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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  

Science Conference Proceedings (OSTI)

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

An aerial radiological survey of the Central Savannah River Site, Aiken, South Carolina  

Science Conference Proceedings (OSTI)

An aerial radiological survey was conducted over a 194-square- kilometer (75-square-mile) area encompassing the central portion of the Savannah River Site (SRS). The survey was flown during February 10--27, 1987. These radiological measurements were used as baseline data for the central area and for determining the extent of man-made radionuclide distribution. Previous SRS surveys included small portions of the area; the 1987 survey was covered during the site- wide survey conducted in 1979. Man-made radionuclides (including cobalt-60, cesium-137, protactinium-234m, and elevated levels of uranium-238 progeny) that were detected during the survey were typical of those produced by the reactor operations and material processing activities being conducted in the area. The natural terrestrial radiation levels were consistent with those measured during prior surveys of other SRS areas. 1 refs., 4 figs.

Feimster, E.L.

1991-09-01T23:59:59.000Z

5

Nevada Test Site Area 25. Radiological survey and cleanup project, 1974-1983. Final report  

SciTech Connect

This report describes radiological survey, decontamination and decommissioning of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The cleanup was part of the Surplus Facilities Management Program funded by the Department of Energy's Richland Operations Office. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for alpha and beta plus gamma radiation contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 12 figures.

McKnight, R.K.; Rosenberry, C.E.; Orcutt, J.A.

1984-01-01T23:59:59.000Z

6

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

7

An aerial radiological survey of the southwest drainage basin area of the Savannah River Site  

SciTech Connect

An aerial radiological survey was conducted over a 106-square-mile area of the Savannah River Site (SRS), formerly the Savannah River Plant. The survey was conducted from August 24 through September 8, 1988, to collect baseline radiological data over the area. Both natural and man-made gamma emitting radionuclides were detected in the area. The detected man-made sources were confined to creeks, branches, and SRS facilities in the surveyed area and were a result of SRS operations. Naturally-occurring radiation levels were consistent with those levels detected in adjacent areas during previous surveys. The annual dose levels were within the range of levels found throughout the United States.

Feimster, E.L.

1994-04-01T23:59:59.000Z

8

AERIAL RADIOLOGICAL SURVEYS  

SciTech Connect

Measuring terrestrial gamma radiation from airborne platforms has proved to be a useful method for characterizing radiation levels over large areas. Over 300 aerial radiological surveys have been carried out over the past 25 years including U.S. Department of Energy (DOE) sites, commercial nuclear power plants, Formerly Utilized Sites Remedial Action Program/Uranium Mine Tailing Remedial Action Program (FUSRAP/UMTRAP) sites, nuclear weapons test sites, contaminated industrial areas, and nuclear accident sites. This paper describes the aerial measurement technology currently in use by the Remote Sensing Laboratory (RSL) for routine environmental surveys and emergency response activities. Equipment, data-collection and -analysis methods, and examples of survey results are described.

Proctor, A.E.

1997-06-09T23:59:59.000Z

9

An Aerial Radiological Survey of Selected Areas of Area 18 - Nevada Test Site  

Science Conference Proceedings (OSTI)

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 Area 18 of the Nevada Test Site (NTS) for the purpose of mapping man-made radiation deposited as a result of the Johnnie Boy and Little Feller I tests. The survey area centered over the Johnnie Boy ground zero but also included the ground zero and deposition area of the Little Feller I test, approximately 7,000 feet (2133 meters) southeast of the Johnnie Boy site. The survey was conducted in one flight. The completed survey covered a total of 4.0 square miles. The flight lines (with the turns) over the surveyed areas are presented in Figure 1. One 2.5-hour-long flight was performed at an altitude of 100 ft above ground level (AGL) with 200 foot flight-line spacing. A test-line flight was conducted near the Desert Rock Airstrip to ensure quality control of the data. The test line is not shown in Figure 1. However, Figure 1 does include the flight lines for a ''perimeter'' flight. The path traced by the helicopter flying over distinct roads within the survey area can be used to overlay the survey data on a base map or image. The flight survey lines were flown in an east-west orientation perpendicular to the deposition patterns for both sites. This technique provides better spatial resolution when contouring 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 every second over the course of the survey and were geo-referenced using a differential Global Positioning System. 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 identify specific radioactive isotopes. Based on the results of the RSL NTS 1994 surveys, this area was chosen for a resurvey to improve the spatial resolution of the reported depositions for the Johnnie Boy and Little Feller I events. In addition, the survey was expected to confirm the absence of detectable concentrations of Americium-241 (Am-241) at the Johnnie Boy site and attempt to confirm the presence of Uranium-235 (U-235).

Craig Lyons

2009-07-31T23:59:59.000Z

10

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

11

Radiological survey of the inactive uranium-mill tailings at the Spook site, Converse County, Wyoming  

SciTech Connect

Results of a radiological survey performed at the Spook site in Converse County, Wyoming, in June 1976, are presented. The mill at this site was located a short distance from the open-pit mine where the ore was obtained and where part of the tailings was dumped into the mine. Several piles of overburden or low-grade ore in the vicinity were included in the measurements of above-ground gamma exposure rate. The average exposure rate over these piles varied from 14 ..mu..R/hr, the average background exposure rate for the area, to 140 ..mu..R/hr. The average exposure rate for the tailings and former mill area was 220 ..mu..R/hr. Movement of tailings particles down dry washes was evident. The calculated concentration of /sup 226/Ra in ten holes as a function of depth is presented graphically.

Haywood, F.F.; Christian, D.J.; Chou, K.D.; Ellis, B.S.; Lorenzo, D.; Shinpaugh, W.H.

1980-05-01T23:59:59.000Z

12

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

Science Conference Proceedings (OSTI)

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

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

1994-10-01T23:59:59.000Z

13

An aerial radiological survey of the Durango, Colorado uranium mill tailings site and surrounding area  

SciTech Connect

An aerial radiological survey of Durango, Colorado, including the inactive uranium mill tailings piles located southwest of the town, was conducted during August 25--29, 1980, for the Department of Energy's Environmental and Safety Engineering Division. Areas of radiation exposure rates higher than the local background, which was about 15 microrentgens per hour ({mu}R/h), were observed directly over and to the south of the mill tailings piles, over a cemetery, and at two spots near the fairgrounds. The rapidly changing radiation exposure rates at the boundaries of the piles preclude accurate extrapolation of aerial radiological data to ground level exposure rates in their immediate vicinity. Estimated radiation exposure rates close to the piles, however, approached 30 times background, or about 450 {mu}R/h. Radiation exposure rates in a long area extending south from the tailings piles were about 25 {mu}R/h.

Hilton, L.K.

1981-06-01T23:59:59.000Z

14

An aerial radiological survey of the Durango, Colorado uranium mill tailings site and surrounding area. Date of survey: August 1980  

Science Conference Proceedings (OSTI)

An aerial radiological survey of Durango, Colorado, including the inactive uranium mill tailings piles located southwest of the town, was conducted during August 25--29, 1980, for the Department of Energy`s Environmental and Safety Engineering Division. Areas of radiation exposure rates higher than the local background, which was about 15 microrentgens per hour ({mu}R/h), were observed directly over and to the south of the mill tailings piles, over a cemetery, and at two spots near the fairgrounds. The rapidly changing radiation exposure rates at the boundaries of the piles preclude accurate extrapolation of aerial radiological data to ground level exposure rates in their immediate vicinity. Estimated radiation exposure rates close to the piles, however, approached 30 times background, or about 450 {mu}R/h. Radiation exposure rates in a long area extending south from the tailings piles were about 25 {mu}R/h.

Hilton, L.K.

1981-06-01T23:59:59.000Z

15

Radiological surveys of properties contaminated by residual radioactive materials from uranium processing sites  

Science Conference Proceedings (OSTI)

This report examines methods for determining the extent and nature of contamination on properties contaminated by residual radioactive materials from uranium processing sites. Methods are also examined for verifying the success of remedial actions in removing the residual radioactive materials. Using literature review and practical experiences from the Edgemont, South Dakota survey program a critical review is made of sampling programs, instrumentation, analytical procedures, data reporting format, and statistical analyses of data. Protocols are recommended for measuring indoor and outdoor gamma-ray exposure rates, surface and subsurface Radium-226 concentrations in soil, and radon daughter concentrations.

