/a. The doses of ionizing radiation deriving from external radiation (gamma dose rate), indoor radon and thoron with their short-lived progenies in several cases exceeded the recommended annual effective dose threshold level of 10 mSv. At none of the sites investigated did the individual annual effective doses exceed 30 mSv, the internationally recommended value for considering intervention. Current doses of ionizing radiation do not represent a serious hazard to the health of the resident public, but this issue should be adequately addressed to further reduce needless exposure of the resident public to ionizing radiation.

P. Stegnar; I. Shishkov; M. Burkitbayev; B. Tolongutov; M. Yunusov; R. Radyuk; B. Salbu

2013-01-01T23:59:59.000Z

123

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

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

124

Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) More Documents & Publications

125

Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) More Documents & Publications

126

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Work Coverage Radiological Work Coverage Instructor's Guide 2.11-1 Course Title: Radiological Control Technician Module Title: Radiological Work Coverage Module Number: 2.11 Objectives: 2.11.01 List four purposes of job coverage. 2.11.02 Explain the differences between continuous and intermittent job coverage. 2.11.03 Given example conditions, identify those that should require job coverage. 2.11.04 Identify items that should be considered in planning job coverage. 2.11.05 Identify examples of information that should be discussed with workers during pre-job briefings. 2.11.06 Describe exposure control techniques that can be used to control worker and technician radiation exposures. L 2.11.07 Describe the in-progress radiological surveys that should be performed, at your site, under various radiological conditions.

127

DOE-HDBK-1122-99; Radiological Control Technican Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Work Coverage Radiological Work Coverage Study Guide 2.11-1 Course Title: Radiological Control Technician Module Title: Radiological Work Coverage Module Number: 2.11 Objectives: 2.11.01 List four purposes of job coverage. 2.11.02 Explain the differences between continuous and intermittent job coverage. 2.11.03 Given example conditions, identify those that should require job coverage. 2.11.04 Identify items that should be considered in planning job coverage. 2.11.05 Identify examples of information that should be discussed with workers during pre-job briefings. 2.11.06 Describe exposure control techniques that can be used to control worker and technician radiation exposures. i 2.11.07 Describe the in-progress radiological surveys that should be performed, at your site, under various radiological conditions.

128

Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network (OSTI)

-site dose measurements include the contribution from natural terrestrial and cosmic background radiation-site areas known to have radiation dose slightly above the natural background radiation. The results was estimated as 9.20E-01 mrem (9.2 Sv) to the MEI. The dose from the ingestion pathway was estimated as 4

129

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

SciTech Connect

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

130

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

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

131

Microsoft Word - Berger Radiological Conditions.doc  

Office of Legacy Management (LM)

Dec. Dec. 2, 2009 1 Summary of Information Regarding Radiological Conditions of NFSS Vicinity Properties J. D. Berger, CHP DeNuke Contracting Services, Inc. Oak Ridge, TN The following is a summary of the information obtained from reviews of radiological survey reports, prepared by ORAU in support of the DOE Formerly Utilized Sites Remedial Action Program. These reports were obtained for review from the IVEA Program at ORAU/ORISE. A list of the reports, reviewed for this summary, is included at the end of this report. Hard copies of reports for ORAU survey activities of NFSS and NFSS Vicinity Properties are available at the South Campus Site of ORAU (these reports are not available in electronic form). In addition, there are 12 - 14 boxes of hard-copy supporting data and information, pertinent to the surveys. I inspected the contents of Box 54. That box contained records for NFSS Vicinity

132

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

SciTech Connect

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

133

Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network (OSTI)

. The effective dose equivalent (EDE) from air emissions in 2013 was estimated as 3.65E-01 mrem (3.6 Sv dose limit of 10 mrem (100 Sv). In addition, the dose from the ingestion pathway was estimated as 2 the natural background radiation. The average annual external dose from on-site ambient sources was 66 � 8

134

Development of standard evaluation plan for survey and investigation of residual radioactivity on site  

Science Journals Connector (OSTI)

......standard evaluation plan for survey and investigation...site investigation plan are needed to ensure...under their control. Regulatory agencies need to...historical records review, process knowledge...Office of Nuclear Regulatory Research. NUREG-1640...standard evaluation plan for survey and investigation......

Sang Won Shin; Joo Ho Whang; Su Hong Lee; Jea Min Lee

2011-07-01T23:59:59.000Z

135

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

SciTech Connect

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

136

A survey on contrast radiography and adverse reaction in the radiology departments of university dental hospitals in Japan  

Science Journals Connector (OSTI)

We analyzed the results of a questionnaire regarding the use of contrast radiography and computed tomography (CT), and the reactions to contrast media during 1993, which was sent to 28 Radiology Departments of Un...

Kenji Yuasa D.D.S.; Ph.D.; Koichi Yonetsu D.D.S. Ph.D.…

1996-12-01T23:59:59.000Z

137

ORNL-5680 Radiological Surveys  

Office of Legacy Management (LM)

These guidelines recommend the following graded action levels for remedial action in terms of external gamma radiation level (EGR) and indoor radon daughter concentration level...

138

THE RELATIONSHIP BETWEEN THE RADIATION SURVEY AND SITE INVESTIGATION PROCESS, THE CERCLA REMEDIAL OR REMOVAL  

E-Print Network (OSTI)

Assessment Site Inspection Remedial Investigation Feasibility Study Remedial Design/ Remedial Action PassAPPENDIX F THE RELATIONSHIP BETWEEN THE RADIATION SURVEY AND SITE INVESTIGATION PROCESS, THE CERCLA REMEDIAL OR REMOVAL PROCESS, AND THE RCRA CORRECTIVE ACTION PROCESS This appendix presents a discussion

139

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

SciTech Connect

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

140

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

SciTech Connect

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

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

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Monitoring Environmental Monitoring Study Guide 2.09-1 Course Title: Radiological Control Technician Module Title: Environmental Monitoring Module Number: 2.09 Objectives: 2.09.01 State the goals of an environmental monitoring program. 2.09.02 State the exposure limits to the general public as they apply to environmental monitoring. 2.09.03 Define the term "critical nuclide." 2.09.04 Define the term "critical pathway." i 2.09.05 State locations frequently surveyed for radiological contamination at outdoor waste sites associated with your site and the reasons for each. 2.09.06 Define the term "suspect waste site," and how they can be identified. i 2.09.07 Describe the methods used for environmental monitoring at your site. INTRODUCTION Environmental monitoring plays a large role in the field of radiological control.

142

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

SciTech Connect

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

143

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

SciTech Connect

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

144

Radiological Worker Training - Radiological Control Training for Supervisors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A A December 2008 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 iii Foreword This Handbook describes an implementation process for training as recommended in

145

DOE - Office of Legacy Management -- Monticello Mill Site - UT 03  

NLE Websites -- All DOE Office Websites (Extended Search)

Mill Site - UT 03 Mill Site - UT 03 FUSRAP Considered Sites Site: Monticello Mill Site (UT.03) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Monticello, Utah, Disposal and Processing Sites Documents Related to Monticello Mill Site Monticello Mill Tailings Site Operable Unit III Interim Remedial Action Progress Report July 1999-July 2000. GJO-2000-163-TAR. September 2000 U.S. Department of Energy at Grand Junction 2003 Annual Inspection Monticello, Utah November 2003 2005 Annual Inspection of the Monticello Mill Tailings (USDOE) and Monticello Radioactively Contaminated Properties Sites December 2005 Office

146

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

MEASUREMENT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix B December 2008 Reaffirmed 2013 DOE HANDBOOK RADIOLOGICAL WORKER TRAINING RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ . ii Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 Foreword This Handbook describes a recommended implementation process for core training as outlined in

147

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix A Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 Foreword This Handbook describes an implementation process for training as recommended in

148

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix A Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 Foreword This Handbook describes an implementation process for training as recommended in

149

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix C December 2008 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Safety Training for Radiation Producing (X-Ray) Devices U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008

150

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix C December 2008 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Safety Training for Radiation Producing (X-Ray) Devices U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008

151

Analysis of the Variability of Classified and Unclassified Radiological Source term Inventories in the Rainier Mesa/Shoshone Mountain Area, Nevada Test Site  

SciTech Connect

It has been proposed that unclassified source terms used in RM/SM reactive transport modeling investigations should be based on yield-weighted source terms calculated using the RM/SM average source term from Bowen et al. (2001) and the unclassified announced yields reported in DOE/NV-209. This unclassified inventory is likely to be used in unclassified contaminant boundary calculations and is, thus, relevant to compare to the classified inventory. They have examined the classified radionuclide inventory produced by 73 underground nuclear tests conducted in the Rainier Mesa/Shoshone Mountain (RM/SM) area of the Nevada Test Site. The goals were to (1) evaluate the variability in classified radiological source terms among the 73 tests and (2) and compare that variability and inventory uncertainties to an average unclassified inventory (e.g. Bowen 2001). To evaluate source term variability among the 73 tests, radiological inventories were compared on two relative scales: geometric mean and yield-weighted geometric mean. Furthermore, radiological inventories were either decay corrected to a common date (9/23/1992) or the time zero (t{sub 0}) of each test. Thus, a total of four data sets were produced. The date of 9/23/1992 was chosen based on the date of the last underground nuclear test at the Nevada Test Site.

Zhao, P; Zavarin, M

2008-06-04T23:59:59.000Z

152

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

SciTech Connect

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

153

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

SciTech Connect

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

154

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

SciTech Connect

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

155

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

SciTech Connect

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

156

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

SciTech Connect

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

157

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

SciTech Connect

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

158

Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project  

SciTech Connect

This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

1992-06-01T23:59:59.000Z

159

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range  

SciTech Connect

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

NONE

1997-06-01T23:59:59.000Z

160

Release criteria and pathway analysis for radiological remediation  

SciTech Connect

Site-specific activity concentrations were derived for soils contaminated with mixed fission products (MFP), or uranium-processing residues, using the Department of Energy (DOE) pathway analysis computer code RESRAD at four different sites. The concentrations and other radiological parameters, such as limits on background-subtracted gamma exposure rate were used as the basis to arrive at release criteria for two of the sites. Valid statistical parameters, calculated for the distribution of radiological data obtained from site surveys, were then compared with the criteria to determine releasability or need for further decontamination. For the other two sites, RESRAD has been used as a preremediation planning tool to derive residual material guidelines for uranium. 11 refs., 4 figs., 3 tabs.

Subbaraman, G.; Tuttle, R.J.; Oliver, B.M. (Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.); Devgun, J.S. (Argonne National Lab., IL (United States))

1991-01-01T23:59:59.000Z

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

DOE-HDBK-1141-2001; Radiological Assessor Training, Instructor's Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8-1 8-1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Aspects of Plutonium Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify the radiological properties of plutonium. 2. Identify the biological effects of plutonium. 3. Identify special controls and considerations required for plutonium operations. 4. Describe appropriate instruments, measurement techniques, and special radiological survey methods for plutonium. 5. Describe personnel protection requirements and dose control techniques for plutonium. Training Aids: Overhead Transparencies (OTs): OT 8.1 - OT 8.12 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen

162

EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT LABORATO  

Office of Legacy Management (LM)

Oe. 1-G Oe. 1-G l/ZL=q n EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT LABORATO EP-F-002 Of THE UNITED STATES DECEMBER 1981 DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL SURVEY OF THE AREA SURROUNDING THE BUREAU OF MINES SITE ALBANY, OREGON DATE OF SURVEY: FEBRUARY 1980 AN AERIAL RADIOLOGICAL SURVEY OF THE BUREAU OF MINES SITE ALBANY, OREGON I I I . t I 1 I I I I I I I t PROJECT SCIENTIST: E. FEIMSTER EG&G, INC. LAS VEGAS, NEVADA 1.0 SUMMARY OF RESULTS An aerial radiological measuring system was used to survey areas surrounding the Bureau of Mines Site near Albany, Oregon in February 1980. The survey was conducted for the U.S. Department of Energy's Office of Operational Safety by the Department's Remote Sensing Laboratory of Las

163

Radiological-dose assessments of atolls in the northern Marshall Islands  

SciTech Connect

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

164

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Monitoring Environmental Monitoring Instructor's Guide 2.09-1 Course Title: Radiological Control Technician Module Title: Environmental Monitoring Module Number: 2.09 Objectives: 2.09.01 State the goals of an environmental monitoring program. 2.09.02 State the exposure limits to the general public as they apply to environmental monitoring. 2.09.03 Define the term "critical nuclide." 2.09.04 Define the term "critical pathway." L 2.09.05 State locations frequently surveyed for radiological contamination at outdoor waste sites associated with your site and the reasons for each. 2.09.06 Define the term "suspect waste site," and how they can be identified. L 2.09.07 Describe the methods used for environmental monitoring at your site. References: 1. Gollnick, Daniel, Basic Radiation Protection Technology, 2nd Edition, Pacific

165

EMSL - radiological  

NLE Websites -- All DOE Office Websites (Extended Search)

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

166

Workplace Violence Policy Survey of Department of Energy Contractor Sites (ORISE 2002-0580, 2002)  

NLE Websites -- All DOE Office Websites (Extended Search)

WORKPLACE VIOLENCE POLICY SURVEY WORKPLACE VIOLENCE POLICY SURVEY OF DEPARTMENT OF ENERGY CONTRACTOR SITES Prepared for U.S. Department of Energy Office of Health Programs Washington, DC Prepared by Center for Human Reliability Studies Oak Ridge Institute for Science and Education Oak Ridge, TN May 2002 ORISE 2002-0580 INTRODUCTION No workplace is immune to the threat of workplace violence. It can and does happen anywhere and at any time. Companies must make a concerted effort to evaluate their potential for workplace violence and implement measures to address this issue for the protection of their employees. The Occupational Safety and Health Act of 1970 (29 USC 654 et. seq., U.S. Department of Labor, amended September 29, 1998) requires companies to provide employees with a safe and healthful place to work. The "general duty" clause of this Act

167

POST-REMEDIAL RADIOLOGICAL DOSE AND RISK ASSESSMENT FOR THE BLISS & LAUGHLIN SITE BUFFALO, NEW YORK  

Office of Legacy Management (LM)

i i TABLE OF CONTENTS Table of Contents ........................................................................................................... i List of Tables................................................................................................................ iii List of Figures .............................................................................................................. iii 1 Introduction ............................................................................................................... 1 1.1 Site Description and History ............................................................................ 1 1.2 Purpose............................................................................................................. 4

168

Radiological Worker Training - Radiological Contamination Control for Laboratory Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

B B December 2008 DOE HANDBOOK RADIOLOGICAL WORKER TRAINING RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ . Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 iii Foreword This Handbook describes a recommended implementation process for core training as outlined in

169

A multispectral scanner survey of the Rocky Flats Environmental Technology Site and surrounding area, Golden, Colorado  

SciTech Connect

Aerial multispectral scanner imagery was collected of the Rocky Flats Environmental Technology Site in Golden, Colorado, on June 3, 5, 6, and 7, 1994, using a Daedalus AADS1268 multispectral scanner and coincident aerial color and color infrared photography. Flight altitudes were 4,500 feet (1372 meters) above ground level to match prior 1989 survey data; 2,000 feet (609 meters) above ground level for sitewide vegetation mapping; and 1,000 feet (304 meters) above ground level for selected areas of special interest. A multispectral survey was initiated to improve the existing vegetation classification map, to identify seeps and springs, and to generate ARC/INFO Geographic Information System compatible coverages of the vegetation and wetlands for the entire site including the buffer zone. The multispectral scanner imagery and coincident aerial photography were analyzed for the detection, identification, and mapping of vegetation and wetlands. The multispectral scanner data were processed digitally while the color and color infrared photography were manually photo-interpreted to define vegetation and wetlands. Several standard image enhancement techniques were applied to the multispectral scanner data to assist image interpretation. A seep enhancement was applied and a color composite consisting of multispectral scanner channels 11, 7, and 5 (thermal infrared, mid-infrared, and red bands, respectively) proved most useful for detecting seeps, seep zones, and springs. The predawn thermal infrared data were also useful in identifying and locating seeps. The remote sensing data, mapped wetlands, and ancillary Geographic Information System compatible data sets were spatially analyzed for seeps.

Brewster, S.B. Jr.; Brickey, D.W.; Ross, S.L.; Shines, J.E.

1997-04-01T23:59:59.000Z

170

US, UK, Kazakhstan Secure Radiological Transportation Vehicles...  

National Nuclear Security Administration (NNSA)

place them in secure storage, and improve radiological transportation security and site security. The United Kingdom-funded projects provide an immediate security and safety...

171

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

SciTech Connect

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

172

Solar Site Survey for the Advanced Technology Solar Telecope. I. Analysis of the Seeing Data  

E-Print Network (OSTI)

The site survey for the Advanced Technology Solar Telescope concluded recently after more than two years of data gathering and analysis. Six locations, including lake, island and continental sites, were thoroughly probed for image quality and sky brightness. The present paper describes the analysis methodology employed to determine the height stratification of the atmospheric turbulence. This information is crucial because day-time seeing is often very different between the actual telescope aperture (~30 m) and the ground. Two independent inversion codes have been developed to analyze simultaneously data from a scintillometer array and a solar differential image monitor. We show here the results of applying them to a sample subset of data from May 2003, which was used for testing. Both codes retrieve a similar seeing stratification through the height range of interest. A quantitative comparison between our analysis procedure and actual in situ measurements confirms the validity of the inversions. The sample data presented in this paper reveal a qualitatively different behavior for the lake sites (dominated by high-altitude seeing) and the rest (dominated by near-ground turbulence).