Young, J.A.; Jackson, P.O.; Thomas, V.W.

1983-06-01T23:59:59.000Z

16

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

Science Conference Proceedings (OSTI)

The former Associate Aircraft Tool and Manufacturing Company site is located at 3550 Dixie Highway, Fairfield, Ohio. Associate Aircraft Tool and Manufacturing Company produced hollow uranium slugs in a machine shop at the site in 1956. The work was performed for National Lead of Ohio in a contract with the Atomic Energy Commission to augment the capacity of the Feed Materials Production Center at Fernald in the development of nuclear energy for defense-related projects. The current occupant of the building, Force Control, operates a multipurpose machine shop. At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at the former Associate Aircraft Tool and Manufacturing Company Site, Fairfield, Ohio. The survey was performed from February to May of 1995. The purpose of the survey was to verify that radioactivity from residues of {sup 238}U was remediated to a level below acceptable DOE guidelines levels.

Rice, D.E.; Murray, M.E.; Brown, K.S.

1996-01-01T23:59:59.000Z

17

Confirmatory radiological survey for the 190-C Main Pumphouse Facility decommissioning at the Hanford Site, Richland, Washington  

Science Conference Proceedings (OSTI)

An independent assessment of remedial action activities at the 190-C Main Pumphouse Facility at the Hanford Site, Richland, Washington has been accomplished by the Oak Ridge National Laboratory Environmental Assessments Group. The purpose of the assessment was to confirm the site`s compliance with DOE applicable guidelines and provide independent measurements of the activity levels in the 190-C trenches and 105-C process water tunnels. The assessment included reviews of the Decontamination and Decommissioning Plan and data provided in the pre- and post-remedial action surveys. An on-site independent verification survey of the facility was conducted during the period of November 19--21, 1996. The independent verification survey included beta and gamma scans, smears for removable contamination, and direct measurements for beta-gamma activity in the trenches and tunnels. The same measurements and scans, with the addition of alpha measurements, were performed on the floor in the filter repair confinement area. The facility was also spot-checked for direct alpha and beta-gamma activity.

Coleman, R.L. [Oak Ridge National Lab., TN (United States); Forbes, G.H. [Oak Ridge National Lab., Grand Junction, CO (United States). Environmental Technology Section

1997-06-01T23:59:59.000Z

18

A series of low-altitude aerial radiological surveys of selected regions within Areas 3, 5, 8, 9, 11, 18, and 25 at the Nevada Test Site  

SciTech Connect

A series of low-altitude, aerial radiological surveys of selected regions within Areas 3, 5, 8, 9, 11, 18,and 25 of the Nevada Test Site was conducted from December 1996 through June 1999. The surveys were conducted for the US Department of Energy by the Remote Sensing Laboratory, located in Las Vegas, Nevada, and maintained and operated by Bechtel Nevada. The flights were conducted at a nominal altitude of 15 meters above ground level along a set of parallel flight lines spaced 23 meters apart. The purpose of these low-altitude surveys was to measure, map, and define the areas of americium-241 activity. The americium contamination will be used to determine the areas of plutonium contamination. Americium-241 activity was detected within 8 of the 11 regions. The three regions where americium-241 was not detected were in the inactive Nuclear Rocket Development Station complex in Area 25, which encompassed the Test Cell A and Test Cell C reactor test stands and the Reactor Maintenance Assembly and Disassembly facility.

Colton, D.P.

1999-12-01T23:59:59.000Z

19

A Mobile High Resolution Gamma Ray Spectrometry System for Radiological Surveys  

Science Conference Proceedings (OSTI)

Surveying nuclear power plant sites for radioactive contamination is an expensive part of the overall decommissioning process. This report details a mobile radiological survey system designed to produce a rapid and cost effective radiological characterization of outdoor land areas. The system combines high resolution gamma ray spectrometry with modern automated surveying techniques to precisely locate areas of contamination.

1998-12-04T23:59:59.000Z

20

Nevada Test Site Radiological Control Manual  

Science Conference Proceedings (OSTI)

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

Radiological Control Managers' Council Nevada Test Site

2010-02-09T23:59:59.000Z

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


21

Radiological Habits Survey: Bradwell, 2007  

E-Print Network (OSTI)

.2 Comparisons with previous surveys 55 Table A Comparison between 1999 and 2007 aquatic internal exposure 56 3. METHODS FOR DATA ANALYSIS 19 3.1 Data recording 19 3.2 Data analysis 21 4. AQUATIC RADIATION RADIATION PATHWAYS 41 5.1 Terrestrial survey area 41 5.2 Unusual pathways 42 5.3 Retailers 43 5.4 Food

22

Radiological Habits Survey: Wylfa, 2004  

E-Print Network (OSTI)

.7 Internal exposure 28 4.8 External exposure 31 4.9 Water based activities 33 5. TERRESTRIAL RADIATION PATHWAYS 34 5.1 Terrestrial survey area 34 5.2 Wholesalers and retailers 36 5.3 Internal exposure 36 6 analysis 21 4. AQUATIC RADIATION PATHWAYS 23 4.1 Aquatic survey area 23 4.2 Commercial fisheries 25 4

23

Radiological Habits Survey: Winfrith, 2003  

E-Print Network (OSTI)

.7 Internal exposure 26 4.8 External exposure 30 4.9 Water based activities 31 5 TERRESTRIAL RADIATION exposure 37 6 DIRECT RADIATION PATHWAYS 40 6.1 Direct radiation survey area 40 6.2 Residential activities analysis 19 4 AQUATIC RADIATION PATHWAYS 21 4.1 Aquatic survey area 21 4.2 Commercial fisheries 23 4

24

Radiological Habits Survey: Amersham, 2004  

E-Print Network (OSTI)

.4 Wholesalers and retailers 29 4.5 Internal exposure 29 4.6 External exposure 30 4.7 Water based activities 32 5. TERRESTRIAL RADIATION PATHWAYS 35 5.1 Terrestrial survey area 35 5.2 Wholesalers and retailers 39 5.3 Internal exposure 39 6. DIRECT RADIATION PATHWAYS 43 6.1 Direct radiation survey area 43 6.2 Residential activities

25

Radiological Habits Survey, Dounreay, 2003  

E-Print Network (OSTI)

.5 Internal exposure 25 4.6 External exposure 28 5. TERRESTRIAL RADIATION PATHWAYS 32 5.1 Terrestrial survey area and local produce 32 5.2 Novel radiation pathways 33 5.3 Land cover 33 5.4 Internal exposure 34 5 conversion 14 3.2 Determination of critical groups 14 4. AQUATIC RADIATION PATHWAYS 18 4.1 Aquatic survey

26

An aerial radiological survey of Naturita, Colorado and surrounding area  

SciTech Connect

An aerial radiological survey of four areas in the vicinity of the inactive uranium mill tailings site at Naturita, Colorado was conducted in September 1981. The average background radiation exposure rate (normalized to 3 feet above the ground) was about 10 to 16 microroentgens per hour ({mu}R/h). Uranium ore or tailings were detected at Naturita, Nucla, East Vancorum, and the general region downriver and downwind from the former mill tailings site.

Jaffe, R.J.

1982-09-01T23:59:59.000Z

27

Radiological Habits Survey: Hartlepool, 2002  

E-Print Network (OSTI)

.4 Seafood wholesalers and retailers 27 4.5 Wildfowl 28 4.6 Other food pathways 28 4.7 Internal exposure 29 4.8 External exposure 32 4.9 Water based activities 35 5. TERRESTRIAL RADIATION PATHWAYS 36 5.1 Terrestrial survey area 36 5.2 Terrestrial food wholesalers and retailers 38 5.3 Internal exposure 38 6. DIRECT

28

Radiological Habits Survey: Cardiff, 2003  

E-Print Network (OSTI)

.4 Seafood wholesalers and retailers 26 4.5 Wildfowl 26 4.6 Internal exposure 27 4.7 External exposure 29 4.2 Terrestrial food wholesalers and retailers 37 5.3 Internal exposure 37 6. COMBINED PATHWAYS 41 7. CONCLUSIONS of the survey 15 3. METHODS FOR DATA ANALYSIS 18 3.1 Data recording 18 3.2 Data analysis 20 4. AQUATIC RADIATION

29

Radiological Habits Survey, Faslane, 2006  

E-Print Network (OSTI)

.3 Land cover 24 5.4 Internal exposure 25 6. DIRECT RADIATION 26 7. COMBINED PATHWAYS 28 8. CONCLUSIONS.5 Wildfowling 18 4.6 Internal exposure 19 4.7 External exposure 21 4.8 Water based activities 22 5. TERRESTRIAL.2 Determination of critical groups 11 3.3 Data analysis 11 4. AQUATIC RADIATION PATHWAYS 15 4.1 Aquatic survey

30

Radiological Habits Survey: Devonport, 2004  

E-Print Network (OSTI)

36 5.2 Wholesalers and retailers 38 5.3 Internal exposure 38 6. DIRECT RADIATION PATHWAYS 42 6.4 Wholesalers and retailers 28 4.5 Wildfowl 28 4.6 Other pathways 28 4.7 Internal exposure 29 4.8 External exposure 31 4.9 Water based activities 34 5. TERRESTRIAL RADIATION PATHWAYS 36 5.1 Terrestrial survey area

31

Radiological Habits Survey: Dungeness, 2005  

E-Print Network (OSTI)

44 5.2 Wholesalers and retailers 47 5.3 Internal exposure 47 6. DIRECT RADIATION PATHWAYS 50 6.4 Wholesalers and retailers 34 4.5 Wildfowl 35 4.6 Other pathways 35 4.7 Internal exposure 36 4.8 External exposure 39 4.9 Water based activities 42 5. TERRESTRIAL RADIATION PATHWAYS 44 5.1 Terrestrial survey area

32

Radiological Habits Survey: Trawsfynydd, 2005  

E-Print Network (OSTI)

5.2 Wholesalers and retailers 36 5.3 Internal exposure 36 6. DIRECT RADIATION PATHWAYS 40 6.1 Direct.3 Angling 28 4.4 Wholesalers and retailers 28 4.5 Wildfowl 28 4.6 Internal exposure 29 4.7 External exposure analysis 22 4. AQUATIC RADIATION PATHWAYS 25 4.1 Aquatic survey area 25 4.2 Commercial fisheries 27 4

33

Radiological Habits Survey, Chapelcross, 2005  

E-Print Network (OSTI)

and local produce 25 5.2 Novel radiation pathways 26 5.3 Land cover 26 5.4 Internal exposure 27 6. DIRECT fisheries 18 4.3 Angling 19 4.4 Seafood wholesalers and retailers 19 4.5 Internal exposure 20 4.6 External exposure 22 4.7 Water based activities 23 5. TERRESTRIAL RADIATION PATHWAYS 25 5.1 Terrestrial survey area

34

Radiological Habits Survey, Hunterston 2001  

E-Print Network (OSTI)

and local produce 25 5.2 Novel radiation pathways 26 5.3 Land cover 26 5.4 Internal exposure 27 5.5 External fisheries 18 4.3 Angling and hobby fishing 19 4.4 Seafood wholesalers and retailers 19 4.5 Internal exposure 19 4.6 External exposure 23 5. TERRESTRIAL RADIATION PATHWAYS 25 5.1 Terrestrial survey area

35

Radiological Habits Survey: Sizewell, 2005  

E-Print Network (OSTI)

.1 Terrestrial survey area 38 5.2 Wholesalers and retailers 40 5.3 Internal exposure 40 6. DIRECT RADIATION fishing 29 4.4 Wholesalers and retailers 30 4.5 Wildfowl 30 4.6 Other pathways 30 4.7 Internal exposure 31 4.8 External exposure 34 4.9 Water based activities 36 5. TERRESTRIAL RADIATION PATHWAYS 38 5

36

Radiological Habits Survey: Sellafield, 2003  

E-Print Network (OSTI)

.4 Seafood wholesalers and retailers 28 4.5 Wildfowl 28 4.6 Other pathways 29 4.7 Internal exposure 29 4.8 External exposure 33 4.9 Water based activities 36 5. TERRESTRIAL RADIATION PATHWAYS 38 5.1 Terrestrial survey area 38 5.2 Terrestrial food wholesalers and retailers 41 5.3 Internal exposure 41 6. DIRECT

37

Radiological decontamination, survey, and statistical release method for vehicles  

SciTech Connect

Earth-moving vehicles (e.g., dump trucks, belly dumps) commonly haul radiologically contaminated materials from a site being remediated to a disposal site. Traditionally, each vehicle must be surveyed before being released. The logistical difficulties of implementing the traditional approach on a large scale demand that an alternative be devised. A statistical method for assessing product quality from a continuous process was adapted to the vehicle decontamination process. This method produced a sampling scheme that automatically compensates and accommodates fluctuating batch sizes and changing conditions without the need to modify or rectify the sampling scheme in the field. Vehicles are randomly selected (sampled) upon completion of the decontamination process to be surveyed for residual radioactive surface contamination. The frequency of sampling is based on the expected number of vehicles passing through the decontamination process in a given period and the confidence level desired. This process has been successfully used for 1 year at the former uranium millsite in Monticello, Utah (a cleanup site regulated under the Comprehensive Environmental Response, Compensation, and Liability Act). The method forces improvement in the quality of the decontamination process and results in a lower likelihood that vehicles exceeding the surface contamination standards are offered for survey. Implementation of this statistical sampling method on Monticello projects has resulted in more efficient processing of vehicles through decontamination and radiological release, saved hundreds of hours of processing time, provided a high level of confidence that release limits are met, and improved the radiological cleanliness of vehicles leaving the controlled site.

Goodwill, M.E.; Lively, J.W.; Morris, R.L.

1996-06-01T23:59:59.000Z

38

Site Energy Surveys  

E-Print Network (OSTI)

Operating improvements and selected investments have already improved US refining and petrochemical energy utilization efficiency by about 20%, compared to 1972 operating efficiencies. This is equivalent to saving well over 250,000 B/D of crude; which is equal to the output of several major synthetic fuels projects! Site Energy Surveys can be an important technique for achieving the next major increment (1520%) in energy savings, even when using existing technology. These surveys encompass the total site, all associated plants, and investigate all aspects of energy requirements, heat integration configurations, steam/power cogeneration possibilities and inefficient practices. After potential energy conservation opportunities have been identified, screening is conducted to develop their economic attractiveness. This presentation reviews factors leading to the need for Site Energy Surveys, the objectives for conducting surveys, the approach utilized, considerations given to values of energy and concludes with overall improvements achieved.

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

1981-01-01T23:59:59.000Z

39

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

40

An aerial radiological survey of Naturita, Colorado and surrounding area. Date of survey: September 1981  

SciTech Connect

An aerial radiological survey of four areas in the vicinity of the inactive uranium mill tailings site at Naturita, Colorado was conducted in September 1981. The average background radiation exposure rate (normalized to 3 feet above the ground) was about 10 to 16 microroentgens per hour ({mu}R/h). Uranium ore or tailings were detected at Naturita, Nucla, East Vancorum, and the general region downriver and downwind from the former mill tailings site.

Jaffe, R.J.

1982-09-01T23:59:59.000Z

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.


41

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

42

Autonomous mobile robot for radiologic surveys  

DOE Patents (OSTI)

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

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

1994-06-28T23:59:59.000Z

43

Autonomous mobile robot for radiologic surveys  

DOE Patents (OSTI)

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

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

1994-01-01T23:59:59.000Z

44

Site-specific waste management instruction - radiological screening facility  

DOE Green Energy (OSTI)

This Site-Specific Waste Management Instruction provides guidance for managing waste generated from radiological sample screening operations conducted to support the Environmental Restoration Contractor`s activities. This document applies only to waste generated within the radiological screening facilities.

G. G. Hopkins

1997-12-31T23:59:59.000Z

45

Results of the radiological survey at 136 West Central Avenue (MJ030), Maywood, New Jersey  

SciTech Connect

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory. A radiological survey of the private, residential property at 136 West Central Avenue, Maywood, New Jersey, was conducted during 1987. The survey and sampling of the ground surface and subsurface were carried out on April 29, 1987.

Foley, R.D.; Crutcher, J.W.; Carrier, R.F.; Floyd, L.M.