H. Socas-Navarro; J. Beckers; P. Brandt; J. Briggs; T. Brown; W. Brown; M. Collados; C. Denker; S. Fletcher; S. Hegwer; F. Hill; T. Horst; M. Komsa; J. Kuhn; A. Lecinski; H. Lin; S. Oncley; M. Penn; T. Rimmele; K. Streander

2005-08-31T23:59:59.000Z

173

DOE - Office of Legacy Management -- Edgemont Mill Site - SD 01  

Office of Legacy Management (LM)

Edgemont Mill Site - SD 01 Edgemont Mill Site - SD 01 FUSRAP Considered Sites Site: Edgemont Mill Site (SD.01) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Edgemont, South Dakota, Disposal Site Documents Related to Edgemont Mill Site 2012 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites-Edgemont, South Dakota, Disposal Site. LMS/S09415. November 2012 U.S. Department of Energy 2008 UMTRCA Title II Sites Annual Report November 2008 Edgemont, South Dakota FACT SHEET Office of Legacy Management Edgemont, South Dakota, Disposal Site This fact sheet provides information about the Uranium Mill

174

Radiological Assessor Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1-2008 1-2008 August 2008 DOE HANDBOOK Radiological Assessor Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techs\ Foreword This Handbook describes an implementation process for training as recommended in Implementation Guide G441.1-1B, Radiation Protection Programs, March 2007, and as outlined in DOE- STD- 1098-99, CN1, March 2005, DOE Radiological Control (the Radiological Control Standard - RCS). The Handbook is meant to assist those individuals within the Department of

175

DOE - Office of Legacy Management -- Uravan Mill Site - CO 02  

Office of Legacy Management (LM)

Uravan Mill Site - CO 02 Uravan Mill Site - CO 02 FUSRAP Considered Sites Site: Uravan Mill Site (CO.02 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Naturita, Colorado, Processing Site Documents Related to Uravan Mill Site Data Validation Package for the July and October 2008 Water Sampling at the Naturita Processing and Disposal Sites Data Validation Report for the July 2009 Groundwater and Surface Water Sampling at the Naturita, Colorado, Processing Site; LMS/NAP/S00709; October 2009 2012 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites-Naturita, Colorado,

176

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

Office of Legacy Management (LM)

COMPRE}IENSIVE RADIOLOGICAI SURVEY COMPRE}IENSIVE RADIOLOGICAI SURVEY OFF-SITE PROPERTY N,-NORTS NIAGARA FALLS STORAGE SITE LE'l,f ISTON ' NE'l^l YORK P r e p a r e d f o r U . S . D e p a t t m e n t o f E a e r g Y a s p a r t o f t h e F o r m e r l y U t i l i z e d S i t e s - - R e r n e d i a l A c t i o n P r o g r a m J . D . B e r g e r P r o j e c t S t a f f A . J . B o e r n e r W . 0 . E e l t o n R . D " C o n d r a T . J . S o w e l l P . W . F r a m e C . F . W e a v e r R . C . G o s s l e e B . S . Z a c h a r e k Prepared by R a d i o l o g i c a l S i t e A s s e s s m e n t P r o g r a m Manpower Education, Research, and Training Division O a k R i d g e A s s o c i a t e d U n i v e r s i t i e s O a k R i d g e , T e n n e s s e e 3 7 8 3 1 - 0 1 1 7 FINAI. REPORT M a y 1 9 8 4 This report is based on work performed under contract number DE-AC05-760R00033 with the Department of Energy. TAB1E OF CONTENTS L i s t o f F i g u r e s L i s t o f T a b l e s P a g e i i t_ l- t- 1 I 2 5 8 8 4 3 I n t r o d u c t i o n S i t e D e s c r i p t i o n Survey Procedures R e s u I t s

177

Radiological Control  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-1098-2008 October 2008 DOE STANDARD RADIOLOGICAL CONTROL U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ii DOE-STD-1098-2008 This document is available on the Department of Energy Technical Standards Program Website at http://www.standards.doe.gov/ DOE-STD-1098-2008 Radiological Control DOE Policy October 2008 iii Foreword 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

178

Description of the Formerly Utilized Sites Remedial Action Program  

SciTech Connect

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

179

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

180

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

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

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

182

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

183

Radiological Control  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-1098-2008 October 2008 ------------------------------------- Change Notice 1 May 2009 DOE STANDARD RADIOLOGICAL CONTROL U.S. Department of Energy SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1098-2008 ii This document is available on the Department of Energy Technical Standards Program Website at http://www.standards.doe.gov/ iii DOE-STD-1098-2008 Change Notice 1: DOE-STD-1098-2008, Radiological Control Standard Section/page/paragraph Change Section 211, page 2-3, paragraph 1 Add new paragraph 1: "Approval by the appropriate Secretarial Officer or designee should be required

184

DOE - Office of Legacy Management -- WNI Split Rock Site - 043  

NLE Websites -- All DOE Office Websites (Extended Search)

Split Rock Site - 043 Split Rock Site - 043 FUSRAP Considered Sites Site: WNI Split Rock Site (043) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Western Nuclear, Inc. (WNI) Split Rock site is a Uranium Mill Tailings Remedial Action (UMTRA) Title II site located in Jeffrey City, Wyoming. UMTRA Title II sites are privately owned and operated sites that were active when the Uranium Mill Tailings Control Act was passed in 1978. The majority of the milling conducted at these sites was for private sale, but a portion was sold to the U.S. Government. After the owner completes U.S. Nuclear Regulatory Commission license termination, the Department of

185

DOE - Office of Legacy Management -- ANC Gas Hills Site - 040  

NLE Websites -- All DOE Office Websites (Extended Search)

ANC Gas Hills Site - 040 ANC Gas Hills Site - 040 FUSRAP Considered Sites Site: ANC Gas Hills Site (040) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The ANC Gas Hills site is a Uranium Mill Tailings Remedial Action (UMTRA) Title II site located in Gas Hills, Wyoming. UMTRA Title II sites are privately owned and operated sites that were active when the Uranium Mill Tailings Radiation Control Act was passed in 1978. The majority of the milling conducted at these sites was for private sale, but a portion was sold to the U.S. Government. After the owner completes U.S. Nuclear Regulatory Commission license termination, the Department of Energy¿s

186

DOE - Office of Legacy Management -- Pathfinder Lucky Mc Site - 042  

NLE Websites -- All DOE Office Websites (Extended Search)

Pathfinder Lucky Mc Site - 042 Pathfinder Lucky Mc Site - 042 FUSRAP Considered Sites Site: Pathfinder Lucky Mc Site (042) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Pathfinder Lucky Mc site is a Uranium Mill Tailings Remedial Action (UMTRA) Title II site located in the Gas Hills Uranium Mining District west of Casper, Wyoming. UMTRA Title II sites are privately owned and operated sites that were active when the Uranium Mill Tailings Radiation Control Act was passed in 1978. The majority of the milling conducted at these sites was for private sale, but a portion was sold to the U.S. Government. After the owner completes U.S. Nuclear Regulatory Commission license termination,

187

DOE - Office of Legacy Management -- WNI Sherwood Site - 039  

NLE Websites -- All DOE Office Websites (Extended Search)

Sherwood Site - 039 Sherwood Site - 039 FUSRAP Considered Sites Site: WNI Sherwood Site (039) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This site is a Uranium Mill Tailings Remedial Action (UMTRA) Title II site located in the State of Washington. UMTRA Title II sites are privately owned and operated sites that were active when the Uranium Mill Tailings Radiation Control Act was passed in 1978. The majority milling conducted at this site was for private sale. After the owner completes NRC license termination the Department of Energy¿s Grand Junction Office will be responsible for providing stewardship for the groundwater and disposal

188

DOE - Office of Legacy Management -- Chevron Panna Maria Site - 030  

NLE Websites -- All DOE Office Websites (Extended Search)

Chevron Panna Maria Site - 030 Chevron Panna Maria Site - 030 FUSRAP Considered Sites Site: Chevron Panna Maria Site (030) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This site is a Uranium Mill Tailings Remedial Action (UMTRA) Title II site located in Texas. UMTRA Title II sites are privately owned and operated sites that were active when the Uranium Mill Tailings Radiation Control Act was passed in 1978. The milling conducted at this site was for private sale. After the owner completes U. S. Nuclear Regulatory Commission license termination the Department of Energy¿s Grand Junction Office will be responsible for providing stewardship for the groundwater and disposal

189

DOE - Office of Legacy Management -- Hecla Durita Site - 012  

NLE Websites -- All DOE Office Websites (Extended Search)

Hecla Durita Site - 012 Hecla Durita Site - 012 FUSRAP Considered Sites Site: Hecla Durita Site (012 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Hecla site is a Uranium Mill Tailings Radiation Control Act (UMTRCA) Title II site located in Durita, Colorado. UMTRCA Title II sites are privately owned and operated sites that were active when the Uranium Mill Tailings Radiation Control Act was passed in 1978. The majority of milling conducted at this site was for private sale. After the owner completes U.S. Nuclear Regulatory Commission license termination, the Department of Energy's Grand Junction Office will be responsible for providing

190

Industrial Radiology  

Science Journals Connector (OSTI)

... chief application of industrial radiology in Norway is in the examination of pipe welds in hydroelectric plant. H. Vinter (Denmark), director of the Akademiet for de Technische Videns ... and to compare various methods of non-destructive testing. He gave results of tests on turbine disk forgings of austenitic steel which showed satisfactory agreement between radiography, ultrasonic examination and ...

1950-11-18T23:59:59.000Z

191

Radiological health aspects of uranium milling  

SciTech Connect

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

192

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

Energy.gov (U.S. Department of Energy (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.

193

Results of Surveys for Special Status Reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory  

SciTech Connect

The purpose of this report is to present the results of a live-trapping and visual surveys for special status reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory (LLNL). The survey was conducted under the authority of the Federal recovery permit of Swaim Biological Consulting (PRT-815537) and a Memorandum of Understanding issued from the California Department of Fish and Game. Site 300 is located between Livermore and Tracy just north of Tesla road (Alameda County) and Corral Hollow Road (San Joaquin County) and straddles the Alameda and San Joaquin County line (Figures 1 and 2). It encompasses portions of the USGS 7.5 minute Midway and Tracy quadrangles (Figure 2). Focused surveys were conducted for four special status reptiles including the Alameda whipsnake (Masticophis lateralis euryxanthus), the San Joaquin Whipsnake (Masticophis Hagellum ruddock), the silvery legless lizard (Anniella pulchra pulchra), and the California horned lizard (Phrynosoma coronanum frontale).

Woollett, J J

2008-09-18T23:59:59.000Z

194

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

SciTech Connect

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

195

OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL  

Office of Legacy Management (LM)

ornl< ORNLRASA-8664 (MJ18V) orni OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL EZ-BBBB - *VERIFICATION SURVEY AT THE BALLOD ASSOCIATES PROPERTY,...

196

Development of standard evaluation plan for survey and investigation of residual radioactivity on site  

Science Journals Connector (OSTI)

......Development of standard evaluation plan for survey and...investigation plan are needed to...historical records review, process knowledge...expressed as a standard deviation...Development of standard evaluation plan for survey and......

Sang Won Shin; Joo Ho Whang; Su Hong Lee; Jea Min Lee

2011-07-01T23:59:59.000Z

197

DOE - Office of Legacy Management -- Nevada Test Site - 023  

Office of Legacy Management (LM)

Nevada Test Site - 023 Nevada Test Site - 023 FUSRAP Considered Sites Site: Nevada Test Site (023) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Nevada Test Site was established by the Atomic Energy Commission in the 1950's to conduct field testing of nuclear explosives in connection with the research and development of nuclear weapons. The environmental management activities for this site are under the purview of the Department of Energy¿s Nevada Operations Office. The National Nuclear Security Administration is the site landlord and will be responsible for Long Term Stewardship. Also see Documents Related to Nevada Test Site

198

DOE - Office of Legacy Management -- Maryland Disposal Site - MD 05  

Office of Legacy Management (LM)

Maryland Disposal Site - MD 05 Maryland Disposal Site - MD 05 FUSRAP Considered Sites Site: MARYLAND DISPOSAL SITE (MD.05 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Baltimore - Vicinity , Maryland MD.05-1 Evaluation Year: 1989 MD.05-1 Site Operations: Proposed disposal site - never developed. MD.05-1 Site Disposition: Eliminated Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Indicated Radiological Survey(s): None Indicated Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to MARYLAND DISPOSAL SITE MD.05-1 - Report (DOE/OR/20722-131 Revision 0); Site Plan for the Maryland Disposal Site; April 1989 Historical documents may contain links which are no longer valid or to

199

DOE - Office of Legacy Management -- Trinity Test Site - NM 17  

Office of Legacy Management (LM)

Trinity Test Site - NM 17 Trinity Test Site - NM 17 FUSRAP Considered Sites Site: TRINITY TEST SITE (NM.17 ) Eliminated from consideration under FUSRAP - U.S. Army controls site Designated Name: Not Designated Alternate Name: None Location: missile range - 30 miles west of Carrizozo , White Sands , New Mexico NM.17-1 Evaluation Year: 1985 NM.17-1 Site Operations: Detonation of the first atomic bomb occurred at this site. NM.17-1 Site Disposition: Eliminated NM.17-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Fission fragments NM.17-1 Radiological Survey(s): NM.17-1 Site Status: Eliminated from consideration under FUSRAP - U.S. Army controls site NM.17-1 Also see Documents Related to TRINITY TEST SITE NM.17-1 - DOE Memorandum/Checklist; Jones to File; Subject:

200

DOE - Office of Legacy Management -- Project Gas Buggy Site - NM 14  

Office of Legacy Management (LM)

Gas Buggy Site - NM 14 Gas Buggy Site - NM 14 FUSRAP Considered Sites Site: Project Gas Buggy Site (NM.14 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Gasbuggy, New Mexico, Site Nevada Test Site History Documents Related to Project Gas Buggy Site Fact Sheet Gasbuggy, New Mexico The Gasbuggy Site is located in northwestern New Mexico in Rio Arriba County approximately 55 miles east of the city of Farmington and approximately 12 miles southwest of Dulce, New Mexico, in the Carson National Forest. Floodplains and Wetlands Survey Results for the Gasbuggy and Gnome-Coach Sites, New Mexico, December 1993.

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

Radiological Areas  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Revision to Clearance Policy Associated with Recycle of Scrap Metals Originating from Revision to Clearance Policy Associated with Recycle of Scrap Metals Originating from Radiological Areas On July 13, 2000, the Secretary of Energy imposed an agency-wide suspension on the unrestricted release of scrap metal originating from radiological areas at Department of Energy (DOE) facilities for the purpose of recycling. The suspension was imposed in response to concerns from the general public and industry groups about the potential effects of radioactivity in or on material released in accordance with requirements established in DOE Order 5400.5, Radiation Protection of the Public and Environment. The suspension was to remain in force until DOE developed and implemented improvements in, and better informed the public about, its release process. In addition, in 2001 the DOE announced its intention to prepare a

202

Dental Radiology  

Science Journals Connector (OSTI)

Dental radiology is the core diagnostic modality of veterinary dentistry. Dental radiographs assist in detecting hidden painful pathology, estimating the severity of dental conditions, assessing treatment options, providing intraoperative guidance, and also serve to monitor success of prior treatments. Unfortunately, most professional veterinary training programs provide little or no training in veterinary dentistry in general or dental radiology in particular. Although a technical learning curve does exist, the techniques required for producing diagnostic films are not difficult to master. Regular use of dental x-rays will increase the amount of pathology detected, leading to healthier patients and happier clients who notice a difference in how their pet feels. This article covers equipment and materials needed to produce diagnostic intraoral dental films. A simplified guide for positioning will be presented, including a positioning “cheat sheet” to be placed next to the dental x-ray machine in the operatory. Additionally, digital dental radiograph systems will be described and trends for their future discussed.

Tony M. Woodward

2009-01-01T23:59:59.000Z

203

DOE - Office of Legacy Management -- Beverly MA Site - MA 04  

Office of Legacy Management (LM)

Beverly MA Site - MA 04 Beverly MA Site - MA 04 FUSRAP Considered Sites Beverly, MA Alternate Name(s): Metal Hydrides, Inc. Ventron Corporation MA.04-1 Location: Congress Street, Beverly, Massachusetts MA.04-4 Historical Operations: Provided uranium metal production under contract with MED. Thorium and radium contamination occurred from non-MED operations. MA.04-6 Eligibility Determination: Eligible MA.04-1 Radiological Survey(s): Assessment Survey, Verification Survey MA.04-4 MA.04-7 Site Status: Certified- Certification Basis, Federal Register Notice included MA.04-5 MA.04-6 MA.04-7 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP Also see Beverly, MA, Site Documents Related to Beverly, MA Beverly Site Aerial Photograph

204

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

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

205

General Employee Radiological Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-HDBK-1131-2007 iii Foreword This Handbook describes an implementation process for core training as recommended in chapter 14, Radiation Safety Training, of Implementation Guide G44.1B, Radiation Protection Programs Guide, and as outlined in the DOE Radiological Control Standard [RCS - DOE-STD-1098-99, Ch. 1]. The Handbook is meant to assist those individuals

206

Radiological Source Registry and Tracking  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Source Registry and Tracking (RSRT) Radiological Source Registry and Tracking (RSRT) Home HSS Logo Radiological Source Registry and Tracking (RSRT) Department of Energy (DOE) Notice N 234.1 Reporting of Radioactive Sealed Sources has been superseded by DOE Order O 231.1B Environment, Safety and Health Reporting. O 231.1B identifies the requirements for centralized inventory and transaction reporting for radioactive sealed sources. Each DOE site/facility operator that owns, possesses, uses or maintains in custody those accountable radioactive sealed sources identified in Title 10 Code of Federal Regulation Part 835, Occupational Radiation Protection (10 CFR 835), Appendix E, and International Atomic Energy Agency (IAEA) Categories 1 and 2 radioactive sealed sources identified in Attachment 5, Appendix A of O 321.1B, will submit information to the DOE Radiological Source Registry and Tracking (RSRT) System.