1989-02-01T23:59:59.000Z

46

Radiological Surveys Performed in Support of the Demolition and Bulk Disposal Decommissioning Method  

SciTech Connect

Connecticut Yankee Atomic Power Company is decommissioning the Haddam Neck Plant using the 'Demolition and Bulk Disposal' method, or commonly referred to as 'Rip and Ship'. In general, completing the project using this method entails the removal of all irradiated fuel and highly contaminated systems and components, and the subsequent demolition of the above ground portions of most site structures. Since most structures are removed from site, cost and time savings are realized by virtually eliminating the need for remediation. However, this method of decommissioning creates more waste, both radiological and non-radiological, which must be segregated, packaged and disposed of properly. Prior to demolition, various types of radiological surveys must be performed and work controls put into place to minimize the spread of contamination to other areas of the site, and to prevent the inadvertent release of radioactive materials from the site. This paper will discuss the various types of radiological surveys performed, and controls implemented, in support of the demolition and bulk material disposal decommissioning method, with the emphasis on pre-demolition surveys. Details will be provided on the release criteria, survey design, survey implementation and data analysis on each of the various surveys, as well as a discussion on the controls implemented to prevent the various wastes from inadvertently being shipped to an inappropriate disposal facility. This paper will also strive to provide lessons learned for future projects that utilize the demolition and bulk disposal decommissioning method. (authors)

Yetter, R.F. [Babcock Services, Inc., 1840 Terminal Drive, Richland, WA 99352 (United States); Newson, C.T. [Connecticut Yankee Atomic Power Company, 362 Injun Hollow Road, East Hampton, CT 06424 (United States)

2006-07-01T23:59:59.000Z

47

Quarterly environmental radiological survey summary second quarter 1996 100, 200, 300 and 600 areas  

Science Conference Proceedings (OSTI)

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Second Quarter 1996 survey results and the status of actions required from current and past reports are summarized below: All the routine environmental radiological surveys scheduled during April, May, and June 1996 were completed. One Hundred twenty- five environmental radiological surveys were performed during the second quarter of 1996, twenty nine at the active waste sites and ninety six at the inactive waste sites. Contamination above background levels Wag found at three of the active waste sites and fifteen of the inactive waste sites. Contamination levels as high as 65,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys seven were in Underground Radioactive Material (URM) areas and one was in an unposted area. The contamination found within three of the URM areas was immediately cleaned up and no further action was required. In the remaining four sites the areas were posted and will require decontamination. At the site where there was no posting, the contamination was below action levels, however, Site Support Services was notified. Radiological Problem Reports (RPR`s) were issued and the sites were turned over to the landlord for further action if required. During the second quarter 1996, 0. 7 hectares (1.7 acres) were stabilized and radiologically down posted from Surface Contamination (SC) to URM. No Compliance Assessment Reports (CARS) were issued for sites found out of compliance with standards identified in WHC-CM-7-5, Environmental Compliance. No Surveillance Compliance/Inspection Reports (SCIR) were closed during the Second Quarter of 1996. Five open SCIRB had not been resolved.

Dorian, J.J., Westinghouse Hanford

1996-07-26T23:59:59.000Z

48

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

49

Results of the independent radiological verification survey at 112 Avenue E, Lodi, New Jersey (LJ082V)  

SciTech Connect

Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the U.S. Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (112 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property. Based on the remedial action and verification survey data reported in this document, all radiological measurements fall below the limits prescribed by DOE radiological guidelines established for this site, and the property at 112 Avenue E, Lodi, New Jersey successfully meets the DOE radiological guidelines for unrestricted use.

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

1996-09-01T23:59:59.000Z

50

Results of the independent radiological verification survey at 113 Avenue E, Lodi, New Jersey (LJ081V)  

SciTech Connect

Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the U. S. Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (113 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property.

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

1996-09-01T23:59:59.000Z

51

Results of the independent radiological verification survey at 108 Avenue E, Lodi, New Jersey (LJ084V)  

SciTech Connect

Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the US Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (108 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property.

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

1996-09-01T23:59:59.000Z

52

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

53

Radiological Habits Survey: Berkeley and Oldbury, 2007  

E-Print Network (OSTI)

aquatic internal exposure 63 pathways at Berkeley and Oldbury Table B Comparison between 2001 and 2007 of the survey 18 3. METHODS FOR DATA ANALYSIS 22 3.1 Data recording 22 3.2 Data analysis 24 4. AQUATIC RADIATION. TERRESTRIAL RADIATION PATHWAYS 45 5.1 Terrestrial survey area 45 5.2 Unusual pathways 48 5.3 Wholesalers

54

Radiological Habits Survey: Sellafield Review, 2005  

E-Print Network (OSTI)

2. Survey area 3 3. Conduct of survey 3 4. Data analysis 4 4.1 Internal exposure 4 Figure 2 Critical;3 1. Introduction This report describes a review of public radiation exposure pathways due to liquid 1996-2005 5 4.2 External exposure 6 5. Conclusions 7 6. Recommendations 7 7. References 7 Figure 1

55

FACT SHEET ERDA'S RADIOLOGICAL SURVEY PROGRAM INTRODUCTION  

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

New York; Site A, Cook County Forest Preserve, Palos Park, Illinois; Bridgeport Brass Metal Extfusion Plant (now property of General Motors Corporation), Adrian, Michigan;...

56

Radiological Habits Survey: Aldermaston/Burghfield, 2002  

E-Print Network (OSTI)

.3 Internal exposure 30 6 ALDERMASTON DIRECT RADIATION 33 6.1 Direct radiation survey area 33 6.2 Residential pathways 22 4.5 Internal exposure 23 4.6 External exposure 25 4.7 Water based activities 26 5 TERRESTRIAL 3 METHODS FOR DATA ANALYSIS 16 3.1 Data recording 16 3.2 Data analysis 18 4 AQUATIC RADIATION

57

Radiological Habits Survey, Rosyth Business Park, 2005  

E-Print Network (OSTI)

.3 Land cover 17 5.4 Internal exposure 17 6. DIRECT RADIATION 18 7. COMBINED PATHWAYS 19 8. CONCLUSIONS.5 Wildfowling 14 4.6 Internal exposure 14 4.7 External exposure 15 4.8 Water based activities 16 5. TERRESTRIAL 3.2 Determination of critical groups 8 4. AQUATIC RADIATION PATHWAYS 9 4.1 Aquatic survey area 9 4

58

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

59

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 . . . . . . . . .

60

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 ,.--(_ ~_ -_- --- -_ _.. ;

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


61

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

Science Conference Proceedings (OSTI)

Results of a radiological survey of the inactive uranium-mill site a Naturita, Colorado, conducted in May 1976, are presented. The spread of tailings was detected in the area surrounding the site by means of direct above ground gamma measurements and analysis of surface and subsurface soil samples. Radiochemical analyses of water samples in the vicinity of the tailings pile indicate local surface water contamination immediately downstream from the pile, although the /sup 226/Ra concentration in the water at that point as well below the concentration guide for drinking water. The calculated subsoil distribution of /sup 226/Ra in onsite holes is presented graphically. The tailings at this site were removed and reprocessed at another location. This operation was completed and reclamation of the site was conducted in 1978. Consequently the information in this report documents radiological conditions that no longer exist.

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

1980-03-01T23:59:59.000Z

62

Results of the radiological survey at 266 East Spring Valley Avenue (MJ024), Hackensack, New Jersey  

SciTech Connect

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE, by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory. A radiological survey of the private, residential property at 266 East Spring Valley Avenue, Hackensack, New Jersey, was conducted during 1987. The survey and sampling of the ground surface and subsurface were carried out on April 23, 1987. 4 refs., 2 figs., 3 tabs.

Foley, R.D.; Crutcher, J.W.; Carrier, R.F.; Floyd, L.M.