207

DOE - Office of Legacy Management -- St Louis Airport Site Vicinity  

Office of Legacy Management (LM)

St Louis Airport Site Vicinity St Louis Airport Site Vicinity Properties - 017 FUSRAP Considered Sites Site: St. Louis Airport Site Vicinity Properties (017) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: These properties are located in Hazelwood and Berkeley, Missouri, approximately 15 miles northwest of downtown St. Louis. The properties are associated with the St. Louis Airport Site. The Manhattan Engineer District (MED), a predecessor agency of the U.S. Department of Energy (DOE), acquired the St. Louis Airport Site in 1946. The site was operated by the MED and the Atomic Energy Commission (the successor agency to the MED and a

208

DOE - Office of Legacy Management -- Gunnison Mill Site - CO 0-06  

Office of Legacy Management (LM)

Gunnison Mill Site - CO 0-06 Gunnison Mill Site - CO 0-06 FUSRAP Considered Sites Site: Gunnison Mill Site (CO.0-06 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Gunnison, Colorado, Processing Site Documents Related to Gunnison Mill Site Verification Montioring Report for the Gunnison, Colorado, Processing Site, September 2007. 2011 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites-Gunnison, Colorado, Disposal Site. LMS/S08056. January 2012 U.S. Department of Energy 2009 UMTRCA Title I Annual Report January 2010 Gunnison, Colorado Page 8-1 8.0 Gunnison, Colorado, Disposal Site

209

DOE - Office of Legacy Management -- Green River Mill Site - UT 0-01  

Office of Legacy Management (LM)

Green River Mill Site - UT 0-01 Green River Mill Site - UT 0-01 FUSRAP Considered Sites Site: Green River Mill Site (UT.0-01 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Green River, Utah, Disposal Site Documents Related to Green River Mill Site Data Validation Package for the June 2009 Groundwater and Surface Water Sampling at the Green River, Utah, Disposal Site; LMS/GRN/S0609; October 2009 2012 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites-Green River, Utah, Disposal Site. LMS/S09461. February 2013 Historic Fact Sheet: Green River Disposal Site Uranium ore was

210

Ground-penetrating radar survey of the Maxey Flats Low-Level Nuclear Waste Disposal Site, Fleming County, Kentucky  

SciTech Connect

A ground-penetrating radar survey was conducted at the Maxey Flats Low-Level Nuclear Waste Disposal Site, Kentucky, to more accurately determine the location of burial trenches and pits, and to identify locations and depths of any prominent subsurface features. A geologic/electromagnetic model of the site was developed and utilized for analysis of the acquired data. Depths of penetration derived from radar records correlate well with those calculated from the model. A final interpretation of the radar data is presented.

Horton, K.A.; Morey, R.M.

1982-06-01T23:59:59.000Z

211

Estimating radiological background using imaging spectroscopy  

SciTech Connect

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

212

RADIOLOGICAL SURWY  

Office of Legacy Management (LM)

111 111 j -,~ ' - et- -*\. _(a v - r\lfs+8 plY 45+ c iill I r\l&; p) :;!I..; .: .. :,, ,m -,< :' - ' ec-. :-*% ". _(.*- ~ . . : : : ' .. : : : .. ..:, . . . :. : : ,, :;I;:~~:; :.:.!,;;y ' 1;: .: 1. .., ; ' . :. : c :...: .;: .: RADIOLOGICAL SURWY - RADIoL~BI~L.::.~~~y:- : ::: 1 ,: . . : : :: :. :..." - OFi~:,~~~~:poRTI~~~ 0J-g ,m_ ,. :. y.;,:. ,.:I; .:. F~~~~~~as~~~ ~~~~~~~:~~~~ :co~~~:~~~~~; ;, .. ; I : : ::.. :.. :. - ,B~~Lo,.~-~~~. ..; .:I ,,,, :--:.;:I:: ;' #I Y' i ' 11". .. .. ; :;: ;I, ' . 1::. J;,;. ~;_:y,;:::::; - T.J..:+~uS~~ .' .:' : : . . .. ...: .:.. : OFTHE EXCERIORPORTIONS O F THE FORIMER BLISS ANT3 LAUGHLIN STEEL COMPANY FAC' KJTy - BUFFALO,NEw YORK - T. J.VITKUS I : . . : : ' . .:. : I : : .. :. Prepaied for.:the:' 6ffice.iibfiEnvir~nmenfal Re$o&idn z . . :

213

DOE - Office of Legacy Management -- Hamilton OH Site - OH 27  

Office of Legacy Management (LM)

Hamilton OH Site - OH 27 Hamilton OH Site - OH 27 FUSRAP Considered Sites Hamilton, OH Alternate Name(s): Herring-Hall-Marvin Safe Company Diebold Incorporated OH.27-2 Location: 1550 Grand Boulevard, Hamilton, Ohio OH.27-2 Historical Operations: Machined uranium metal slugs from rolled stock, under subcontract with National Lead, an MED contractor. OH.27-3 OH.27-4 OH.27-9 Eligibility Determination: Eligible OH.27-1 Radiological Survey(s): Assessment Surveys, Verification Survey OH.27-1 OH.27-5 OH.27-6 OH.27-7 Site Status: Certified - Certification Basis, Federal Register Notice included OH.27-8 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP Also see Hamilton, OH Site Documents Related to Hamilton, OH

214

DOE - Office of Legacy Management -- Columbus East OH Site - OH 26  

Office of Legacy Management (LM)

Columbus East OH Site - OH 26 Columbus East OH Site - OH 26 FUSRAP Considered Sites Columbus East, OH Alternate Name(s): B&T Metals Site OH.26-1 Location: 425 West Town Street, Columbus, Ohio OH.26-3 Historical Operations: Performed extrusion and machining on natural uranium metal billets to support MED. OH.26-4 OH.26-7 Eligibility Determination: Eligible OH.26-1 OH.26-2 Radiological Survey(s): Assessment Survey, Verification Survey OH.26-5 OH.26-6 Site Status: Certified - Certification Basis, Federal Register Notice included OH.26-8 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP Also see Columbus East, OH, Site Documents Related to Columbus East, OH Columbus East Site Aerial Photograph FACT SHEET Office of Legacy Management Columbus East, Ohio, Site

215

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

216

DOE - Office of Legacy Management -- Tuba City Mill Site - AZ 0-02  

Office of Legacy Management (LM)

Mill Site - AZ 0-02 Mill Site - AZ 0-02 FUSRAP Considered Sites Site: Tuba City Mill Site (AZ.0-02 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Tuba City, Arizona, Disposal Site Documents Related to Tuba City Mill Site 2012 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites-Tuba City, Arizona, Disposal Site. LMS/S09461. February 2013 2008 UMTRCA Title I Annual Report January 2009 Tuba City, Arizona February 2009 Groundwater and Surface Water Sampling at the Tuba City, Arizona Disposal Site May 2009 This fact sheet provides information about the Uranium Mill Tailings

217

DOE - Office of Legacy Management -- Palos Park Forest Preserve Site (A  

Office of Legacy Management (LM)

Palos Park Forest Preserve Site (A Palos Park Forest Preserve Site (A Plot M) - IL 04 FUSRAP Considered Sites Site: Palos Park Forest Preserve Site (A/Plot M) (IL.04 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Site A/Plot M, Illinois, Decommissioned Reactor Site Documents Related to Palos Park Forest Preserve Site (A/Plot M) Surveillance of Site A and Plot M Report for 2011. ANL-12/01 Surveillance of Site A and Plot M Report for 2007 Environment, Safety, and Health/Quality Assurance Oversight Division Surveillance of Site A and Plot M Report for 2009. ANL-10/01. April 2010 U.S. Department of Energy Office of Legacy Management Environmental

218

DOE - Office of Legacy Management -- Rifle Mill Site - CO 0-11  

Office of Legacy Management (LM)

Rifle Mill Site - CO 0-11 Rifle Mill Site - CO 0-11 FUSRAP Considered Sites Site: Rifle Mill Site (CO.0-11 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Rifle, Colorado, New Processing Site Rifle, Colorado, Old Processing Site Documents Related to Rifle Mill Site 2009 Verification Monitoring Report for the Old and New Rifle, Colorado, Processing Sites; LMS/RFO/RFN/S05775; September 2009. This report evaluates and interprets groundwater monitoring data collected at the Old and New Rifle Sites and assesses the progress of meeting the compliance strategy for groundwater cleanup. 2012 Annual Site Inspection and Monitoring Report for Uranium Mill

219

DOE - Office of Legacy Management -- Naturita Mill Site - CO 0-08  

Office of Legacy Management (LM)

Naturita Mill Site - CO 0-08 Naturita Mill Site - CO 0-08 FUSRAP Considered Sites Site: Naturita Mill Site (CO.0-08) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Naturita, Colorado, Processing Site Documents Related to Naturita Mill Site Data Validation Package for the July and October 2008 Water Sampling at the Naturita Processing and Disposal Sites Data Validation Report for the July 2009 Groundwater and Surface Water Sampling at the Naturita, Colorado, Processing Site; LMS/NAP/S00709; October 2009 2012 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites-Naturita, Colorado,

220

DOE - Office of Legacy Management -- Slick Rock Mill Site - CO 08  

NLE Websites -- All DOE Office Websites (Extended Search)

Slick Rock Mill Site - CO 08 Slick Rock Mill Site - CO 08 FUSRAP Considered Sites Site: Slick Rock Mill Site (CO.08) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Slick Rock, Colorado, Processing Site Documents Related to Slick Rock Mill Site 2012 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites-Slick Rock, Colorado, Disposal Site. LMS/S09461. February 2013 Verification Monitoring Report for the Slick Rock, Colorado, Processing Sites, 2007 Update June 2008 Office of Legacy Management DOE M/1577 2008 - -L Work Performed Under DOE Contract No. for the U.S.

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

DOE - Office of Legacy Management -- Shoal Test Site - NV 03  

Office of Legacy Management (LM)

Shoal Test Site - NV 03 Shoal Test Site - NV 03 FUSRAP Considered Sites Site: SHOAL TEST SITE (NV.03 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Sand Springs Range NV.03-1 Location: Near U.S. Highway 50 , Fallon , Nevada NV.03-2 Evaluation Year: 1987 NV.03-2 Site Operations: Underground nuclear detonation site. NV.03-1 Site Disposition: Eliminated - Potential for contamination remote NV.03-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: None at the Surface and Fission Fragments Within the Subsurface NV.03-1 Radiological Survey(s): Yes Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to SHOAL TEST SITE NV.03-1 - Report (NVO-1229-105 Part I); Evaluation of the Project

222

NIAGARA FALLS STORAGE SITE  

Office of Legacy Management (LM)

:i" :i" _,, ' _~" ORISE 95/C-70 :E : i:; :' l,J : i.: RADIOLOGICAL SURVEY Op BUILDINGS 401, ' 403, AND ' m HITTMAN BUILDING $ <,' 2:. NIAGARA FALLS STORAGE SITE I .~~ ; " LEWISTON, ' NEW YORK : f? j:,:i I ,.J- ;b f" /: Li _e.*. ~,, I ,,~, ,:,,;:, Prepared by T. .I. Vitkus i,c Environmental Survey and Site Assessment Program Energy/Environment Systems Division ;>::; Oak Ridge Institute for Science and Education .,:, "Oak Ridge, Temressee 37831-0117 .F P ., ? :_ &,d ,,,, ;<:x,, Prepared for the 3 I. Office of Environmental Restoration I, U.S. Department of Energy i gy i. ~: ,,, "! ? ' :' : "' ,//, FINAL REPORT ".$ :,a ,,, MARCH 1995 ; m L ,, ,, ,,,. ., ,,. ' 1 jq ,Ij:,., .,~ _,I_ 1 This report is based on work performed under contract number DE-AC05-760R00033 with the

223

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Change Notice No. 1 2009 Change Notice No. 2 2011 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009 Original Change Part 3 1.05-1 NCRP Report No. 93 "Ionizing Radiation Exposure of the Population of the United States". NCRP Report No. 160 "Ionizing Radiation Exposure of the Population

224

5 - Medical Considerations for Radiological Terrorism  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the medical considerations for radiological terrorism. Radiological warfare (RW) attack is the deliberate use of radiological materials to cause injury and death. The explosion of a radiological weapon causes damage by the heat and blast liberated at the time of detonation. The proliferation of nuclear material and technology has made the acquisition and terrorist use of ionizing radiation more probable than ever. Currently, there are three threat scenarios for radiological terrorism. The most probable scenario for the near future would be a radiological dispersion device. Such a weapon can be developed and used by any terrorist with conventional weapons and access to radionuclides. This is an expedient weapon in that the radioactive waste material is easy to obtain from any location that uses radioactive sources. These sites can include a nuclear-waste processor, a nuclear power plant, a university research facility, a medical radiotherapy clinic, or an industrial complex.

James Winkley; Paul D. Mongan

2006-01-01T23:59:59.000Z

225

Radiological Control  

National Nuclear Security Administration (NNSA)

materials, such as pipelines, radioactive cribs, covered ponds, covered ditches, catch tanks, inactive burial grounds, and sites of known, covered, unplanned releases (spills)....

226

DOE - Office of Legacy Management -- West Milton Reactor Site - NY 21  

Office of Legacy Management (LM)

Milton Reactor Site - NY 21 Milton Reactor Site - NY 21 FUSRAP Considered Sites Site: West Milton Reactor Site (NY.21) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This site is one of a group of 77 FUSRAP considered sites for which few, if any records are available in their respective site files to provide an historical account of past operations and their relationship, if any, with MED/AEC operations. Reviews of contact lists, accountable station lists, health and safety records and other documentation of the period do not provide sufficient information to warrant further search of historical records for information on these sites. These site files remain "open" to

227

DOE - Office of Legacy Management -- Fairfield OH Site - OH 23  

NLE Websites -- All DOE Office Websites (Extended Search)

Fairfield OH Site - OH 23 Fairfield OH Site - OH 23 FUSRAP Considered Sites Fairfield, OH Alternate Name(s): Associate Aircraft Tool & Manufacturing, Inc. Associated Aircraft Tool and Manufacturing Company Force Control Industries Former Dixie Machinery OH.23-1 OH.23-2 Location: 3660 Dixie Highway, Fairfield, Ohio OH.23-2 Historical Operations: Produced natural uranium hollow slugs, resulting in uranium metal contamination. OH.23-4 OH.23-5 Eligibility Determination: Eligible OH.23-1 OH.23-2 Radiological Survey(s): Assessment Survey, Verification Survey OH.23-3 OH.23-6 Site Status: Certified - Certification Basis, Federal Register Notice included OH.23-7 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

228

DOE - Office of Legacy Management -- Buffalo NY Site - NY 54  

NLE Websites -- All DOE Office Websites (Extended Search)

Buffalo NY Site - NY 54 Buffalo NY Site - NY 54 FUSRAP Considered Sites Buffalo, NY Alternate Name(s): Bliss & Laughlin Steel Company Niagara Cold Drawn Steel Corporation Ramco Steel Incorporated NY.54-1 NY.54-4 Location: 110 Hopkins Street, Buffalo, New York NY.54-1 Historical Operations: Machined and straightened uranium rods as subcontracted work from National Lead Company, an AEC contractor. NY.54-3 NY.54-4 LTSM012601 Eligibility Determination: Eligible NY.54-4 Radiological Survey(s): Assessment Surveys, Verification Surveys NY.54-6 NY.54-7 NY.54-8 LTSM012601 Site Status: Certified- Certification Basis and Certification Statement BLS000001 LTSM012152 LTSM012584 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

229

Hospital Triage in First Hours After Nuclear or Radiological...  

NLE Websites -- All DOE Office Websites (Extended Search)

Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster Medical professionals with the Radiation Emergency Assistance CenterTraining Site (REACTS) at the...

230

Survey of ecological resources at selected US Department of Energy sites  

SciTech Connect

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

231

Standardized radiological dose evaluations  

SciTech Connect

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

232

Implementation of a Radiological Safety Coach program  

SciTech Connect

The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.

Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

1998-02-01T23:59:59.000Z

233

SURVEY OF ROLLING MILL USED BY BETHLEHEM STEEL CORPORATION LACKAWANNA, NEW YORK  

Office of Legacy Management (LM)

SURVEY OF ROLLING MILL USED BY SURVEY OF ROLLING MILL USED BY BETHLEHEM STEEL CORPORATION LACKAWANNA, NEW YORK Work performed by the Health and Safety Research Division Gak Ridge fiational Laboratory Oak Ridge, Tennessee 37830 September 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites!- Remedial Action Program SURVEY OF ROLLING MILL USED BY BETHLEHEM STEEL CORPORATION LACKAWANNA, NEW YORK A radiological survey was conducted at the Bethelem Steel Corporation Plant in Lackawanna, New York, on September 23, 1980, by representatives of Oak Ridge National Laboratory (ORNL). The subject of the radiological survey was a portion of the original 25.4-cm (lo-inch) bar mill used in converting uranium billets into 3.8-cm rods. All radiation survey

234

For S Radiological  

Office of Legacy Management (LM)

? . ? . -. .- * -* (\/If.r.-5- .* , d- For S Radiological ' mer Bridgepo pecial Metals Adrian, Survey of the Irt Brass Company Extrusion Plant, Michigan / /f?t' . ( F. F. Haywood H. W. Dickson W. D. Cottrell W. H. Shinpaugh _ : I., _-. .I ( ._ rc/ DOE/EV-0005128 ORNL-57 13 / J. E. Burden 0. R. Stone R. W. Doane W. A. Goldsmith 4 , Printed in the United States of America. Available from National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road, Springfield, Virginia 22161 NTIS price codes-Printed Copy: A06 Microfiche A01 This report was prepared as an account of work sponsored by an agency of the UnitedStatesGovernment. Neither theUnitedStatesGovernment noranyagency thereof, nor any of their employees, makes any warranty, express or implied, or

235

DOE - Office of Legacy Management -- Riverton Mill Site - WY 0-04  

Office of Legacy Management (LM)

Mill Site - WY 0-04 Mill Site - WY 0-04 FUSRAP Considered Sites Site: Riverton Mill Site (WY.0-04 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Riverton, Wyoming, Processing Site Documents Related to Riverton Mill Site Data Validation Package for the November 2008 Groundwater and Surface Water Sampling at the Riverton, Wyoming, Processing Site. February 2009 U. S. Department of Energy (DOE) Status and Planned Actions at the Riverton, Wyoming, Uranium Mill Tailing Radiation Control Act (UMTRCA) Title I Site April Gil, PhD Environment Team Lead Office of Legacy Management (LM) May 2, 20122 Status and Action Summary 􀂄 Surface

236

DOE - Office of Legacy Management -- Monument Valley Mill Site - AZ 0-01  

Office of Legacy Management (LM)

Monument Valley Mill Site - AZ 0-01 Monument Valley Mill Site - AZ 0-01 FUSRAP Considered Sites Site: Monument Valley Mill Site (AZ.0-01) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Monument Valley, Arizona, Processing Site Documents Related to Monument Valley Mill Site Data Validation Package for the June 2009 Water Sampling at the Monument Valley, Arizona, Processing Site; LMS/MON/S0609; October 2009 Natural and Enhanced Attenuation of Soil and Ground Water at Monument Valley, Arizona, and Shiprock, New Mexico 2006 Status Report June 2008 Data Validation Package for 2007 Groundwater Sampling at the Monument Valley, AZ Processing Site

237

DOE - Office of Legacy Management -- Spook Site - WY 0-01  

Office of Legacy Management (LM)

Spook Site - WY 0-01 Spook Site - WY 0-01 FUSRAP Considered Sites Site: Spook Site (WY.0-01) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Documents Related to Spook Site 2012 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites-Spook, Wyoming, Disposal Site. LMS/S09461. February 2013 U.S. Department of Energy 2008 UMTRCA Title I Annual Report January 2009 Spook, Wyoming U.S. Department of Energy 2007 UMTRCA Title I Annual Report December 2007 Spook, Wyoming FACT SHEET - Spook, Wyoming This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I

238

DOE - Office of Legacy Management -- Berkeley CA Site - CA 03  

Office of Legacy Management (LM)

Berkeley CA Site - CA 03 Berkeley CA Site - CA 03 FUSRAP Considered Sites Berkeley, CA Alternate Name(s): University of California Gilman Hall, University of California CA.03-1 Location: Gilman Hall, University of California, Berkeley, California CA.03-1 Historical Operations: Performed research and development on the synthesis and production of plutonium, resulting in uranium, plutonium, cesium and americium contamination. CA.03-3 CA.03-5 Eligibility Determination: Eligible CA.03-1 CA.03-2 Radiological Survey(s): Assessment Surveys CA.03-3 CA.03-4 Site Status: Certified- Certification Basis and Certification Statement CA.03-5 CA.03-6 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP Also see Berkeley, CA, Site

239

DOE - Office of Legacy Management -- Maywood Site - NJ 10  

Office of Legacy Management (LM)

Maywood Site - NJ 10 Maywood Site - NJ 10 FUSRAP Considered Sites Maywood, NJ Alternate Name(s): Maywood Chemical Works Maywood Chemical Company Maywood Interim Storage Site (MISS) Stepan Chemical Company NJ.10-2 NJ.10-3 NJ.10-7 NJ.10-11 Location: 100 West Hunter Avenue, Maywood/Rochelle Park, New Jersey NJ.10-4 Historical Operations: Processed monazite sands for extraction of rare earth compounds and mantle-grade thorium nitrates. NJ.10-2 NJ.10-3 NJ.10-4 NJ.10-5 Eligibility Determination: Eligible NJ.10-1 NJ.10-10 Radiological Survey(s): Assessment Surveys NJ.10-6 NJ.10-7 NJ.10-8 Site Status: Cleanup in progress by U.S. Army Corps of Engineers. NJ.10-9 NJ.10-13 USACE FUSRAP Long-term Care Requirements: To be determined upon completion. Also see FUSRAP Maywood Superfund Site

240

Digital Surveying Directional Surveying Specialists | Open Energy  

Open Energy Info (EERE)

Digital Surveying Directional Surveying Specialists Digital Surveying Directional Surveying Specialists Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Digital Surveying Directional Surveying Specialists Author Directional Surveying Specialists Published Publisher Not Provided, 2012 DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Digital Surveying Directional Surveying Specialists Citation Directional Surveying Specialists. Digital Surveying Directional Surveying Specialists [Internet]. 2012. [cited 2013/10/08]. Available from: http://www.digitalsurveying.co.za/services/geophysical-borehole-surveying/overview/optical-televiewer/ Retrieved from "http://en.openei.org/w/index.php?title=Digital_Surveying_Directional_Surveying_Specialists&oldid=690244"

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

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

SciTech Connect

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

242

Radiological Worker Training - Radiological Safety Training for Radiation Producing (X-Ray) Devices  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

C C December 2008 DOE HANDBOOK Radiological Worker Training Radiological Safety Training for Radiation Producing (X-Ray) Devices U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management

243

Nevada Site Celebrates 2014, Makes Way for 2015 | Department...  

Office of Environmental Management (EM)

Station on the NNSS. A technician collects radiological measurements at the Tonopah Test Range cleanup site. A technician collects radiological measurements at the Tonopah Test...

244

RADIOLOGICAL ASSESSMENT  

Office of Legacy Management (LM)

ASSESSMENT ASSESSMENT and STABILIZATION' SCENARIOS PARRERSBURG,'W. VA. SITE FEBRUARY 1980 M. CARSON J. COFFMAN N. MANDELTORT, ! Division of Nuclear Service Operations Chem-Nuclear\ Systems, Inc. 240 Stoneridge Dr., Suite 100 Columbia, South Carolina 29210 Prepared for AMAX Specialty Hetals Corporation One Greenwich Plaza Greenwich, Connecticut 06830 During July' 1978, Chem-Nuclear Systems, Inc. (CNSI) began an assessment program for AMAX Specialty Metals Corp."(AMAX) u to locate, quantify, and evaluate the'extent of environmental radioactive contamination at the AMAX Parkersburg., West Virginia former zirconium/hafnium processing facility. In addition, preliminary ive assessments were to be made to assist AMAX in evaluat ,ing alternat methods for site cleanup.

245

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

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

246

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Instructor's Guide Instructor's Guide 2.17-1 Course Title: Radiological Control Technician Module Title: Contamination Monitoring Instrumentation Module Number: 2.17 Objectives: 2.17.01 List the factors which affects an RCT's selection of a portable contamination monitoring instrument. L 2.17.02 Describe the following features and specifications for commonly used count rate meter probes used at your site for beta/gamma and/or alpha surveys: a. Detector type b. Detector shielding and window c. Types of radiation detected/measured d. Energy response for measured radiation e. Specific limitations/characteristics L 2.17.03 Describe the following features and specifications for commonly used count rate instruments used at your site: a. Types of detectors available for use b. Operator-adjustable controls

247

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TS TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 December 2008 Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 2 DOE-HDBK-1130-2008 Original Change Throughout Program Management Guide Instructor's Guide Student's Guide "Shall" and "Must" statements Program Management Instructor's Material Student's Material Reworded to non-mandatory language unless associated with a requirement document.

248

General Employee Radiological Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Not Measurement Not Measurement Sensitive DOE-HDBK-1131-2007 December 2007_______ Change Notice 1 Reaffirmed 2013 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The average annual radiation dose to a member of the general population is about 360 millirem/year. The average annual radiation dose to a member of the general population is about 620 millirem/year. Part 2 page 5 Natural background radiation is by far the

249

General Employee Radiological Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

_______ _______ Change Notice 1 June 2009 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The average annual radiation dose to a member of the general population is about 360 millirem/year. The average annual radiation dose to a member of the general population is about 620 millirem/year. Part 2 page 5 Natural background radiation is by far the

250

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8 8 December 2008 Change Notice 1 June 2009 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1130-2008 Original Change Part 2 Module 2 page 17 Medical radiation sources (total average dose ~ 54 mrem/yr) 1) X rays (total average dose ~ 40mrem/yr) a) X rays are similar to gamma rays; however, they originate outside the nucleus.

251

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TS TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 December 2008 Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 2 DOE-HDBK-1130-2008 Original Change Throughout Program Management Guide Instructor's Guide Student's Guide "Shall" and "Must" statements Program Management Instructor's Material Student's Material Reworded to non-mandatory language unless associated with a requirement document.

252

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

_______ _______ Change Notice 1 June 2009 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009 Original Change Part 3 1.05-1 NCRP Report No. 93 "Ionizing Radiation Exposure of the Population of the United States". NCRP Report No. 160 "Ionizing Radiation Exposure of the Population of the United States". Part 3 1.05-9 4) U.S. national average from diagnostic

253

SUWECT:' .El,imination of Sites from the Formerly Utilized Sites RemediaTAction  

Office of Legacy Management (LM)

SUWECT:' .El,imination of Sites from the Formerly Utilized Sites RemediaTAction SUWECT:' .El,imination of Sites from the Formerly Utilized Sites RemediaTAction * .,, * < ,. -. Program " -:. " : ,. .: . . ., ", ~0: The File ',. ,.'. .., ,, I' ; ,. : 2 ., %" The'facili.ties'listed belbw have been evaluated'tb determine if remedial .,.action underthe,Formerl,y Utili,zed 'Sites%Remedial,Action :Program (FUSRAP) ',' is warranted. The evaluations consisted of record searches, interviews, site visits, and radiological surveys;,' Based onthis information, which is'summarized'in the attached eltmination reports, the Department of Energy has'detenained that the potential for contamination 'at these sites is low. Accordingly, these,sites, have been eliminated from further consideration under FUSRAP. : .: "

254

DOE - Office of Legacy Management -- Indian Orchard MA Site - MA 08  

NLE Websites -- All DOE Office Websites (Extended Search)

Indian Orchard MA Site - MA 08 Indian Orchard MA Site - MA 08 FUSRAP Considered Sites Indian Orchard, MA Alternate Name(s): Chapman Valve Manufacturing Company Chapman Valve Site Crane Company MA.08-3 MA.08-4 Location: 203 Hampshire Street, Indian Orchard, Massachusetts MA.08-2 Historical Operations: Machined extruded natural uranium rods and supplied valves and other products to MED and AEC. Also machined natural uranium rods into slugs for Brookhaven National Laboratory. MA.08-6 MA.08-7 MA.08-8 MA.08-14 Eligibility Determination: Eligible MA.08-2 Radiological Survey(s): Assessment Survey, Verification Survey MA.08-11 MA.08-12 Site Status: Certified - Certification Basis, Federal Register Notice included. MA.08-13 MA.08-14 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

255

DOE - Office of Legacy Management -- New York, NY, Site - NY 61  

Office of Legacy Management (LM)

York, NY, Site - NY 61 York, NY, Site - NY 61 FUSRAP Considered Sites New York, NY Alternate Name(s): Baker and Williams Warehouses Ralph Ferrara Company Warehouses Ralph Ferrara, Inc. NY.61-2 Location: 513-519, 521-527, and 529-535 West 20th Street, New York, New York NY.61-3 Historical Operations: Received and stored uranium ores and concentrates for MED. NY.61-5 NY.61-6 NY.61-7 Eligibility Determination: Eligible NY.61-1 NY.61-2 Radiological Survey(s): Assessment Surveys, Verification Surveys NY.61-3 NY.61-4 NY.61-8 NY.61-9 NY.61-10 Site Status: Certified - Certification Basis, Federal Register Notice Included NY.61-11 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP Also see New York, New York, Site

256

DOE - Office of Legacy Management -- New Brunswick NJ Site - NJ 14  

Office of Legacy Management (LM)

Brunswick NJ Site - NJ 14 Brunswick NJ Site - NJ 14 FUSRAP Considered Sites New Brunswick, NJ Alternate Name(s): New Brunswick Laboratory NJ.14-1 Location: 986 Jersey Avenue, New Brunswick, New Jersey NJ.14-2 Historical Operations: Performed radiochemical analyses on uranium, thorium, beryllium, and zirconium metals and compounds for MED, AEC, ERDA, and DOE to support nuclear power and weapons programs. NJ.14-3 NJ.14-5 Eligibility Determination: Eligible NJ.14-1 Radiological Survey(s): Assessment Surveys, Verification Surveys NJ.14-2 NJ.14-4 NJ.14-6 Site Status: Certification Basis, Federal Register Notice Included NJ.14-5 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP Also see New Brunswick, New Jersey, Site

257

DOE - Office of Legacy Management -- Chicago North IL Site - IL 05  

Office of Legacy Management (LM)

North IL Site - IL 05 North IL Site - IL 05 FUSRAP Considered Sites Chicago North, IL Alternate Name(s): National Guard Armory 124th Field Artillery Armory Illinois National Guard Armory Site IL.05-4 IL.05-5 Location: 5200 Cottage Grove Avenue, Chicago, Illinois IL.05-4 Historical Operations: Processed and stored uranium metal, resulting in uranium metal and dry uranium oxide contamination. Metallurgical operations were conducted by the University of Chicago, an MED contractor. IL.05-5 IL.05-7 IL.05-8 Eligibility Determination: Eligible IL.05-1 IL.05-2 IL.05-3 Radiological Survey(s): Assessment Surveys, Verification Surveys IL.05-6 IL.05-7 Site Status: Certified-Certification Basis, Federal Register Notice Included IL.05-7 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

258

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

SciTech Connect

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

259

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

SciTech Connect

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

260

Designation of Sites for Remedial Action - Metal Hydrides, Beverly,  

Office of Legacy Management (LM)

T: T: Designation of Sites for Remedial Action - Metal Hydrides, Beverly, MA; Bridgeport Brass, Adrian, MI and Seymour, Chicago, IL CT; National Guard Armory, 0: Joe LaGrone, Manager Oak Ridge Operations Office Based on the attached radiological survey data (Attachments 1 through 3) and an appropriate authority review, the following properties are being authorized for remedial action. It should be noted that the attached survey data are for designation purposes only and that Bechtel National, Inc. (BNI) should conduct appropriate comprehensive characterization studies to determine the extent'and magnitude of contamination on properties. Site Location Priority Former Bridgeport Brass Co. (General Motors) Adrian, MI Low Former Bridgeport Brass Co.

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

Electromagnetic Borehole Flowmeter Surveys at Selected In Situ Redox Manipulation Barrier Wells, Zero-Valent Iron Site, Hanford, Washington  

SciTech Connect

Ambient (i.e., static) and dynamic (i.e., pumping-induced) electromagnetic borehole flowmeter (EBF) surveys were performed in 10 selected In Situ Redox Manipulation (ISRM) barrier wells to characterize the distribution of in-well vertical flow conditions and to infer the relative hydraulic conductivity distribution in the upper-part of the unconfined aquifer. These wells are located in two areas where the aquifer is targeted for testing of zero-valent iron injection to mend a failed portion of the ISRM barrier at the 100 D Area, Hanford Site. Each of these two areas consists of a group of five wells, one group to the southwest and one group to the northeast. The upper ~15 to 20 ft (~4.6 to 6.1 m) of the unconfined aquifer was characterized for in-well vertical flow conditions and vertical profile information regarding relative hydraulic conductivity. At some well site locations, the upper ~2 to 3 ft (~0.6 to 1 m) of the well-screen interval could not be characterized under pumping (dynamic) conditions because of the presence of the pump.

Newcomer, Darrell R.

2009-02-09T23:59:59.000Z

262

DOE - Office of Legacy Management -- Bayo Canyon NM Site - NM 01  

NLE Websites -- All DOE Office Websites (Extended Search)

Bayo Canyon NM Site - NM 01 Bayo Canyon NM Site - NM 01 FUSRAP Considered Sites Bayo Canyon, NM Alternate Name(s): Bayo Canyon Area Bayo Canyon (TA-10) Site NM.01-2 Location: Canyon in the Pajarito Plateau Region in Los Alamos County, Los Alamos, NM NM.01-3 Historical Operations: Used in 1944-1961 by the MED and later AEC at Los Alamos National Laboratory as a firing site for conventional and high-explosives experiments involving natural and depleted uranium, strontium, and lanthanum as a radiation source for blast diagnosis. NM.01-3 NM.01-5 Eligibility Determination: Eligible NM.01-1 Radiological Survey(s): Assessment Survey NM.01-3 Site Status: Certified- Certification Basis NM.01-5 NM.01-6 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

263

An assessment of the radiological scenario around uranium mines in Singhbhum East district, Jharkhand, India  

Science Journals Connector (OSTI)

......radiological scenario around uranium mines in Singhbhum East district...radiological scenario around uranium-mining sites in the Singhbhum...3 The Royal Society. The Health Hazards of Depleted Uranium Munitions (2001) The Royal......

R. M. Tripathi; S. K. Sahoo; S. Mohapatra; A. C. Patra; P. Lenka; J. S. Dubey; V. N. Jha; V. D. Puranik

2012-07-01T23:59:59.000Z

264

Bibliography of reports by US Geological Survey personnel pertaining to underground nuclear testing and radioactive waste disposal at the Nevada Test Site, and radioactive waste disposal at the WIPP Site, New Mexico, January 1, 1979-December 31, 1979  

SciTech Connect

This bibliography presents reports released to the public between January 1, 1979, and December 31, 1979, by personnel of the US Geological Survey. Reports include information on underground nuclear testing and waste management projects at the NTS (Nevada Test Site) and radioactive waste projects at the WIPP (Waste Isolation Pilot Plant) site, New Mexico. Reports on Project Dribble, Tatum Dome, Mississippi, previously prepared as administrative reports and released to the public as 474-series reports during 1979 are also included in this bibliography.

Glanzman, V.M.

1980-01-01T23:59:59.000Z

265

PPPL Site Environmental Report  

SciTech Connect

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 2011,” are documented and certified to be correct.