1989-02-01T23:59:59.000Z

63

Radiological verification survey results at the Pompton Plains Railroad Spur, Pequannock, New Jersey (PJ008V)  

SciTech Connect

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

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

1995-05-01T23:59:59.000Z

64

An Aerial Radiological Survey of the Yucca Mountain Project Proposed Land Withdrawal and Adjacent Areas  

SciTech Connect

An aerial radiological survey of the Yucca Mountain Project (YMP) proposed land withdrawal was conducted from January to April 2006, and encompassed a total area of approximately 284 square miles (73,556 hectares). The aerial radiological survey was conducted to provide a sound technical basis and rigorous statistical approach for determining the potential presence of radiological contaminants in the Yucca Mountain proposed Land withdrawal area. The survey site included land areas currently managed by the Bureau of Land Management, the U.S. Air Force as part of the Nevada Test and Training Range or the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as part of the Nevada Test Site (NTS). The survey was flown at an approximate ground speed of 70 knots (36 meters per second), at a nominal altitude of 150 ft (46 m) above ground level, along a set of parallel flight lines spaced 250 ft (76 m) apart. The flight lines were oriented in a north-south trajectory. The survey was conducted by the DOE NNSA/NSO Remote Sensing Laboratory-Nellis, which is located in Las Vegas, Nevada. The aerial survey was conducted at the request of the DOE Office of Civilian Radioactive Waste Management. The primary contaminant of concern was identified by YMP personnel as cesium-137 ({sup 137}Cs). Due to the proposed land withdrawal area's proximity to the historical Nuclear Rocket Development Station (NRDS) facilities located on the NTS, the aerial survey system required sufficient sensitivity to discriminate between dispersed but elevated {sup 137}Cs levels from those normally encountered from worldwide fallout. As part of that process, the survey also measured and mapped the exposure-rate levels that currently existed within the survey area. The inferred aerial exposure rates of the natural terrestrial background radiation varied from less than 3 to 22 microroentgens per hour. This range of exposure rates was primarily due to the surface geological features within the survey area. The survey area has extensive areas of desert valleys, mountain ranges, extinct volcanic cones, and old lava flows. With the exception of five areas identified within the NRDS boundaries (discussed later in this report), there were no areas within the survey that exceeded aerial survey minimum detectable concentration levels of 0.4 through 0.7 picocuries per gram (pCi/g). The {sup 137}Cs levels do not exceed typical worldwide fallout levels for the continental United States.

Craig Lyons, Thane Hendricks

2006-07-01T23:59:59.000Z

65

Site survey method and apparatus  

SciTech Connect

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.

Oldham, James G. (Albuquerque, NM); Spencer, Charles R. (Boise, ID); Begley, Carl L. (Albuquerque, NM); Meyer, H. Robert (Albuquerque, NM)

1991-06-18T23:59:59.000Z

66

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

67

An aerial radiological survey of the Ames Laboratory and surrounding area, Ames, Iowa. Date of survey: July 1991  

Science Conference Proceedings (OSTI)

An aerial radiological survey of the Ames Laboratory and surrounding area in Ames, Iowa, was conducted during the period July 15--25, 1991. The purpose of the survey was to measure and document the terrestrial radiological environment at the Ames Laboratory and the surrounding area for use in effective environmental management and emergency response planning. The aerial survey was flown at an altitude of 200 feet (61 meters) along a series of parallel lines 350 feet (107 meters) apart. The survey encompassed an area of 36 square miles (93 square kilometers) and included the city of Ames, Iowa, and the Iowa State University. The results are reported as exposure rates at 1 meter above ground level (inferred from the aerial data) in the form of a gamma radiation contour map. Typical background exposure rates were found to vary from 7 to 9 microroentgens per hour ({mu}R/h). No anomalous radiation levels were detected at the Ames Laboratory. However, one anomalous radiation source was detected at an industrial storage yard in the city of Ames. In support of the aerial survey, ground-based exposure rate and soil sample measurements were obtained at several sites within the survey perimeter. The results of the aerial and ground-based measurements were found to agree within the expected uncertainty of {+-}15%.

Maurer, R.J.

1993-04-01T23:59:59.000Z

68

Results of the radiological survey at Essex Street and State Route 17 (MJ036), Maywood, New Jersey  

SciTech Connect

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE, by members of the Measurement Applications and Development Group of the Oak Ridge National Laboratory. A radiological survey of the commercial property at Essex Street and State Route 17, Maywood, New Jersey, was conducted during 1987. 4 refs., 2 figs., 3 tabs.

Foley, R.D.; Crutcher, J.W.; Carrier, R.F.; Floyd, L.M.

1989-02-01T23:59:59.000Z

69

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

70

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

71

Finding and evaluating potential radiological problems in the vicinity of uranium milling sites  

Science Conference Proceedings (OSTI)

Tailings at inactive milling sites usually have a low frequency of human occupancy but continuously generate /sup 222/Rn into the atmosphere. Measurements of airborne /sup 222/Rn and /sup 222/Rn flux are made on the sites to define the tailings source term. Concurrently with these measurements, an ambient /sup 222/Rn monitoring network is established off-site and a meteolrololgical station is established at or near the mill site. Radioactivity can migrate to areas outside of site boundaries by wind and water erosion, groundwater transport, spillage of incoming purposes. In order to identify and assess off-site radioactivity on properties in the vicinity of milling sites, a combination of aerial and ground-level radiological monitoring techniques are used. The ground mobile gamma-ray scan is conducted using a vehicle equipped with sensitive gamma-ray detectors. The detectors are shielded so that gamma radiation input is viewed through only one side of the vehicle. This system is capable of precisely locating properties which have anomalously high gamma radiation levels caused by the presence of tailings. Subsequently, these properties are identified as candidate vicinity properties and are scheduled for radiological surveys subject to the property owner's consent. The comprehensive radiological surveys conducted at these vicinity properties determine the amount, type, and location of tailings materials. Structures on a vicinity property are carefully surveyed to determine the presence or absence of construction-related uses of tailings. If structural uses of tailings are found, air samples are analyzed for /sup 222/Rn progeny, short-term continuous /sup 222/Rn monitoring is instituted, and /sup 222/Rn flux rate from tailings are estimated. If warranted, long-term /sup 222/Rn and progeny measurements are made.

Goldsmith, W.A.; Yates, W.G.

1982-01-01T23:59:59.000Z

72

Interim Report on Cumulative Risk Assessment for Radiological and Chemical Constituents of Concern at Decommissioning Sites  

Science Conference Proceedings (OSTI)

Decommissioning nuclear facilities focus extensive efforts on site characterization to demonstrate regulatory compliance in the termination of site licenses. Many decommissioning sites, while recognizing radiological characterization and assessment needs, lacked experience in chemical risk assessment. This report documents plant approaches for performing cumulative risk assessments of both radiological and non-radiological constituents of concern.

2005-12-08T23:59:59.000Z

73

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

Science Conference Proceedings (OSTI)

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

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

1980-06-01T23:59:59.000Z

74

An aerial radiological survey of the Oak Ridge Reservation, Oak Ridge, Tennessee. Date of survey: April 1992  

Science Conference Proceedings (OSTI)

An aerial radiological survey of the Oak Ridge Reservation (ORR) and surrounding area in Oak Ridge, Tennessee, was conducted during the period March 30 to April 14,1992. The purpose of the survey was to measure and document the terrestrial radiological environment of the Oak Ridge Reservation for use in environmental management programs and emergency response planning. The aerial survey was flown at an altitude of 150 feet (46 meters) along a series of parallel lines 250 feet (76 meters) apart and included X-10 (Oak Ridge National Laboratory), K-25 (former Gaseous Diffusion Plant), Y-12 (Weapons Production Plant), the Freels Bend Area and Oak Ridge Institute for Science and Education, the East Fork Poplar Creek (100-year floodplain extending from K-25 to Y-12), Elza Gate (former uranium ore storage site located in the city of Oak Ridge), Parcel A, the Clinch River (river banks extending from Melton Hill Dam to the city of Kingston), and the CSX Railroad Tracks (extending from Y-12 to the city of Oak Ridge). The survey encompassed approximately 55 square miles (1 41 square kilometers) of the Oak Ridge Reservation and surrounding area.

Maurer, R.J.

1993-04-01T23:59:59.000Z

75

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

Science Conference Proceedings (OSTI)

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

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

1980-03-01T23:59:59.000Z

76

8-1 1999 SITE ENVIRONMENTAL REPORT CHAPTER 8: RADIOLOGICAL DOSE ASSESSMENT  

E-Print Network (OSTI)

8-1 1999 SITE ENVIRONMENTAL REPORT CHAPTER 8: RADIOLOGICAL DOSE ASSESSMENT During 1999, potential (0.4 mSv) per year. Radiological Dose Assessment 8CHAPTER1999 SITE ENVIRONMENTAL REPORT B R O O K H: RADIOLOGICAL DOSE ASSESSMENT 8.1 AMBIENT RADIATION MEASUREMENTS BNL measures environmental background radiation

Homes, Christopher C.

77

Radiological survey of the inactive uranium-mill tailings at Riverton, Wyoming  

SciTech Connect

Results of a radiological survey performed at the Riverton, Wyoming site in July 1976, are presented. The average external gamma exposure rate at 1 m over the tailings pile was 56 ..mu..R/hr. The corresponding rate for the former mill area was 97 ..mu..R/hr. Movement of tailings particles in a dry wash is evident; but it appears that, in general, the earth cover over the tailings pile has been effective in limiting both wind and water erosion of the tailings. The calculated concentration of /sup 226/Ra as a function of depth in 15 augered holes is presented graphically. A survey of the Teton Division Lumber Company property in Riverton showed a maximum external gamma exposure rate of 270 ..mu..R/hr.

Haywood, F.F.; Lorenzo, D.; Christian, D.J.; Chou, K.D.; Ellis, B.S.; Shinpaugh, W.H.

1980-03-01T23:59:59.000Z

78

CHAPTER 9: RADIOLOGICAL DOSE ASSESSMENT 1998 SITE ENVIRONMENTAL REPORT9-1  

E-Print Network (OSTI)

CHAPTER 9: RADIOLOGICAL DOSE ASSESSMENT 1998 SITE ENVIRONMENTAL REPORT9-1 9C H A P T E R Radiological Dose Assessment This chapter discusses the potential radio- logical doses to offsite individuals: RADIOLOGICAL DOSE ASSESSMENT 9.1 EXTERNAL PENETRATING RADIATION MEASUREMENTS The Brookhaven National Laboratory

Homes, Christopher C.

79

An Aerial Radiological Survey of the City of North Las Vegas (Downtown) and the Motor Speedway  

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 on December 11-12, 2007, with the purpose of mapping natural radiation background and locating any man-made radioactive sources. The survey covered 19.4 square miles (9.2 square miles over the downtown area of the City of North Las Vegas and 10.2 square miles over the Las Vegas Motor Speedway [LVMS]). The flight lines over the surveyed areas are presented in Figures 1 and 2. A total of four 2.5-hour-long flights were performed at an altitude of 150 ft above ground level (AGL) with 300 ft 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 sources. 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 City of North Las Vegas and LVMS security along with the gross counts-based exposure rate and man-made counts maps.

Piotr Wasiolek

2007-12-01T23:59:59.000Z

80

8-1 SITE ENVIRONMENTAL REPORT 2000 CHAPTER 8: RADIOLOGICAL DOSE ASSESSMENT  

E-Print Network (OSTI)

Radiological Dose Assessment 8 2004 SITE ENVIRONMENTAL REPORT8-1 DRAFT Brookhaven National, and any immersion dose. The dose assessment has routinely shown that the total effective dose equivalent-site locations are with the #12;2004 SITE ENVIRONMENTAL REPORT 8-2 CHAPTER 8: RADIOLOGICAL DOSE ASSESSMENT DRAFT

Homes, Christopher C.

Note: This page contains sample records for the topic "radiological surveys site" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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81

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

SciTech Connect

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

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

1999-01-01T23:59:59.000Z

82

An aerial radiological survey of the West Valley Demonstration Project and surrounding area, West Valley, New York  

SciTech Connect

An aerial radiological survey of the West Valley Demonstration Project and the surrounding area was conducted from mid-August through early September 1984 by EG G Energy Measurements, Inc. for the United States Department of Energy. The radiological survey was part of the United States Department of Energy Comprehensive Integrated Remote Sensing (CIRS) program, which provides state-of-the-art remote sensing to support the needs of the various DOE facilities. The survey consisted of airborne measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. These measurements allowed an estimate of the distribution of isotopic concentrations in the area surrounding the project site. Results are reported as isopleths superimposed on aerial photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. 8 refs., 16 figs., 9 tabs.

Berry, H.A.

1991-09-01T23:59:59.000Z

83

An aerial radiological survey of the Robert Emmett Ginna Nuclear Power Plant and surrounding area, Ontario, New York  

SciTech Connect

Terrestrial radioactivity surrounding the Robert Emmett Ginna Nuclear Power Plant was measured using aerial radiological surveying 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 employed 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 the area surrounding the plant site varied from 6 to 10 microroentgens per hour. Man-made radiation (cobalt-60 within the plant site and cesium-1 37 directly over the reactor) was found at the plant site. In addition, small areas of suspected cesium-137 activity were found within the survey areas. Other than these small sites, the survey area was free of man-made radioac- tivity.

Proctor, A.E.

1997-06-01T23:59:59.000Z

84

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

SciTech Connect

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

Colin Okada

2010-09-16T23:59:59.000Z

85

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

86

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

87

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

88

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

89

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

SciTech Connect

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

W.C. Adams

2007-03-13T23:59:59.000Z

90

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

91

An aerial radiological survey of the Fernald Environmental Management Project and surrounding area, Fernald, Ohio  

SciTech Connect

An aerial radiological survey was conducted from May 17--22, 1994, over a 36 square mile (93 square kilometer) area centered on the Fernald Environmental Management Project located in Fernald, Ohio. The purpose of the survey was to detect anomalous gamma radiation in the environment surrounding the plant. The survey was conducted at a nominal altitude of 150 feet (46 meters) with a line spacing of 250 feet (76 meters). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter (3.3 feet) above ground was prepared and overlaid on an aerial photograph of the area. Analysis of the data for man made sources showed five sites within the boundaries of the Fernald Environmental Management Project having elevated readings. The exposure rates outside the plant boundary were typical of naturally occurring background radiation. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries to supplement the aerial data. It was concluded that although the radionuclides identified in the high-exposure-rate areas are naturally occurring, the levels encountered are greatly enhanced due to industrial activities at the plant.

Phoenix, K.A.

1997-04-01T23:59:59.000Z

92

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

SciTech Connect

Results of a radiological survey of two inactive mill sites near Slick Rock, Colorado, in April 1976 are presented. One mill, referred to in this report as North Continent (NC), was operated primarily for recovery of radium and vanadium and, only briefly, uranium. The Union Carbide Corporation (UCC) mill produced a uranium concentrate for processing elsewhere and, although low-level contamination with /sup 226/Ra was widespread at this site, the concentration of this nuclide in tailings was much lower than at the NC site. The latter site also has an area with a high above-ground gamma dose rate (2700 ..mu..R/hr) and a high-surface /sup 226/Ra concentration (5800 pCi/g). This area, which is believed to have been a liquid disposal location during plant operations, is contained within a fence. A solid disposal area outside the present fence contains miscellaneous contaminated debris. The estimated concentration of /sup 226/Ra as a function of depth, based on gamma hole-logging data, is presented for 27 holes drilled at the two sites.

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

1980-06-01T23:59:59.000Z

93

An aerial radiological survey of Project Rulison and surrounding area, Battlement Creek Valley, Colorado  

SciTech Connect

An aerial radiological survey was conducted over the Project Rulison site, 40 miles (64 kilometers) northeast of Grand Junction, Colorado, from July 6 through July 12, 1993. Parallel lines were flown at intervals of 250 feet (76 meters) over a 6.5-square-mile (17-square-kilometer) area at a 200-foot (61-meter) altitude surrounding Battlement Creek Valley. 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 3.5 to 12.5 {mu}R/h (excluding cosmic) at 1 meter above ground level. No anomalous or man-made isotopes were found.

NONE

1995-08-01T23:59:59.000Z

94

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

Science Conference Proceedings (OSTI)

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

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

1980-10-01T23:59:59.000Z

95

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

96

Results of the independent radiological verification survey at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts (CIO001V)  

SciTech Connect

The Chapman Valve Manufacturing Company in Indian Orchard, Massachusetts was one of many companies performing work during the 1940s associated with the development of nuclear energy for defense-related projects for the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC). In 1991, a radiological survey was conducted at the site. The survey report indicated {sup 238}U contamination in excess of the DOE criteria for surface contamination, and some {sup 235}U residues in the west end of the building. Decontamination of the facility to supplemental guidelines, derived by a hazard assessment based on appropriate scenarios for this building, was conducted by subcontractor personnel in 1995 under the direction of Bechtel National Incorporated (BNI), the project management contractor for FUSRAP. The independent radiological verification survey detailed in this report was performed in July and August 1995 under the FUSRAP program by members of ORNL at the request of DOE. The radiological verification survey of the west end of the building included gamma, alpha, and beta-gamma scans for fixed contamination, smear sampling for transferable contamination, and radionuclide analysis of soil samples taken from outside the building and from excavations in the concrete floor inside the building.