Virginia Finley, Robeert Sheneman and Jerry Levine

2012-12-21T23:59:59.000Z

266

DOE - Office of Legacy Management -- Reactor Site - Fort Belvoir - VA 0-02  

NLE Websites -- All DOE Office Websites (Extended Search)

Reactor Site - Fort Belvoir - VA Reactor Site - Fort Belvoir - VA 0-02 FUSRAP Considered Sites Site: REACTOR SITE - FORT BELVOIR (VA.0-02 ) Eliminated from further consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: None Location: Fort Belvoir , Virginia VA.0-02-1 Evaluation Year: 1987 VA.0-02-1 Site Operations: No evidence of AEC involvement with reactor operations. AEC conducted health and safety inspections of this site. Probably a licensed operation. VA.0-02-1 Site Disposition: Eliminated - Referred to DOD VA.0-02-1 Radioactive Materials Handled: Reactor fuel Primary Radioactive Materials Handled: Reactor Fuel Radiological Survey(s): Health and safety inspections VA.0-02-1 Site Status: Eliminated from further consideration under FUSRAP - Referred to DOD VA.0-02-1

267

Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Safety 3 C #12;Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2013-2014 Page 1

Sheridan, Scott

268

Panoramic Radiology: Endodontic Considerations  

Science Journals Connector (OSTI)

Endodontics is concerned with the morphology, physiology, and pathology of the human dental pulp and periradicular tissues. Radiology is especially important for diagnosis in the...

2007-01-01T23:59:59.000Z

269

Radiological Assistance Program  

Directives, Delegations, and Requirements

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

270

PRELIMINARY SURVEY OF VITRO CORPORATION  

Office of Legacy Management (LM)

PRELIMINARY SURVEY OF VITRO CORPORATION (VITRO LABORATORIES) WEST ORANGE, NEW JERSEY Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Actton Program VITRO CORPORATION (VITRO LABORATORIES) WEST ORANGE, NEW JERSEY At the request of the Department of Energy (DOE), a preliminary survey was performed at the former Vitro Corporation Laboratory in West Orange, New Jersey (see Fig 1), on November 30, 1977, to assess the radiological status of those facilities utilized under Atomic Energy Commission (AEC) contract during the late 1950s and early 1960s. This

271

DOE - Office of Legacy Management -- Chupadera Mesa NM Site - NM 04  

Office of Legacy Management (LM)

Chupadera Mesa NM Site - NM 04 Chupadera Mesa NM Site - NM 04 FUSRAP Considered Sites Chupadera Mesa, NM Alternate Name(s): None Location: Approximately 28 miles northeast of the Trinity nuclear test site on the White Sands Missile Range, Northeast of Bingham, New Mexico NM.04-5 Historical Operations: Received the deposition of longer-lived radionuclides in the fallout from the nuclear test, primarily cesium-137, strontium-90, plutonium-239, cobalt-60, and europium-155. NM.04-2 NM.04-5 Eligibility Determination: No further action required. Radiation levels below cleaunup criteria. NM.04-1 NM.04-2 Radiological Survey(s): Assessment Surveys NM.04-3 NM.04-4 Site Status: NA - No Further Action Required NM.04-1 NM.04-2 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

272

DOE - Office of Legacy Management -- Middlesex North NJ Site - NJ 05  

Office of Legacy Management (LM)

Middlesex North NJ Site - NJ 05 Middlesex North NJ Site - NJ 05 FUSRAP Considered Sites Middlesex North, NJ Alternate Name(s): Middlesex Landfill Middlesex Municipal Landfill NJ.05-2 NJ.05-4 Location: Mountain Avenue to Bound Brook, Middlesex, New Jersey NJ.05-2 Historical Operations: Served as a disposal site for low-level radioactive pitchblende ore generated from activites at the Middlesex Sampling Plant. NJ.05-2 NJ.05-3 Eligibility Determination: Eligible NJ.05-1 Radiological Survey(s): Assessment Surveys NJ.05-3 NJ.05-4 Site Status: Certification Basis and Federal Register Notice. USACE determination for additional remediation is pending. NJ.05-5 NJ.05-6 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

273

DOE - Office of Legacy Management -- Jersey City NJ Site - NJ 07  

NLE Websites -- All DOE Office Websites (Extended Search)

Jersey City NJ Site - NJ 07 Jersey City NJ Site - NJ 07 FUSRAP Considered Sites Jersey City, NJ Alternate Name(s): Kellex Laboratory Jersey City Laboratory Kellex/Pierpont Vitro Corporation of America Delco-Levco Pierpont Property M.W. Kellogg Site NJ.07-1 NJ.07-2 NJ.07-6 Location: New Jersey Route 440 and Kellogg Street, Jersey City, New Jersey NJ.07-5 Historical Operations: Conducted research and development for MED and AEC on gaseous diffusion process for uranium enrichment using uranium hexaflouride and solvent extraction process for uranium recovery from ores. Also conducted solvent extraction of uranium and other byproducts from waste. Processes resulted in contamination of uranium, radium, and thorium. NJ.07-3 NJ.07-5 Eligibility Determination: Radiological Survey(s): Assessment Survey, Verification Survey NJ.07-4

274

DOE - Office of Legacy Management -- Granite City IL Site - IL 28  

Office of Legacy Management (LM)

Granite City IL Site - IL 28 Granite City IL Site - IL 28 FUSRAP Considered Sites Granite City, IL Alternate Name(s): Granite City Steel General Steel Industries General Steel Casings Corporation New Betatron Building IL.28-3 Location: 1417 State Street, Granite City, Illinois IL.28-3 Historical Operations: Under subcontract with Mallinckrodt and using a government-owned Betatron (magnetic induction electron accelerator), x-rayed natural uranium ingots and dingots to detect metallurgical flaws. Contamination from rubbing off of oxidized uranium during handling. IL.28-3 IL.28-5 Eligibility Determination: Eligible IL.28-1 IL.28-2 Radiological Survey(s): Assessment Surveys, Verification Survey IL.28-6 IL.28-7 IL.28-8 Site Status: Certified - Certification Basis, Federal Register Notice included IL.28-9

275

ADVANTAGES OF INVESTIGATING CHEMICAL AND RADIOLOGICAL CONSTITUENTS SIMULTANEOUSLY IN SOIL AND GROUNDWATER  

SciTech Connect

At some sites both chemical and radiological investigation of soil and groundwater is required for overall site characterization. While the planning and execution of investigation activities is usually completed to fulfill regulatory (i.e., United States Environmental Protection Agency or United States Nuclear Regulatory Commission) requirements, coordination of chemical and radiological investigation programs may provide an opportunity for reducing the duration of investigation activities and reducing overall project costs. There are several similarities in the chemical and radiological investigation processes that one can take advantage of in program design and execution to efficiently plan and execute chemical and radiological investigations simultaneously. At sites where both chemical and radiological constituents are being investigated in soil and groundwater, various steps can be taken during the investigation processes to combine chemical and radiological investigation and characterization activities. With proper planning, investigating chemical and radiological constituents simultaneously in soil and groundwater can reduce the project schedule and provide cost savings for overall characterization of the site.

Downey, H.; Shephard, E.; Walter, N.

2003-02-27T23:59:59.000Z

276

MCNP Techniques for Modeling Sodium Iodide Spectra of Kiwi Surveys  

SciTech Connect

This work demonstrates how MCNP can be used to predict the response of mobile search and survey equipment from base principles. The instrumentation evaluated comes from the U.S. Department of Energy’s Aerial Measurement Systems. Through reconstructing detector responses to various point-source measurements, detector responses to distributed sources can be estimated through superposition. Use of this methodology for currently deployed systems allows predictive determinations of activity levels and distributions for common configurations of interest. This work helps determine the quality and efficacy of certain surveys in fully characterizing an effected site following a radiological event of national interest.

Robert B. Hayes

2007-11-01T23:59:59.000Z

277

DOE-HDBK-1141-2001; Radiological Assessor Training, Student's Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Student's Guide Notes Module 4-1 I. Introduction II. Radiological Control Program A. Overall program The Radiological Control Program consists of the commitments, policies, and procedures that are administered by a site or facility to meet the EH Health and Safety Policy. The Radiation Protection Program required by 10 CFR Part 835 is an element of the overall Radiological Control Program. The Radiological Control Program should address the following: * Requirements * Responsibilities * Programs/procedures * Assessments B. Size of the program Radiological Control Programs vary in size. There are several factors that may affect the magnitude of a Radiological Control Program. The specific mission, types and quantities of

278

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

279

DOE - Office of Legacy Management -- Palmerton Ore Buying Site - PA 33  

NLE Websites -- All DOE Office Websites (Extended Search)

Palmerton Ore Buying Site - PA 33 Palmerton Ore Buying Site - PA 33 FUSRAP Considered Sites Site: PALMERTON ORE BUYING SITE (PA.33) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: New Jersey Zinc Company PA.33-1 Location: Palmerton , Pennsylvania PA.33-2 Evaluation Year: 1994 PA.33-3 Site Operations: Mid-1950s - AEC leased the New Jersey Zinc Company property and established a uranium ore stockpile on the property in the vicinity of Palmerton, PA. PA.33-4 Site Disposition: Eliminated - Potential for residual contamination and resulting exposure beyond that associated with natural background radiation considered remote PA.33-3 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium Ore PA.33-4 Radiological Survey(s): Yes PA.33-5

280

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

SciTech Connect

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

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

DOE standard: Radiological control  

SciTech Connect

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

282

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7of 9 7of 9 Radiological Control Technician Training Practical Training Phase II Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 ii Table of Contents Page Introduction.............................................................................. ......1 Development of Job Performance Measures (JPMs)............................ .....1 Conduct Job Performance Evaluation...................................................3 Qualification Area: Radiological Instrumentation.......................................5 Task 2-1.................. ..................................................................... 5 Objective.............................................................................. 5

283

NEVADA TEST SITE RADIOLOGICAL CONTROL MANUAL  

Office of Scientific and Technical Information (OSTI)

manufacturing, processing, or other equipment, such as reactor components, piping, and tanks g. The radioactive material consist solely of nuclear weapons or their components h....

284

Radiological standards and calibration laboratory capabilities  

SciTech Connect

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

285

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

SciTech Connect

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

286

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

SciTech Connect

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

287

DOE/EV-0005/10 Formerly Utilized MED/AEC Sites Remedial Action Program  

Office of Legacy Management (LM)

0 0 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Former Horizons Inc., Metal Handling Facility, Cleveland, Ohio February 1979 - Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology DOE/EV-0005/10 UC-70 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Former Horizons Inc., Metal Handling Facility, Cleveland, Ohii February 1979 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology Washington, D.C. 20545 Under Contract No. W-7405-ENG-26 By the Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 Available from: National Technical Information Service (NTIS)

288

ANL=OHS/HP=83=102 FORMERLY UTILIZED MEDIAEC SITES REMEDIAL ACTION PROGRAM  

Office of Legacy Management (LM)

' DO E/EV=0005/40 ' DO E/EV=0005/40 ANL=OHS/HP=83=102 FORMERLY UTILIZED MEDIAEC SITES REMEDIAL ACTION PROGRAM RADIOLOGICAL SURVEY OF THE ALBANY METALLURGICAL RESEARCH CENTER UNITED STATES BUREAU OF MINES ALBANY, OREGON Q\OLO G/C G- 4& G SITES REMEDIAL ACTION PROGRAM RADIOLOGICAL SURVEY OF THE ALBANY METALLURGICAL RESEARCH CENTER

289

DOEIEV-0005/20 Formerly Utilized MED/AEC Sites Remedial Action Program  

Office of Legacy Management (LM)

20 20 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Middlesex Municipal Landfill, Middlesex, New Jersey April 1980 , Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Office of Environmental Compliance and Overview Division of Environmental Control Technology DOE/EV-O005/20 UC-70 Formerly Utilized MED/AEC Sites Remedbl Action Program Radiological Survey uf the Middlesex Municipal Landfill, Middlesex, New Jersey April 1980 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Office of Environmental Compliance and Overview Division of Environmec!al Coctrol Technology Washington, D.C. 20545 by Oak Ridge National Laboratory Oak Ridge, Tennessee 37830

290

OE/EV-0005/2 Formerly Utilized MED/AEC Sites Remedial Action Program  

Office of Legacy Management (LM)

OE/EV-0005/2 OE/EV-0005/2 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Hooker Chemical Company Niagara Falls, New York January 1977 Final Report Prepared for U.S. Department of Energy Division of Environmental Control Technology Washington, D.C. 20545 DOE/EV-0005/2 UC-70 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Hooker Chemical Company Niagara Falls, New York January 1977 Final Report Prepared for U.S. Department of Energy Division of Environmental Control Technology Washing-ton, D.C. 20545 Under Contract No. W-7405-ENE-26 Oak Ridge National Laboratory Oak Ridge, Tennessee 3783C NOTICE This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United

291

DOE/EV-0005/15 Formerly Utilized MED/AEC Sites Remedial Action Program  

Office of Legacy Management (LM)

5 5 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Bayo Canyon, Los Alamos, New Mexico June 1979 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology DOE/EV-0005/15 UC-71 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Bayo Canyon, Los Alamos, New Mexico June 1979 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology Washington, D.C. 20545 by Los Alamos Scientific Laboratory Los Alamos, New Mexico 87545 Under Contract No. W-7405-ENG-36 Available from: National Technical Information Service (NTIS) U.S. Department of Commerce 5285 Port Royal Road Springfield, Virginia 22161

292

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Access Control and Work Area Setup Access Control and Work Area Setup Instructor's Guide 2.10-1 Course Title: Radiological Control Technician Module Title: Access Control and Work Area Setup Module Number: 2.10 Objectives: L 2.10.01 State the purpose of and information found on a Radiological Work Permit (RWP) including the different classifications at your site. L 2.10.02 State responsibilities in using or initiating a RWP. L 2.10.03 State the document that governs the ALARA program at your site. L 2.10.04 Describe how exposure/performance goals are established at your site. L 2.10.05 State the conditions under which a pre-job ALARA review is required at your site. L 2.10.06 State the conditions under which a post-job ALARA review is required at your site. 2.10.07 State purpose of radiological postings, signs, labels, and barricades; and

293

Radiological worker training  

SciTech Connect

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

294

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

SciTech Connect

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

295

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTRT] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

296

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTRT] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 25-Oct-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

297

Roadmap: Radiologic Imaging Sciences -Radiation Therapy (with AAS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Radiation Therapy (with AAS Radiologic Technology) ­ Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAA] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

298

Roadmap: Radiologic Imaging Sciences -Radiation Therapy (with AAS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Radiation Therapy (with AAS Radiologic Technology) ­ Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAA] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

299

Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended semester-by-semester plan of study

Sheridan, Scott

300

DOE - Office of Legacy Management -- Wayne Site - NJ 16  

Office of Legacy Management (LM)

Wayne Site - NJ 16 Wayne Site - NJ 16 FUSRAP Considered Sites Wayne, NJ Alternate Name(s): Wayne Interim Storage Site (WISS) W.R. Grace and Company W.R. Grace Site Rare Earths, Inc. Davison Chemical Division NJ.16-1 NJ.16-2 NJ.16-3 Location: 868 Black Oak Road, Wayne, New Jersey NJ.16-5 Historical Operations: Produced crude thorium hydroxide and rare earth elements from monazite sands. Site was also used for interim storage of contaminated material removed from vicinity properties under FUSRAP. NJ.16-5 Eligibility Determination: Eligible NJ.16-1 NJ.16-11 Radiological Survey(s): Assessment Surveys NJ.16-3 NJ.16-6 NJ.16-7 NJ.16-8 NJ.16-9 Site Status: USACE cleanup complete, not yet delisted from the National Priorities List. USACE Website EPA Website Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

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

DOE-HDBK-1141-2001; Radiological Assessor Training, Instructor's Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4-1 4-1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Elements of a Radiological Control Program Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify factors that influence the scope and magnitude of a Radiological Control Program at any nuclear facility. 2. Identify typical elements of a Radiological Control Program. Training Aids: Overhead Transparencies (OTs): OT 4.1 - OT 4.5 (may be supplemented or substituted with updated or site-specific information) Handouts - "List of Radiological Control Program Elements" "Elements of a Radiological Control Program" Equipment Needs: Overhead projector Screen Flip chart Markers Masking tape Student Materials: Student's Guide

302

Chinese Geological Survey | Open Energy Information  

Open Energy Info (EERE)

Geological Survey Place: China Sector: Geothermal energy Product: Chinese body which is involved in surveys of geothermal sites. References: Chinese Geological Survey1 This...

303

Radiology of thoracic diseases  

SciTech Connect

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

304

OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL  

Office of Legacy Management (LM)

2 7% 2 7% d &y / 7 ORNL/TM- 10076 OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL ~-T-m -~=- -~ w-~- -"" * ,<.~- ~w&$UREMENTs: TAKEN IN THE NIAGARA FALLS, NEW YORK, AREA (NF002) J. K. Williams B. A. Berven ~.~~;:;-~~~ ~. -,' - ~~ 7, OPERATED BY MARTIN MARIDTA ENERGY SYSTEMS, INC, FOR THE UNITED STATES DEPARTMENT OF ENERGY --... ORNL/TM-10076 HEALTH AND SAFETY RESEARCH DIVISION Nuclear and Chemical Waste Programs (Activity No. AH 10 05 00 0; ONLWCOI) RESULTS OF RADIOLOGICAL MEASUREMENTS TAKEN IN THE NIAGARA FALLS, NEW YORK, AREA (NFOO2) J. K. Williams* and B. A. Berven *Biology Division Date Published November 1986 Investigation Team B. A. Berven - RASA Program Manager W. D. Cottrell - FUSRAP Project Director W. H. Shinpaugh - Field Survey Supervisor

305

DOE - Office of Legacy Management -- Latty Avenue Site - MO 04  

NLE Websites -- All DOE Office Websites (Extended Search)

Latty Avenue Site - MO 04 Latty Avenue Site - MO 04 FUSRAP Considered Sites Latty Avenue Site, MO Alternate Name(s): Futura Coatings Futura Chemical Company Facility Hazelwood Interim Storage Site (HISS) Former Cotter Site, Latty Avenue Properties Contemporary Metals Corp. Continental Mining and Milling MO.04-1 MO.04-2 MO.04-5 MO.04-6 MO.06-8 MO.06-11 Location: 9200 Latty Avenue, Hazelwood, Missouri MO.04-1 Historical Operations: Received, stored, and processed uranium residues for the AEC. Storage and processing were licensed by the AEC and NRC and resulted in contamination of uranium and thorium. MO.04-5 MO.04-6 Eligibility Determination: Eligible MO.04-3 MO.04-4 Radiological Survey(s): Assessment Surveys MO.04-2 MO.04-7 MO.04-8 MO.04-9 MO.04-10 MO.04-11 Site Status: Cleanup in progress by U.S. Army Corps of Engineers. MO.04-12

306

Benefits of integration of radiology services across a pediatric health care system with locations in multiple states  

Science Journals Connector (OSTI)

Integration was implemented of previously independently practicing pediatric radiology services across a pediatric health care system with sites 1,000 miles apart.