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

1997-05-01T23:59:59.000Z

97

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

98

DOE - Office of Legacy Management -- Lowman Mill Site - ID 01  

Office of Legacy Management (LM)

Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Lowman, Idaho, Disposal Site Documents Related to Lowman Mill Site Historical documents may contain...

99

DOE - Office of Legacy Management -- Falls City Mill Site - TX...  

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

Materials Handled: Radiological Survey(s): Site Status: Also see Falls City, Texas, Disposal Site Documents Related to Falls City Mill Site Data Validation Package for...

100

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

Office of Legacy Management (LM)

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

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


101

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

102

Radiological Dose Assessment 8 2009 Site environmental report8-  

E-Print Network (OSTI)

at the Lab- oratory are composed of calcium fluoride and lithium fluoride crystals. Accuracy is verified Biota, provides the guidelines for screening methods to estimate radiological doses to aquatic animals

Homes, Christopher C.

103

Radiological Dose Assessment 8 2008 Site environmental report8-  

E-Print Network (OSTI)

of calcium fluoride and lithium fluo- ride crystals. Accuracy is verified by exposing the TLD to a known the guidelines for screening methods to estimate radiological doses to aquatic animals, terrestrial plants

Homes, Christopher C.

104

Radiological Dose Assessment 8 2005 Site environmental report8-  

E-Print Network (OSTI)

are composed of calcium fluoride and lithium fluo- ride crystals. The TLDs' accuracy is verified by comparing Biota, provides the guidelines for screening methods to estimate radiological doses to aquatic animals

Homes, Christopher C.

105

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

E-Print Network (OSTI)

8-1 2001 SITE ENVIRONMENTAL REPORT CHAPTER 8: RADIOLOGICAL DOSE ASSESSMENT During 2001: RADIOLOGICAL DOSE ASSESSMENT 011-400 013-400 017-400 030-400 037-400 038-450 049-400 054-400 066-400073-400 074- tional to the absorbed dose of radiation. The environmental TLDs at BNL are composed of calcium fluoride

Homes, Christopher C.

106

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)

107

Radiological survey of the inactive uranium-mill tailings at Lakeview, Oregon  

Science Conference Proceedings (OSTI)

The results of the radiological survey of the inactive uranium-mill site at Lakeview, Oregon, show that the average gamma-ray exposure rate 1 m above the tailings pile and the evaporation pond area (now dry) is close to the average background level for the area (11 ..mu..R/hr). The /sup 226/Ra concentration in most of the surface soil and sediment samples is also at or below the average background value for surface soil samples in the area (0.8 pCi/g). Calculated /sup 226/Ra concentrations, based on gamma radiation measurements in shallow (1-m-deep) holes, are in agreement with the results of surface soil and sediment analyses and with gamma-ray exposure rate measurements. The tailings at this site have been stabilized by the addition of 46 to 60 cm (18 to 24 in.) of soil that supports vigorous growth of vegetation. This treatment, coupled with a low-level inventory of /sup 226/Ra in the tailings (50 Ci), has resulted in limited spread of tailings by wind and water.

Haywood, F.F.; Burden, J.E.; Ellis, B.S.; Loy, E.T.; Shinpaugh, W.H.

1980-06-01T23:59:59.000Z

108

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

Science Conference Proceedings (OSTI)

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

T.J. Vitkus

2008-04-07T23:59:59.000Z

109

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

Science Conference Proceedings (OSTI)

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

W.C. Adams

2008-06-27T23:59:59.000Z

110

Radiological Habits Survey, Dumfries and Galloway Coast, 2002  

E-Print Network (OSTI)

-washed pasture 19 4.6 Internal exposure 19 4.7 External exposure 24 5. COMBINED PATHWAYS 26 6. MATERIALS.2 Determination of critical groups 10 4. AQUATIC RADIATION PATHWAYS 13 4.1 Aquatic survey area 13 4.2 Commercial of radioactivity in the Irish Sea. Potential exposure pathways include con

111

Radiological Habits Survey, HM Naval Base Clyde, Faslane 2000  

E-Print Network (OSTI)

wholesalers and retailers 17 4.5 Internal exposure 17 4.6 External exposure 19 5. TERRESTRIAL RADIATION pathways 22 5.3 Land cover 22 5.4 Internal exposure 23 5.5 External radiation 25 6. COMBINED PATHWAYS 26 7 conversion 10 3.2 Determination of critical groups 11 4. AQUATIC RADIATION PATHWAYS 14 4.1 Aquatic survey

112

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

Science Conference Proceedings (OSTI)

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

Not Available

1993-10-01T23:59:59.000Z

113

Results of the radiological survey at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio (HO001)  

SciTech Connect

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted investigative radiological surveys at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio in 1988 and 1989. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U. The surveys included gamma scans; direct and transferable measurements of alpha, beta, and gamma radiation levels; and dust, debris, air, and soil sampling for radionuclide analyses. 6 refs., 6 figs., 5 tabs.

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

1990-02-01T23:59:59.000Z

114

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site. Revision 1  

Science Conference Proceedings (OSTI)

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. Section 108 of Public Law 95-604 states that the US Department of Energy (DOE) shall ``select and perform remedial actions at the designated processing sites and disposal sites in accordance with the general standards`` prescribed by the EPA. Regulations governing the required remedial action at inactive uranium processing sites were promulgated by the EPA in 1983 and are contained in 40 CFR Part 192 (1993), Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. This document describes the radiological and physical parameters for the remedial action of the soil.

Not Available

1994-01-01T23:59:59.000Z

115

ORISE: Characterization surveys  

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

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

116

An aerial radiological survey of the Tonopah Test Range including Clean Slate 1,2,3, Roller Coaster, decontamination area, Cactus Springs Ranch target areas. Central Nevada  

SciTech Connect

An aerial radiological survey was conducted of major sections of the Tonopah Test Range (TTR) in central Nevada from August through October 1993. The survey consisted of aerial measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. The initial purpose of the survey was to locate depleted uranium (detecting {sup 238}U) from projectiles which had impacted on the TTR. The examination of areas near Cactus Springs Ranch (located near the western boundary of the TTR) and an animal burial area near the Double Track site were secondary objectives. When more widespread than expected {sup 241}Am contamination was found around the Clean Slates sites, the survey was expanded to cover the area surrounding the Clean Slates and also the Double Track site. Results are reported as radiation isopleths superimposed on aerial photographs of the area.

Proctor, A.E.; Hendricks, T.J.

1995-08-01T23:59:59.000Z

117

RADIOLOGICAL SURVEY OF SITE A AND PLOT M  

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

as the tritiated water source is depleted by both horizontal and vertical migration and radioactive decay. Since substantial amounts of tritium still remain below the surface of...

118

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

119

An Aerial Radiological Survey of the Portsmouth Gaseous Diffusion Plant and Surrounding Area, Portsmouth, Ohio  

SciTech Connect

An aerial radiological survey was conducted over the 16 square-mile (~41 square-kilometer) area surrounding the Portsmouth Gaseous Diffusion Plant. The survey was performed in August 2007 utilizing a large array of helicopter mounted sodium iodide detectors. The purpose of the survey was to update the previous radiological survey levels of the environment and surrounding areas of the plant. A search for a missing radium-226 source was also performed. Implied exposure rates, man-made activity, and excess bismuth-214 activity, as calculated from the aerial data are presented in the form of isopleth maps superimposed on imagery of the surveyed area. Ground level and implied aerial exposure rates for nine specific locations are compared. Detected radioisotopes and their associated gamma ray exposure rates were consistent with those expected from normal background emitters. At specific plant locations described in the report, man-made activity was consistent with the operational histories of the location. There was no spectral activity that would indicate the presence of the lost source.