Lane F. Donnelly; Debbie J. Merinbaum; Monica Epelman…

2014-11-01T23:59:59.000Z

307

Preliminary Notice of Violation, Rocky Flats Environmental Technology Site- EA-96-05  

Energy.gov (U.S. Department of Energy (DOE))

Preliminary Notice of Violation issued to Safe Sites of Colorado related to Radiological and Work Control Deficiencies associated with Two Radiological Release Events at the Rocky Flats Environmental Technology Site, (EA-96-05)

308

Radiological Assessor Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

141-2001 141-2001 April 2001 Change Notice No. 1 and Reaffirmation January 2007 DOE HANDBOOK Radiological Assessor Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Radiological Assessor Training DOE-HDBK-1141-2001 iii

309

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 ii This page intentionally left blank DOE-HDBK-1122-2009 iii Table of Contents Page Introduction................................................................................................................................1 Facility Job Performance Measures ........................................................................................2 Final Verification Signatures ....................................................................................................3 DOE-HDBK-1122-2009 iv

310

Radiological Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 ii This page intentionally left blank. DOE-HDBK-1122-2009 iii Table of Contents Page Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Purpose of Qualification Standard . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Phase I: RCT Academics Training . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . 1 Phase II: RCT Core Practical (JPMs) Training . . . . . . . . . . . . . . . . . .. . . . . . . 1

311

PRELIMINARY SURVEY OF WINCHESTER ENGINEERING AND ANALYTICAL CENTER  

Office of Legacy Management (LM)

WINCHESTER ENGINEERING AND ANALYTICAL CENTER WINCHESTER ENGINEERING AND ANALYTICAL CENTER Winchester, Massachusetts Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 . .- _ 2. / f OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPOdATIOt'i for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action PL;ogram .-__ - - .--..--_ ~. _.. -. THE FORMER WINCHESTER ENGINEERING AND ANALYTICAL CENTER Winchester, Massachusetts At the request of the Department of Energy (DOE, then ERDA), a preliminary survey was performed at the former Winchester Engineering and Analytical Center, Winchester, Massachusetts (see Fig. 1), on January 25, 1977, to assess the radiological status of this facility

312

Radiological Safety Training for Accelerator Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TS TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1108-2002 May 2002 Reaffirmation with Change Notice 2 July 2013 DOE HANDBOOK RADIOLOGICAL SAFETY TRAINING FOR ACCELERATOR FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change Notice No.2 Radiological Training for Accelerator Facilities Page/Section Change Throughout the document: Program Management Guide Instructor's Guide Student's Guide "Shall" and "Must" statements Revised to: Program Management Instructor's Material Student's Material Reworded to non-mandatory language unless associated with a requirement

313

Radiological Safety Training for Uranium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE HDBK-1113-2008 DOE HDBK-1113-2008 April 2008 DOE HANDBOOK RADIOLOGICAL SAFETY TRAINING FOR URANIUM FACILITIES U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-HDBK-1113-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-HDBK-1113-2008 iii Foreword This Handbook describes a recommended implementation process for additional training as outlined in DOE-STD-1098-99, Radiological Control (RCS). Its purpose is to assist those individuals, Department of Energy (DOE) employees, Managing and Operating (M&O) contractors, and Managing and Integrating

314

Radiological Worker Training Power Point Slides for App. A  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

30-2008 30-2008 DOE HANDBOOK Radiological Worker Training DOE-HDBK-1130-2008 Overheads December 2008 Reaffirmed 2013 OT 1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in the above documents. * Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites and facilities. OT 1.3 DOE-HDBK-1130-2008 Overhead 1.3 DOE Radiological Health and Safety Policy * Conduct oversight to ensure compliance and that appropriate radiological work

315

ORISE: REAC/TS Radiological Incident Medical Consultation  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Incident Medical Consultation Radiological Incident Medical Consultation Radiological Incident Medical Consultation The Oak Ridge Institute for Science and Education (ORISE) provides the U.S. Department of Energy (DOE) with a comprehensive capability to respond effectively to medical emergencies involving radiological or nuclear materials. Through the management of the Radiation Emergency Assistance Center/Training Site (REAC/TS), ORISE provides advice and consultation to emergency personnel responsible for the medical management of radiation accidents. REAC/TS strengthens hospital preparedness for radiation emergencies by preparing and educating first responders, medical personnel and occupational health professionals who will provide care to patients with a radiation injury or illness. REAC/TS staff provide medical advice,

316

Radiological Worker Training Power Point Slides for App. A  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

30-2008 30-2008 DOE HANDBOOK Radiological Worker Training DOE-HDBK-1130-2008 Overheads December 2008 Reaffirmed 2013 OT 1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in the above documents. * Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites and facilities. OT 1.3 DOE-HDBK-1130-2008 Overhead 1.3 DOE Radiological Health and Safety Policy * Conduct oversight to ensure compliance and that appropriate radiological work

317

DOE/EV-0005/19 Formerly Utilized MED/AEC Sites Remedial Action Program  

Office of Legacy Management (LM)

9 9 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Building Site 421, United States Watertown Arsenel, Watertown, MA February 1980 . Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology ~--.. _..-- DOE/EV-0005/19 UC-70 Formerly Utilized MED/AEC Sites Remedial Action Program Radiologidal Survey of the Building Site 421, United States Watertown Arsenel, Watertown, MA February 1980 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology Washington, D.C. 20545 by Argonne National Laboratory Argonne, Illinois 60439 Under Contract No. W-31-1 09-ENG-38 -- _.. .-___

318

DOE/EV-0005/16 Formerly Utilized MED/AEC Sites Remedial Action Program  

Office of Legacy Management (LM)

6 6 Formerly Utilized MED/AEC Sites Remedial Action Program Radic&@cal Survey of the St. Louis Airport Storage Site, St. Louis, Missouri September 1979 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology .__ -. __ ..- -- DOE/EV-0005/16 UC-70 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the St. Louis Airport Storage Site, St. Louis, Missouri September 1979 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environment Division of Environmental Control Technology Washington, D.C. 20545 by Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 Under Contract No. W-7405-ENG-26 .--__ _ .- _--- _ ~- Available from:

319

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

SciTech Connect

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

320

Nuclear & Radiological Activity Center (NRAC)  

NLE Websites -- All DOE Office Websites (Extended Search)

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

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

Panoramic Radiology: Oncologic Dentistry Considerations  

Science Journals Connector (OSTI)

Panoramic radiology can serve as an important input supporting ... they are also important (1) for planning dental treatment in preparation of the oral cavity...

2007-01-01T23:59:59.000Z

322

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

98 98 October 1998 Change Notice No. 1 June 2001 Change Notice No. 2 December 2003 Reaffirmation with Errata May 2004 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-98 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration,

323

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

SciTech Connect

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

324

Handling and Packaging a Potentially Radiologically Contaminated...  

Office of Environmental Management (EM)

Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Medical ExaminerCoroner...

325

Order Module--DOE STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL Order Module--DOE STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL "The radiological control program discussed in DOE-STD-1098-2008 goes beyond the scope of, and includes more details than, the documented radiation protection program (RPP) required by 10 CFR 835, -Occupational Radiation Protection.‖ To ensure implementation of a comprehensive and coherent radiological control program that exceeds basic requirements and provides a substantial safety margin, DOE encourages its contractors to implement the provisions of DOE-STD-1098- 2008 to the extent appropriate to facility hazards and operations, consistent with DOE's integrated safety management program. Should any conflicts arise between the site-specific radiological control manual and the documented RPP, the

326

Case Based Dental Radiology  

Science Journals Connector (OSTI)

Dental radiology is quickly becoming integral to the standard of care in veterinary dentistry. This is not only because it is critical for proper patient care, but also because client expectations have increased. Furthermore, providing dental radiographs as a routine service can create significant practice income. This article details numerous conditions that are indications for dental radiographs. As you will see, dental radiographs are often critical for proper diagnosis and treatment. These conditions should not be viewed as unusual; they are present within all of our practices. When you choose not to radiograph these teeth, you leave behind painful pathology. Utilizing the knowledge gained from dental radiographs will both improve patient care and increase acceptance of treatment recommendations. Consequently, this leads to increased numbers of dental procedures performed at your practice.

Brook A. Niemiec

2009-01-01T23:59:59.000Z

327

External dosimetry in the aftermath of a radiological terrorist event  

Science Journals Connector (OSTI)

......Similarly, site assessment and cleanup...routinely at risk from many...case of a nuclear power plant accident...radiological assessments and may be...responsible for terrorism preparedness...Monitoring and Assessment Center...after the nuclear power plant accident......

Gladys A. Klemic; Paul D. Bailey; Kevin M. Miller; Matthew A. Monetti

2006-09-01T23:59:59.000Z

328

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

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

329

Independent Oversight Follow-up Review, Idaho Site – January 2014  

Energy.gov (U.S. Department of Energy (DOE))

Follow-up Review of Activity-Level Implementation of Radiation Controls and Radiological Work Planning at the Materials and Fuels Complex of the Idaho Site

330

Inequalities in reported cancer patient experience by sociodemographic characteristic and cancer site: Evidence from respondents to the English Cancer Patient Experience Survey  

E-Print Network (OSTI)

practitioner consultations before hospital referral for cancer: findings from the 2010 National Cancer Patient Experience Survey in England. Lancet Oncol, 13, 353-65. Macmillan Cancer Support 2012-2013. Cancer Patient Experience Survey: Insight Report...

Saunders, Catherine L.; Abel, Gary A.; Lyratzopoulos, Georgios

2014-01-01T23:59:59.000Z

331

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 Radiation Survey Instrumentation 6 Radiation Survey Instrumentation Instructor's Guide 2.16-1 Course Title: Radiological Control Technician Module Title: Radiation Survey Instrumentation Module Number: 2.16 Objectives: 2.16.01 List the factors which affect an RCT's selection of a portable radiation survey instrument, and identify appropriate instruments for external radiation surveys. L 2.16.02 Identify the following features and specifications for ion chamber instruments used at your facility: a. Detector type b. Instrument operating range c. Detector shielding d. Detector window e. Types of radiation detected/measured f. Operator-adjustable controls g. Markings for detector effective center h. Specific limitations/characteristics. L 2.16.03 Identify the following features and specifications for high range

332

PRELIMINARY SURVEY O F INTERNATIONAL M INERALS AND CHEMICAL CORPORATION  

Office of Legacy Management (LM)

Pk.. = "p' Pk.. = "p' . PRELIMINARY SURVEY O F INTERNATIONAL M INERALS AND CHEMICAL CORPORATION M u lberry, F lorida I Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK.RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT O F ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program .-. _ ._-. .__._ ..-...- -. .,. _... I_-.-.- INTERNATIONAL MINERALS AND CHEMICAL CORPORATION Mulberry, Florida At the request of the Department of Energy (DOE, then ERDA), a preliminary survey was performed at the International Minerals and Chemical Corporation in Mulberry, Florida (see Fig. 1), on April 6, 1977, to assess the radiological status of the facilities utilized under

333

Radiological planning and implementation for nuclear-facility decommissioning  

SciTech Connect

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

Valentine, A.M.

1982-01-01T23:59:59.000Z

334

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

335

Radiological Emergency Response Plan (Vermont)  

Energy.gov (U.S. Department of Energy (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...

336

Radiological cleanup of Enewetak Atoll  

SciTech Connect

For 8 years, from 1972 until 1980, the United States planned and carried out the radiological cleanup, rehabilitation, and resettlement of Enewetak Atoll in the Marshall Islands. This documentary records, from the perspective of DOD, the background, decisions, actions, and results of this major national and international effort. The documentary is designed: First, to provide a historical document which records with accuracy this major event in the history of Enewetak Atoll, the Marshall Islands, the Trust Territory of the Pacific Islands, Micronesia, the Pacific Basin, and the United States. Second, to provide a definitive record of the radiological contamination of the Atoll. Third, to provide a detailed record of the radiological exposure of the cleanup forces themselves. Fourth, to provide a useful guide for subsequent radiological cleanup efforts elsewhere.

Not Available

1981-01-01T23:59:59.000Z

337

Radiological training for tritium facilities  

SciTech Connect

This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835.

NONE

1996-12-01T23:59:59.000Z

338

Radiological Protection for DOE Activities  

Directives, Delegations, and Requirements

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

339

DOE - Office of Legacy Management -- Niagara Falls Storage Site NY - NY 17  

Office of Legacy Management (LM)

Niagara Falls Storage Site NY - NY Niagara Falls Storage Site NY - NY 17 FUSRAP Considered Sites Niagara Falls Storage Site, NY Alternate Name(s): Lake Ontario Ordnance Works (LOOW) Niagara Falls Storage Site (NFSS) DOE-Niagara Falls Storage Site NY.17-1 NY.17-3 Location: Lewiston, New York NY.17-5 Historical Operations: Stored, shipped, and buried radioactive equipment and waste for MED and AEC containing uranium, radium, and thorium. Contains Interim Waste Containment Structure. NY.17-1 NY.17-2 NY.17-14 Eligibility Determination: Eligible NY.17-4 Radiological Survey(s): Assessment Surveys NY.17-3 NY.17-5 NY.17-6 NY.17-7 NY.17-8 NY.17-9 NY.17-10 NY.17-11 NY.17-12 NY.17-14 Site Status: Cleanup in progress by U.S. Army Corps of Engineers. NY.17-13 NY.17-14 NY.17-15 NY.17-16 USACE Website Long-term Care Requirements: To be determined upon completion.

340

Radiological Worker Training Power Point Slides for App. A  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1.1 1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in the above documents. * Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites and facilities. OT 1.3 DOE-HDBK-1130-2008 Overhead 1.3 DOE Radiological Health and Safety Policy * Conduct oversight to ensure compliance and that appropriate radiological work practices are implemented. * Ensure accurate and appropriately made measurements. * Incorporate measures to minimize

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

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 of 9 6 of 9 Radiological Control Technician Training Site Academic Training Study Guide Phase I Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1122-99 Radiological Control Technician Study Guide ii This page intentionally left blank. DOE-HDBK-1122-99 Radiological Control Technician Study Guide iii Course Developers William Egbert Lawrence Livermore National Laboratory Dave Lent Coleman Research Michael McNaughton Los Alamos National Laboratory Bobby Oliver Lockheed Martin Energy Systems Richard Cooke Argonne National Laboratory Brian Thomson Sandia National Laboratory Michael McGough Westinghouse Savannah River Company Brian Killand Fluor Daniel Hanford Corporation Course Reviewers Technical Standards Managers U.S. Department of Energy

342

BASF's Energy Survey Methodology  

E-Print Network (OSTI)

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.... Brainstorming activities always follow the walk-through time to capture as many findings as possible. A ranking process is then applied to extract those 20% of the ideas worth the bulk of the savings. A methodology of developing quick economics is applied...

Theising, T. R.

2005-01-01T23:59:59.000Z

343

EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0: Radiological Work and Storage Building at the Knolls 0: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York Summary 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. Public Comment Opportunities None available at this time. Documents Available for Download July 16, 2012

344

Development of radiological profiles for U.S. Department of Energy low-level mixed wastes  

SciTech Connect

Radiological profiles have been developed by Argonne National Laboratory for low-level mixed wastes (LLMWs) that are under the management of the US Department of Energy (DOE). These profiles have been used in the Office of Environmental Management Programmatic Environmental Impact Statement (EM PEIS) to support the analysis of environmental and health risks associated with the various waste management strategies. The radiological characterization of DOE LLMWs is generally inadequate and has made it difficult to develop a site- and waste-stream-dependent radiological profile for LLMWs. On the basis of the operational history of the DOE sites, a simple model was developed to generate site-dependent and waste-stream-independent radiological profiles for LLMWs. This paper briefly discusses the assumptions used in this model and the uncertainties in the results.

Wilkins, B.D.; Meshkov, N.K.; Dolak, D.A.; Wang, Y.Y.

1995-03-01T23:59:59.000Z

345

DOE-HDBK-1122-99; Radiological Control Technical Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10 Access Control and Work Area Setup 10 Access Control and Work Area Setup Study Guide 2.10-1 Course Title: Radiological Control Technician Module Title: Access Control and Work Area Setup Module Number: 2.10 Objectives: i 2.10.01 State the purpose of and information found on a Radiological Work Permit (RWP) including the different classifications at your site. i 2.10.02 State responsibilities in using or initiating a RWP. i 2.10.03 State the document that governs the ALARA program at your site. i 2.10.04 Describe how exposure/performance goals are established at your site. i 2.10.05 State the conditions under which a pre-job ALARA review is required at your site. i 2.10.06 State the conditions under which a post-job ALARA review is required at your site. 2.10.07 State purpose of radiological postings, signs, labels, and barricades; and the

346

Radiological assessment. A textbook on environmental dose analysis  

SciTech Connect

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

347

E-Print Network 3.0 - areas surveys program Sample Search Results  

NLE Websites -- All DOE Office Websites (Extended Search)

search results for: areas surveys program Page: << < 1 2 3 4 5 > >> 1 Physics Division ESH Bulletin 2007-03 Radiological Survey Requirements Summary: to be an activated ion...

348

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

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

349

PRELIMINARY SURVEY OF U.S. STEEL CORPORATION--AGRI-CHEMICAL  

Office of Legacy Management (LM)

PRELIMINARY SURVEY OF PRELIMINARY SURVEY OF U.S. STEEL CORPORATION--AGRI-CHEMICAL (former Armour Fertilizer Works) Bartow, Florida Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program ..- _ "." --~ ____- - .___ _ --.. U.S. STEEL CORPORATION--AGRI-CHEMICAL (former Armour Fertilizer Works) Bartow, Florida At the request of the Department of Energy (DOE, then ERDA), a preliminary survey was performed at the U.S. Steel Corporation--Agri- Chemical Plant near Bartow, Florida (see Fig. l), on April 4, 1977, to assess the radiological status of those facilities utilized under Atomic

350

Site Index - Hanford Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Index Site Index Calendar Hanford Blog Archive Search Site Feeds Site Index Weather What's New Site Index Email Email Page | Print Print Page |Text Increase Font Size Decrease...

351

LANL responds to radiological incident  

NLE Websites -- All DOE Office Websites (Extended Search)

LANL responds to radiological incident LANL responds to radiological incident LANL responds to radiological incident Multiple tests indicate no health risks to public or employees. August 27, 2012 Aerial view of the Los Alamos Neutron Science Center(LANSCE). Aerial view of the Los Alamos Neutron Science Center (LANSCE). The contamination poses no danger to the public. The Laboratory is investigating the inadvertent spread of Technetium 99 by employees and contractors at the Lujan Neutron Scattering Center August 27, 2012-The Laboratory is investigating the inadvertent spread of Technetium 99 by employees and contractors at the Lujan Neutron Scattering Center at the Los Alamos Neutron Science Center (LANSCE), a multidisciplinary accelerator facility used for both civilian and national security research. The Laboratory has determined that about a dozen people

352

Radiological Training for Tritium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Change Notice No. 2 Change Notice No. 2 May 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 2. Radiological Safety Training for Tritium Facilities DOE-HDBK-1105-2002 Page/Section Change Part 1, page 14 Change: U.S. Department of Energy, Radiological Control

353

Geophysical Evidence through a CSAMT Survey of the Deep Geological Structure at a Potential Radioactive Waste Site at Beishan, Gansu, China  

Science Journals Connector (OSTI)

...Foundation for funding support (no...geophysical studies at Yucca Mountain, Nevada and vicinity...radioactive waste disposal site: Geophysics...waste (HLRW) disposal site in northwestern...models underground disposal waste disposal...

Zhiguo An; Qingyun Di; Changmin Fu; Cheng Xu; Bo Cheng

354

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

SciTech Connect

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

355

Trench sampling report Salmon Site Lamar County, Mississippi  

SciTech Connect

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

356

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

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

357

An overview of dental radiology: a primer on dental radiology  

SciTech Connect

To provide medical and scientific background on certain selected technologies generally considered to be of particular significance, the National Center for Health Care Technology (NCHCT) has commissioned a series of overview papers. This is one of several projects entered into jointly by the Bureau of Radiological Health (BRH) and NCHCT relating to the use of radiation for health care. Dental radiation protection has been a long-time interest of BRH. Both past and on-going efforts to minimize population radiation exposure from electronic products have included specific action programs directed at minimizing unnecessary radiation exposure to the population from dental radiology. Current efforts in quality assurance and referral criteria are two aspects of NCHCT's own assessment of this technology which are described within the larger picture presented in this overview. The issues considered in this document go beyond the radiation exposure aspects of dental x-ray procedures. To be responsive to the informational needs of NCHCT, the assessment includes various other factors that influence the practice of dental radiology. It is hoped this analysis will serve as the basis for planning and conducting future programs to improve the practice of dental radiology.

Manny, E.F.; Carlson, K.C.; McClean, P.M.; Ra1hlin, J.A.; Segal, P.

1980-11-07T23:59:59.000Z

358

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

359

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

360

Radiological Control Programs for Special Tritium Compounds  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

84-2004 84-2004 SEPTEMBER 2004 CHANGE NOTICE NO. 1 Date June 2006 DOE HANDBOOK RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS U.S. Department of Energy AREA OCSH Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Table of Changes Page Change 67 (near bottom) In row 1, column 2 of the table titled "dosimetric properties" 6 mrem was changed to 6 x 10 -2 mrem Available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techstds/ DOE-HDBK-1184-2004 iii Foreword The Department of Energy (DOE) and its predecessor agencies have undertaken a wide variety

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361

Radiological assessment of BWR recirculatory pipe replacement  

SciTech Connect

Replacement of primary recirculating coolant pipe in BWRs is a major effort that has been carried out at a number of nuclear generating stations. This report reviews the planned or actual pipe replacement projects at six sites: Nine Mile Point-1, Monticello, Cooper, Peach Bottom-2, Vermont Yankee, and Browns Ferry-1. It covers the radiological issues of the pipe replacement, measures taken to reduce doses to ALARA, estimated and actual occupational doses, and lessons learned during the various replacements. The basis for the decisions to replace the pipes, the methods used for preparation and decontamination, the removal of old pipe, and the installation of the new pipe are briefly described. Methods for reducing occupational radiation dose during pipe repairs/replacements are recommended. 32 refs., 12 figs., 17 tabs.

Parkhurst, M.A.; Hadlock, D.E.; Harty, R.; Pappin, J.L.

1986-02-01T23:59:59.000Z

362

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

Radiological Threat Task Force Established | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

363

Operational Guidelines/Radiological Emergency Response  

Energy.gov (U.S. Department of Energy (DOE))

Operational Guidelines/Radiological Emergency Response. Provides information and resources concerning the development of Operational Guidelines as part of planning guidance for protection and recovery following Radiological Dispersal Device (RDD) and/or Improvised Nuclear Device (IND) incidents. Operational Guidelines Technical (OGT) Manual, 2009 RESRAD-RDD Complementing Software to OGT Manual EPA Protective Action Guidelines (2013), Interim Final Federal Radiological Monitoring and Assessment Center (FRMAC) Federal Radiological Preparedness Coordinating Committee (FRPCC)

364

Departmental Radiological Emergency Response Assets  

Directives, Delegations, and Requirements

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

365

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

366

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

367

Robotic Surveying  

SciTech Connect

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

368

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Instrumentation Study Guide Instrumentation Study Guide 2.16-1 Course Title: Radiological Control Technician Module Title: Radiation Survey Instrumentation Module Number: 2.16 Objectives: 2.16.01 List the factors which affect an RCT's selection of a portable radiation survey instrument, and identify appropriate instruments for external radiation surveys. i 2.16.02 Identify the following features and specifications for ion chamber instruments used at your facility: a. Detector type b. Instrument operating range c. Detector shielding d. Detector window e. Types of radiation detected/measured f. Operator-adjustable controls g. Markings for detector effective center h. Specific limitations/characteristics i 2.16.03 Identify the following features and specifications for high range instruments used at your facility:

369

Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet  

SciTech Connect

This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for each corrective action site (CAS) within CAU 168. The corrective action investigation (CAI) was conducted in accordance with the ''Corrective Action Investigation Plan for Corrective Action Unit 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada'', as developed under the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 168 is located in Areas 25 and 26 of the Nevada Test Site, Nevada and is comprised of the following 12 CASs: CAS 25-16-01, Construction Waste Pile; CAS 25-16-03, MX Construction Landfill; CAS 25-19-02, Waste Disposal Site; CAS 25-23-02, Radioactive Storage RR Cars; CAS 25-23-13, ETL - Lab Radioactive Contamination; CAS 25-23-18, Radioactive Material Storage; CAS 25-34-01, NRDS Contaminated Bunker; CAS 25-34-02, NRDS Contaminated Bunker; CAS 25-99-16, USW G3; CAS 26-08-01, Waste Dump/Burn Pit; CAS 26-17-01, Pluto Waste Holding Area; and CAS 26-19-02, Contaminated Waste Dump No.2. Analytes detected during the CAI were evaluated against preliminary action levels (PALs) to determine contaminants of concern (COCs) for CASs within CAU 168. Radiological measurements of railroad cars and test equipment were compared to unrestricted (free) release criteria. Assessment of the data generated from the CAI activities revealed the following: (1) Corrective Action Site 25-16-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (2) No COCs were identified at CAS 25-16-03. Buried construction waste is present in at least two disposal cells contained within the landfill boundaries. (3) No COCs were identified at CAS 25-19-02. (4) Radiological surveys at CAS 25-23-02 identified 13 railroad cars that exceeded the NV/YMP Radiological Control Manual limits for free release. Six railroad cars were below these limits and therefore met the free-release criteria. (5) An In-Situ Object Counting System survey taken at CAS 25-23-02 identified two railroad cars possibly containing fuel fragments; both exceeded the NV/YMP Radiological Control Manual free release criteria. (6) Corrective Action Site 25-23-18 contains total petroleum hydrocarbons-diesel-range organics, Aroclor-1260, uranium-234, uranium-235, strontium-90, and cesium-137 that exceed PALs. (7) Radiological surveys at CAS 25-34-01 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (8) Radiological surveys at CAS 25-34-02 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (9) Radiological surveys at CAS 25-23-13 identified six pieces of equipment that exceed the NV/YMP Radiological Control Manual limits for free release. (10) Corrective Action Site 25-99-16 was not investigated. A review of historical documentation and current site conditions showed that no further characterization was required to select the appropriate corrective action. (11) Corrective Action Site 26-08-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (12) Corrective Action Site 26-17-01 contains total petroleum hydrocarbons-diesel-range organics and Aroclor-1260 exceeding the PALs. (13) Radiological surveys at CAS 26-19-02 identified metallic debris that exceeded the NV/YMP Radiological Control Manual limits for free release. Concentrations of radiological or chemical constituents in soil did not exceed PALs.

Wickline, Alfred

2006-12-01T23:59:59.000Z

370

Nuclear / Radiological Advisory Team | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

/ Radiological Advisory Team | National Nuclear Security / Radiological Advisory Team | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear / Radiological Advisory Team Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Operations > Nuclear / Radiological Advisory Team Nuclear / Radiological Advisory Team

371

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Act-Funded Study Assesses Contamination at Former Test Act-Funded Study Assesses Contamination at Former Test Site in California Recovery Act-Funded Study Assesses Contamination at Former Test Site in California 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 land for gamma radiation. Under an interagency agreement with DOE, the Environmental Protection Agency (EPA) is conducting the study at Santa Susana Field Laboratory (SSFL) Area IV and the Northern Undeveloped Land. Recovery Act-Funded Study Assesses Contamination at Former Test Site in California More Documents & Publications EA-1345: Final Environmental Assessment EIS-0402: Notice of Intent to Prepare an Environmental Impact Statement

372

DOEIEV-0005/37 ANL=OHS/HP-83406 FORMERLY UTILIZED MEDIAEC SITES  

Office of Legacy Management (LM)

//, .<.' //, .<.' I ' 1 TL\ t+, -- DOEIEV-0005/37 ANL=OHS/HP-83406 FORMERLY UTILIZED MEDIAEC SITES REMEDIAL ACTION PROGRAM RADIOLOGICAL SURVEY OF THE FORMER WATERTOWN ARSENAL PROPERTY SITE 34 AND SITE 41 WATERTOWN, MASSACHUSETTS o\o\-0 G /Q e-+ a+ -? q+ mii ' ( . % QL G+ OCCUPATIONAL HEALTH AND SAFETY INViSiON Health Physics Section ARGONNE NATIONAL LABORATORY, ARGONNE, ILLINOIS Operated by THE UNIVERSITY O F CHICAGO for the U. S. DEPARTMENT O F ENERGY under Contract W=314 09.Eng-38 Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States government, and operated by The University of Chicago under the provisions of a contract with the Department of Energy. r----- DISCLAIMER I This report was prepared as an account of work sponsored by an

373

Radiological Training for Accelerator Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8-2002 8-2002 May 2002 Change Notice No 1. with Reaffirmation January 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR ACCELERATOR FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 1. Radiological Safety Training for Accelerator Facilities

374

Radiological Training for Tritium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE HANDBOOK DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 1. Radiological Safety Training for Tritium Facilities DOE-HDBK-1105-2002 Page/Section Change Cover sheets parts 1, 2, 3, and 4 Change: Office of Environment, Safety & Health

375

Radiological Control Training for Supervisors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3-2001 3-2001 August 2001 Change Notice No 1. with Reaffirmation January 2007 DOE HANDBOOK Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Radiological Control Training for Supervisors

376

Annual Site Environmental Reports (ASER)  

Energy.gov (U.S. Department of Energy (DOE))

Annual Site Environmental Reports (ASERs) are required by DOE O 231.1B. The ASERs provide important information needed by site managers and DOE Headquarters to assess field environmental program performance, site-wide environmental monitoring and surveillance effectiveness, and confirm compliance with environmental standards and requirements. They are also the means by which DOE sites demonstrate compliance with the radiological protection requirements of DOE O 458.1. In addition, ASERs are an important means of conveying DOE's environmental protection performance to stakeholders and members of the public living near DOE sites.

377

PRELIMINARY SURVEY OF SYLVANIA-CORNING NUCLEAR CORPORATION METALLURGICAL LABORATORY  

Office of Legacy Management (LM)

SYLVANIA-CORNING NUCLEAR CORPORATION SYLVANIA-CORNING NUCLEAR CORPORATION METALLURGICAL LABORATORY BAYSIDE, NEW YORK Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program SYLVANIA-CORNING NUCLEAR CORPORATION METALLURGICAL LABORATORY BAYSIDE, NEW YORK At the request of the Department of Energy (DOE), a preliminary survey was performed at the former Sylvania-Corning Nuclear Corporation in Bayside, New York (see Fig. l), on November 29, 1977, to assess the radiological status of those facilities uti 7 Commission (AEC) contract during the 1950s. _ _ ._. __

378

PRELIMINARY SURVEY OF BETHLEHEM STEEL LACKAWANNA, NEW YORK  

Office of Legacy Management (LM)

BETHLEHEM STEEL BETHLEHEM STEEL LACKAWANNA, NEW YORK Work oerformed bi the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program BETHLEHEM STEEL LACKAWANNA, NEW YORK At the request of the Department of Energy (DOE, then ERDA), a preliminary survey was performed at the Bethlehem Steel Corporation's plant in Lackawanna, New York (see Fig. l), on August 26, 1976, to assess the radiological status of those facilities utilized under Atomic Energy Commission (AEC) contract during the period 1949 through 1951. Anthony LaMastra of Bethlehem Steel, who was in charge of radiation

379

PRELIMINARY SURVEY OF W. R. GRACE COMPANY Ridgewood, Florida  

Office of Legacy Management (LM)

W. R. GRACE COMPANY W. R. GRACE COMPANY Ridgewood, Florida Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program W. R. GRACE COMPANY Ridgewood, Florida At the request of the Department of Energy (DOE, then ERDA), a preliminary survey was performed at the W. R. Grace and Company, Agricultural Chemicals Division plant in Ridgewood, Florida, on April 6, 1977, to assess the radiological status of those facilities utilized under an Atomic Energy Commission (AEC) raw materials contract during the period 7954 through 1955. Gene Terry, General Manager,

380

PRELIMINARY SURVEY OF BRIDGEPORT BRASS COMPANY SEYMOUR, CONNECTICUT  

Office of Legacy Management (LM)

BRIDGEPORT BRASS COMPANY BRIDGEPORT BRASS COMPANY SEYMOUR, CONNECTICUT Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program BRIDGEPORT BRASS COMPANY SEYMOUR, CONNECTICUT At the request of the Department of Energy (then ERDA), a preliminary survey was performed at the Bridgeport Brass Company in Seymour, Connecticut (Fig. 1) on January 26, 1977, to assess the radiological status of those facilities used under Atomic Energy Commission (AEC) contract during the period 1962 through 1964. Mr. Edwin F. Rich, Plant Engineer, provided information about the project and identified those

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

PRELIMINARY SURVEY OF WESTINGHOUSE ELECTRIC CORPORATION EAST PITTSBURGH, PENNSYLVANIA  

Office of Legacy Management (LM)

WESTINGHOUSE ELECTRIC CORPORATION WESTINGHOUSE ELECTRIC CORPORATION EAST PITTSBURGH, PENNSYLVANIA Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program WESTINGHOUSE ELECTRIC CORPORATION EAST PITTSBURGH, PENNSYLVANIA At the request of the Department of Energy (DOE, then ERDA), a preliminary survey was performed at the Westinghouse Electric Corporation's East Pittsburgh Plant in East Pittsburgh, Pennsylvania (see Fig. l), on October 22, 1976, to assess the radiological status of those facilities utilized under AEC/MED contract during an early phase of the Manhattan

382

Understanding Mechanisms of Radiological Contamination  

SciTech Connect

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

383

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

384

PRELIMINARY SURVEY OF AL-TECH SPECIALTY STEEL CORPORATION WATERVLIET, NEW YORK  

Office of Legacy Management (LM)

. . PRELIMINARY SURVEY OF AL-TECH SPECIALTY STEEL CORPORATION WATERVLIET, NEW YORK Work performed by the Health and Safety Research Division 3ak Ridge Natior!+l Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by lJNIuN CARBIDE CORPORATIOi; for the DEPARTMEI?T OF EI4ERGY as part of the Formerly Utilized Sites-- Remedial Action Program --, . -. I .__ . . __ .*l-..l- __. ..-_.-- - - _- - .-- AL-TECH SPECIALTY STEEL CORPORATION WATERVLIET, NEW YORK At the request of the' Department of Energy (DOE, then ERDA), a preliminary survey was performed at the Al-Tech Specialty Steel Corporation plant in Watervliet, New York (see Fig. 1), on August 19, 1976, to assess the radiological status of those facilities utilized in Atomic

385

RADIOLOGICAL EVALUATION OF DECONTAMINATION DEBRIS LOCATED AT THE  

Office of Legacy Management (LM)

h h ' . * ' 1. MI). q-8 RADIOLOGICAL EVALUATION OF DECONTAMINATION DEBRIS LOCATED AT THE FUTURA CHEMICAL COMPANY FACILITY 9200 LATTY AVENUE HAZELWOOD, MISSOURI L.W. Cole J.D. Berger W.O. Helton B.M. Putnam T.J. Sowell C.F. Weaver R.D. Condra September 9, 1981 Work performed by Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 Under Interagency Agreement DOE No. 40-770-80 NRC Fin. No. A-9093-0 Between the U.S. Nuclear Regulatory Commission and the Department of Energy I_--___- ". TABLE OF CONTENTS Page List of Figures. . . . . . . . . . . . . . . . . . . . . . ii List of Tables . . . . . . . . . . . . . . . . . . . . . . iii Introduction . . . . . . . . . . . . . . . . . . . . . . . 1.

386

Hanford radiological protection support services annual report for 1988  

SciTech Connect

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

387

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

SciTech Connect

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

388

UC-70A Formerly Utilized Sites Remedial Action Program (FUSRAP)  

Office of Legacy Management (LM)

F. a% F. a% .~~~~~~":~,~~~~,~. .-+smiii"-l ," ^.-. _ _I ,a ,' ~, *p2 - QRkl~ oR,o~ DOE/OR/20722- 29 UC-70A Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-ACO5-81OR20722 CI c F c F F c CI c c F P RADIOLOGICAL SURVEY OF THE ALBANY RESEARCH CENTER Albany, O regon Bechtel National, inc. Advanced Technology Division L- ..^___ ~. _ .._.. -.~~_-- ._ ._.. .._ .^.". January 1985 Technical information Center Office of Scientific and Technical Information U.S. Department of Energy LEGAL NOTICE This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Department of Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied,

389

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

390

OFF-SITE RADIOLOGICAL SAFETY PROGRAM FOR PROJECT RULISON FLARING...  

Office of Legacy Management (LM)

6. 7. . REFERENCES NVO-61. Projeot,RuRinon PohZ-ShoX Plum and EvaLeuatian. U. S . Atomic Energy Comnission, Nevada Operations O f f i c e , Las Vegas , Nevada, pp. v , 2-5,...

391

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

392

NV/YMP radiological control manual, Revision 2  

SciTech Connect

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

393

Title Preactivity Survey Report for Five Tonopah Test Range Explosive...  

National Nuclear Security Administration (NNSA)

Preactivity Survey Report for Five Tonopah Test Range Explosive Ordnance Disposal Sites Pre-activity survey report to clear areas to be cleaned up. No sensitive species were...

394

Radiological Assistance Program | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

Assistance Program | National Nuclear Security Administration Assistance Program | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Radiological Assistance Program Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > First Responders > Radiological Assistance Program Radiological Assistance Program RAP Logo NNSA's Radiological Assistance Program (RAP) is the nation's

395

TEPP Training - Modular Emergency Response Radiological Transportation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Waste Management » Packaging and Transportation » Services » Waste Management » Packaging and Transportation » Transportation Emergency Preparedness Program » TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) Once the jurisdiction has completed an evaluation of their plans and procedures, they will need to address any gaps in training. To assist, TEPP has developed the Modular Emergency Response Radiological Transportation Training (MERRTT) program. MERRTT provides fundamental knowledge for responding to transportation incidents involving radiological material and builds on training in existing hazardous materials curricula. MERRTT satisfies the training requirements outlined in the Waste Isolation Pilot

396

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...

397

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...

398

Radiological Safety Training for Accelerator Facilities  

Office of Environmental Management (EM)

HANDBOOK RADIOLOGICAL SAFETY TRAINING FOR ACCELERATOR FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public...

399

Radiological Assistance Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Assistance Program | National Nuclear Security Administration Assistance Program | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Radiological Assistance Program Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > First Responders > Radiological Assistance Program Radiological Assistance Program RAP Logo NNSA's Radiological Assistance Program (RAP) is the nation's

400

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Instructor's Guide Instructor's Guide 2.12-1 Course Title: Radiological Control Technician Module Title: Shipment/Receipt of Radioactive Material Module Number: 2.12 Objectives: 2.12.01 List the applicable agencies which have regulations that govern the transport of radioactive material. 2.12.02 Define terms used in DOT regulations. 2.12.03 Describe methods that may be used to determine the radionuclide contents of a package. 2.12.04 Describe the necessary radiation and contamination surveys to be performed on packages and state the applicable limits. 2.12.05 Describe the necessary radiation and contamination surveys to be performed on exclusive use vehicles and state the applicable limits. 2.12.06 Identify the proper placement of placards on a transport vehicle. L 2.12.07 Identify inspection criteria that should be checked prior to releasing a

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

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Study Guide Study Guide 2.12-1 Course Title: Radiological Control Technician Module Title: Shipment/Receipt of Radioactive Material Module Number: 2.12 Objectives: 2.12.01 List the applicable agencies which have regulations that govern the transport of radioactive material. 2.12.02 Define terms used in DOT regulations. 2.12.03 Describe methods that may be used to determine the radionuclide contents of a package. 2.12.04 Describe the necessary radiation and contamination surveys to be performed on packages and state the applicable limits. 2.12.05 Describe the necessary radiation and contamination surveys to be performed on exclusive use vehicles and state the applicable limits. 2.12.06 Identify the proper placement of placards on a transport vehicle. i 2.12.07 Identify inspection criteria that should be checked prior to releasing a

402

"What's New with Independent Verification at Department of Energy Sites"  

Energy.gov (U.S. Department of Energy (DOE))

"What's New with Independent Verification at Department of Energy Sites" Sarah Roberts*, Oak Ridge Associated Universities ; Edward Regnier, U.S. Department of Energy; Tim Vitkus, Oak Ridge Associated Universities; Alexander Williams, U.S. Department of Energy Abstract: Recent rulemaking by the U.S. Department of Energy (DOE) has formalized the requirements for independent verification (IV) of both real and personal property at DOE and National Nuclear Security Administration (NNSA) sites. DOE Order 458.1, Radiation Protection of the Public and the Environment, provides a more detailed framework for radiological clearance and IV than its predecessor DOE Order 5400.5, and emphasizes application of the “graded approach” for property clearance. The Order also incorporates recommendations for property release methodologies including the well-known Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) and the more recently issued guidance document for the release of materials and equipment (the Multi-Agency Radiation Survey and Assessments of Materials and Equipment Manual or MARSAME). The new Order has resulted in many discussions related to the application of requirements at both the headquarters and field site levels. This is not completely unexpected given that one of the major objectives of the document, to allow for a graded approach, allows for flexibility in application. There are trends in lessons learned that should be considered when evaluating the applicability of IV requirements in the Order. Some of those lessons learned include the reduction of overall project risk by early engagement of IV personnel (prior to commencement of the final status surveys), consideration of verification requirements prior to backfilling excavated (remediated) areas, and interpretation of the gray area for what constitutes a “graded approach”.

403

Roadmap: Radiologic Imaging Sciences Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) - Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-MRHA] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended

Sheridan, Scott

404

Roadmap: Radiologic Imaging Sciences Diagnostic Medical Sonography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Diagnostic Medical Sonography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAS] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 11-Apr-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

405

Roadmap: Radiologic Imaging Sciences -Magnetic Resonance Imaging (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Magnetic Resonance Imaging (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-MRRT] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

406

Roadmap: Radiologic Imaging Sciences Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) - Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-MRHA] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 11-Apr-12/LNHD This roadmap is a recommended

Sheridan, Scott

407

Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May 13/LNHD This roadmap is a recommended semester

Sheridan, Scott

408

Roadmap: Radiologic Imaging Sciences -Magnetic Resonance Imaging (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Magnetic Resonance Imaging (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-MRRT] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

409

Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 11-Apr-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

410

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with certification and ATS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTHA] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

411

Roadmap: Radiologic Imaging Sciences-Diagnostic Medical Sonography (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences- Diagnostic Medical Sonography (with certification and ATS Radiologic Technology) Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-HATS] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-13/LNHD This roadmap is a recommended

Sheridan, Scott

412

Roadmap: Radiologic Imaging Sciences Diagnostic Medical Sonography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Diagnostic Medical Sonography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAS] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-2013/LNHD This roadmap is a recommended

Sheridan, Scott

413

Roadmap: Radiologic Imaging Sciences Radiation Therapy (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Radiation Therapy ­ (with certification and ATS Radiologic Technology) - Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-RTHB] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

414

Roadmap: Radiologic Imaging Sciences-Diagnostic Medical Sonography (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences- Diagnostic Medical Sonography (with certification and ATS Radiologic Technology) Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-HATS] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended

Sheridan, Scott

415

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with certification and ATS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTHA] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 25-Oct-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

416

Microsoft PowerPoint - DOE presentation RL Site_DOE-RL.pptx ...  

NLE Websites -- All DOE Office Websites (Extended Search)

Richland Operations Office Site Report Survey Purpose * DOE tasked EurekaFacts to conduct a Hanford site-wide (federal and contractor) employee survey * Purpose - evaluate current...

417

Hanford Site Regional Population - 2010 Census  

SciTech Connect

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

418

Savannah River Site - Reports  

NLE Websites -- All DOE Office Websites (Extended Search)

Reports Reports Savannah River Site Review Reports 2013 Independent Oversight Review of the Savannah River Field Office Tritium Facilities Radiological Controls Activity-Level Implementation, November 2013 Independent Oversight Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development, August 2013 Independent Oversight Review of the Employee Concerns Program at the Savannah River Operations Office, July 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project, January 2013 Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design, January 2013 Activity Reports 2013 Savannah River Site Waste Solidification Building Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design, May 2013

419

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

420

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.

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

Federal Radiological Monitoring and Assessment Center  

Directives, Delegations, and Requirements

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

422

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

423

Memorandum, Reporting of Radiological Sealed Sources Transactions  

Energy.gov (U.S. Department of Energy (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.

424

Independent Activity Report, Pantex Site Office - May 2011 |...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Administration Pantex Site Office Quality Assurance Survey of the contractor's weapon quality program. The purpose of the survey was to examine how Babcock and Wilcox...

425

Benchmarking survey for recycling.  

SciTech Connect

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

426

DOE/EV-0005/30 LA-8890-ENV UC-70 Formerly Utilized MED/AEC Sites  

Office of Legacy Management (LM)

0 0 LA-8890-ENV UC-70 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Site of a Former Radioactive Liquid Waste Treatment Plant (TA-45) and the Effluent Receiving Areas of Acid, Pueblo, and Los Alamos Canyons, Los Alamos, New Mexico May 1981 Final Report Prepared for U.S. Department of Energy Assistant Secretary for Environmental Protection, Safety, and Emergency Preparedness Environmental and Safety Engineering Division Washington, DC 20545 Los Alamos National Laboratory Los Alamos, New Mexico 87545 PREFACE This series of reports results from a program initiated in 1974 by the Atomic Energy Commission (AEC) for determination of the condition of sites formerly utilized by the Manhattan Engineer District (MED) and the AEC for work involving the handling of radioactive materials. Since the early

427

DOEIEV-0005138 AN L-OHS/H P-83-d 08 FORMERLY UTILIZED MEDIAEC SITES  

Office of Legacy Management (LM)

jv@p&5 />:A * 2 jv@p&5 />:A * 2 DOEIEV-0005138 AN L-OHS/H P-83-d 08 FORMERLY UTILIZED MEDIAEC SITES REMEDIAL ACTION PROGRAM RADIOLOGICAL SURVEY OF THE FORMER WATERTOWN ARSENAL PROPERTY GSA SITE WATERTOWN, MASSACHUSETTS OCCUPATIONAL HEALTH AND SAFETY DIVISION Health Physics Section ARGONNE NATIONAL LABORATORY, ARGONNE, ILLlNOlS Operated by THE UNIVERSITY OF CHICAGO for the U. S. DEPARTMENT OF ENERGY under Contract W-31.109-Eng-38 Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is ovvned by the United States government, and operated by The University of Chicago under the provisions of a contract with the Department of Energy. l------ D1SCLA1MER $-------I This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United

428

Hanford radiological protection support services annual report for 1990  

SciTech Connect

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

429

Hanford Radiological Protection Support Services annual report for 1993  

SciTech Connect

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

430

Hanford Radiological Protection Support Services annual report for 1992  

SciTech Connect

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

431

Hanford radiological protection support services annual report for 1997  

SciTech Connect

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

432

Hanford radiological protection support services. Annual report for 1995  

SciTech Connect

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

433

Hanford radiological protection support services annual report for 1996  

SciTech Connect

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

434

Hanford radiological protection support services annual report for 1994  

SciTech Connect

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

435

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

436

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...

437

Model Recovery Procedure for Response to a Radiological Transportation...  

Office of Environmental Management (EM)

Recovery Procedure for Response to a Radiological Transportation Incident Model Recovery Procedure for Response to a Radiological Transportation Incident This Transportation...

438

Model Annex for Preparedness and Response to Radiological Transportati...  

Office of Environmental Management (EM)

Annex for Preparedness and Response to Radiological Transportation Incidents Model Annex for Preparedness and Response to Radiological Transportation Incidents This part should...

439

LHSC MAC Award Recipients 2012 Department of Diagnostic Radiology Victoria Hospital  

E-Print Network (OSTI)

LHSC MAC Award Recipients 2012 Department of Diagnostic Radiology Victoria Hospital Department of Medical Imaging Please join me in congratulating the Angio Interventionalists at Victoria Hospital: Drs peers Dr. Peter Blake, Chair/Chief Nephrology; and Dr. Guy De Rose, Site Chief Surgery Victoria Hospital

Lennard, William N.

440

Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites  

Energy.gov (U.S. Department of Energy (DOE))

This document summarizes radiological conditions at sites remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP) and transferred to the U.S. Department of Energy (DOE) for...

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.


441

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

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

442

Attributes and practices of oral and maxillofacial radiology departments in US and Canadian dental schools  

Science Journals Connector (OSTI)

Abstract Objective: To assess the actual state of oral and maxillofacial radiology departments in US and Canadian dental schools against the ideal characteristics defined by the American Academy of Oral and Maxillofacial Radiology (AAOMR) 1997 position paper. Study Design: Cross-sectional survey of all 65 US and Canadian dental schools. Results: Sixty-four surveys were returned (98%). At most schools, oral and maxillofacial radiology (OMR) was an identifiable division of a department, established policies, and had operational authority for radiographic practices in the primary radiology clinic. The majority of full-time faculty (72%) had formal training in OMR; the majority of part-time faculty (86%) did not. Full-time faculty spent approximately 60% of their time teaching, with the remainder of their time divided among research and scholarship, faculty practice, and service. Routine x-ray equipment was universally available; advanced imaging technologies were not. OMR faculty involvement in the interpretation of radiographs varied across diseases and conditions. Most published scholarship (85%+) was produced by full-time faculty. Average output was 1 paper per person per year, but a relatively small cadre of OMR faculty generated most papers. Conclusions: In some attributes, the status of OMR closely approximated the ideal characteristics established in the AAOMR report. Among the remaining attributes, bridging the difference between the actual and the ideal will be the challenge for the next 5 years. (Oral Surg Oral Med Oral Pathol Oral Radiol Endod 2001;91:101-8)

Mel L. Kantor; Dona Schneider; M.Kevin O Carroll

2001-01-01T23:59:59.000Z

443

Radiological Triage | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Triage | National Nuclear Security Administration Triage | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Radiological Triage Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Render Safe > Radiological Triage Radiological Triage Triage Logo NNSA's Triage is a non-deployable, secure, on-line capability

444

Corrective Action Investigation Plan for Corrective Action Unit 487: Thunderwell Site, Tonopah Test Range, Nevada (Rev. No.: 0, January 2001)  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's (DOE/NV's) approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 487, Thunderwell Site, Tonopah Test Range (TTR), Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 487 consists of a single Corrective Action Site (CAS), RG 26-001-RGRV, Thunderwell Site. The site is located in the northwest portion of the TTR, Nevada, approximately five miles northwest of the Area 3 Control Point and closest to the Cactus Flats broad basin. Historically, Sandia National Laboratories in New Mexico used CAU 487 in the early to mid-1960s for a series of high explosive tests detonated at the bottom of large cylindrical steel tubes. Historical photographs indicate that debris from these tests and subsequent operations may have been scattered and buried throughout the site. A March 2000 walk-over survey and a July 2000 geophysical survey indicated evidence of buried and surface debris in dirt mounds and areas throughout the site; however, a radiological drive-over survey also performed in July 2000 indicated that no radiological hazards were identified at this site. Based on site history, the scope of this plan is to resolve the problem statement identified during the Data Quality Objectives process that detonation activities at this CAU site may have resulted in the release of contaminants of concern into the surface/subsurface soil including total volatile and total semivolatile organic compounds, total Resource Conservation and Recovery Act metals, radionuclides, total petroleum hydrocarbons, and high explosives. Therefore, the scope of corrective action field investigation will involve excavation, drilling, and extensive soil sampling and analysis activities to determine the extent (if any) of both the lateral and vertical contamination and whether or not any such contamination extends beyond the historical boundaries of the site. The results of this field investigation will support a defensible evaluation of CAAs in the subsequent corrective action decision document.

DOE/NV

2001-01-02T23:59:59.000Z

445

Health and Productivity Questionnaire (HPQ) Survey Report  

Energy.gov (U.S. Department of Energy (DOE))

The report is an analysis of a study/survey conducted at several DOE sites to better understand the relationship between health and productivity management. Final Report - 2012

446

Nevada Test Site Environmental Report 2005  

SciTech Connect

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

447

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

448

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} a