Namdoo Moon

2007-12-01T23:59:59.000Z

120

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

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


121

Workshop on Radiological Surveys in Support of the Edgemont Clean-up Action Program  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, has given Pacific Northwest Laboratory (PNL) the responsibility for the development of procedures for the identification of offsite structures and properties in the vicinity of Edgemont, South Dakota, that require remedial action because of elevated radiation levels caused by residual radioactivity as defined in the Uranium Mill Tailings Radiation Control Act of 1978. In order to acquaint interested investigators with the procedures PNL has developed and the measurements that have been performed at Edgemont using these procedures, and also to obtain suggestions for the improvement of these procedures, PNL organized a "Workshop on Radiological Surveys in Support of the Edgemont Clean-up Action Program" on behalf of the Nuclear Regulatory Commission. This workshop was held in Denver on January 21 and 22, 1981. On the first day of the workshop an in-depth discussion of the procedures employed in the entire radiological survey program at Edgemont was held. It included a description of the equipment, techniques and procedures employed in radon daughter measurements within structures, indoor and outdoor gamma radiation surveys, and 226Ra measurements in surface and sub-surface soil samples. On the second day, the results of the measurements that have been conducted at Edgemont were presented. During the afternoon an open discussion of the radiological survey procedures used at Edgemont was held for the purpose of obtaining suggestions for the possible improvement of these procedures. Many useful suggestions were made and a few modifications in the survey procedures at Edgemont have been made in response to these suggestions.

Perkins, R. W.; Young, J. A.; Jackson, P. O.; Thomas, V. W.; Schwendiman, L. C.

1981-10-01T23:59:59.000Z

122

Mobile robotic surveying performance for planetary surface site characterization  

Science Conference Proceedings (OSTI)

Robotic systems will perform mobile surveys for scientific and engineering purposes as part of future missions on lunar and planetary surfaces. With site characterization as a task objective various system configurations and surveying techniques are ... Keywords: area coverage performance, in-situ remote sensing, planetary surface exploration, robotic surveying, site characterization

Edward Tunstel

2008-08-01T23:59:59.000Z

123

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

124

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

125

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

SciTech Connect

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

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

1984-09-01T23:59:59.000Z

126

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

Science Conference Proceedings (OSTI)

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

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

1984-04-01T23:59:59.000Z

127

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:

128

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

129

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.

1987-08-01T23:59:59.000Z

130

Radiological characterization of Yankee Nuclear Power Station  

SciTech Connect

The Yankee nuclear power station located in Rowe, Massachusetts, permanently ceased power operations on February 26, 1992, after 31 yr of operation. Yankee has since initiated decommissioning planning activities. A significant component of these activities is the determination of the extent of radiological contamination of the Yankee site. This paper describes the site radiological characterization program that has been implemented for decommissioning the Yankee plant. Radiological scoping surveys were completed to support submittal of a decommissioning plan to the U.S. Nuclear Regulatory Commission (NRC) by October 1, 1993. These surveys were designed to provide sufficient detail to estimate the extent of contamination, volume of radiological waste, activity of radiological waste, and personnel dose estimates for removal activities. Surveys were conducted both inside and on the grounds outside of the Yankee plant buildings. Survey results were combined with analytical evaluations to characterize the Yankee site.

Bellini, F.X.; Cumming, E.R.; Hollenbeck, P. (Yankee Atomic Electric Co., Bolton, MA (United States))

1993-01-01T23:59:59.000Z

131

A Survey of Interventional Radiology Awareness Among Final-Year Medical Students in a European Country  

Science Conference Proceedings (OSTI)

Interventional radiology (IR) is a rapidly expanding specialty that is facing the challenges of turf wars and personnel shortages. Appropriate exposure of medical students to this field can be vital to recruitment of potential future trainees or referring physicians. The aim of this study was to determine the knowledge and views of final-year medical students in a single EU country regarding various aspects of IR. An electronic survey was sent via e-mail to all final-year medical students in a European country. The students were given a month to respond to the questionnaire. A total of 234 students of 675 (34.5%) replied to the survey. Of the respondents, 35% had previously completed an attachment to the radiology department. The majority of students (63%) thought their knowledge in radiology in general was poor. The percentage of students who correctly identified procedures performed by interventional radiologists was 69% for Hickman line insertion, 79% for fibroid embolization, and 67.5% for lower limb angioplasty. Sixty percent, 30%, and 47% thought that interventional radiologists perform cardiac angioplasties, perform arterial bypasses, and create AV fistulas, respectively. Forty-nine percent felt that interventional radiologists are surgically trained. Eighty-three percent of students were first made aware of angioplasty by a cardiologist. Thirty-one percent thought that interventional radiologists do ward rounds, 24% thought that interventional radiologists have admitting rights, and 26% felt that interventional radiologists run an outpatient practice. A significant number of students (76%) thought that the job prospects in IR are good or excellent but only 40.5% were willing to consider a career in IR. In conclusion, this study indicates that IR remains a nascent but attractive specialty to the majority of medical students. Further development of the existing informal undergraduate curriculum to address shortcomings will ensure that IR continues to attract the brightest talents to the field.

Leong, Sum; Keeling, Aoife N.; Lee, Michael J., E-mail: mlee@rcsi.i [Beaumont Hospital, Department of Academic Radiology (Ireland)

2009-07-15T23:59:59.000Z

132

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

133

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

134

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

135

Radiological audit of remedial action activities at the processing site, transfer site, and Cheney disposal site Grand Junction, Colorado: Audit date, August 9--11, 1993. Final report  

Science Conference Proceedings (OSTI)

The Uranium Mill Tailing Remedial Action (UMTRA) Project`s Technical Assistance Contractor (TAC) performed a radiological audit of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site, transfer site, and Cheney disposal site in Grand Junction, Colorado. Jim Hylko and Bill James of the TAC conducted this audit August 9 through 11, 1993. Bob Cornish and Frank Bosiljevec represented the US Department of Energy (DOE). This report presents one programmatic finding, eleven site-specific observations, one good practice, and four programmatic observations.

Not Available

1993-08-01T23:59:59.000Z

136

Reconnaissance radiological characterization for the White Point Nike Missile Site, San Pedro, California  

SciTech Connect

This report is the result of field work performed at the former White Point Nike Missile Site, San Pedro, California. The Hazardous Waste Remedial Actions Program tasked the Oak Ridge National Laboratory Pollutant Assessments Group in Grand Junction, Colo., with this project. The objective was to determine whether or not radioisotopes possibly associated with past Department of Defense (DOD) operations were present and within accepted background levels. The radiation survey was accomplished by performing three independent radiation surveys, both outdoors and indoors, and random soil sampling. Initially, the site was land surveyed to develop a grid block system. A background radiation investigation was performed out in the San Pedro area.

Espegren, M.L.; Jensen, M.K.; Pierce, G.A. [Oak Ridge National Lab., TN (United States); Smith, S.M. [Oak Ridge Inst. for Science and Education, Grand Junction, CO (United States)

1993-05-01T23:59:59.000Z

137

Reconnaissance radiological characterization for the White Point Nike Missile Site, San Pedro, California  

SciTech Connect

This report is the result of field work performed at the former White Point Nike Missile Site, San Pedro, California. The Hazardous Waste Remedial Actions Program tasked the Oak Ridge National Laboratory Pollutant Assessments Group in Grand Junction, Colo., with this project. The objective was to determine whether or not radioisotopes possibly associated with past Department of Defense (DOD) operations were present and within accepted background levels. The radiation survey was accomplished by performing three independent radiation surveys, both outdoors and indoors, and random soil sampling. Initially, the site was land surveyed to develop a grid block system. A background radiation investigation was performed out in the San Pedro area.

Espegren, M.L.; Jensen, M.K.; Pierce, G.A. (Oak Ridge National Lab., TN (United States)); Smith, S.M. (Oak Ridge Inst. for Science and Education, Grand Junction, CO (United States))

1993-01-01T23:59:59.000Z

138

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

Science Conference Proceedings (OSTI)

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

Not Available

1988-04-01T23:59:59.000Z

139

Radiological survey of shoreline vegetation from the Hanford Reach of the Columbia River, 1990--1992  

Science Conference Proceedings (OSTI)

A great deal of interest exists concerning the seepage of radiologically contaminated groundwater into the Columbia River where it borders the US Department of Energy`s Hanford Site (Hanford Reach). Areas of particular interest include the 100-N Area, the Old Hanford Townsite, and the 300 Area springs. While the radiological character of the seeps and springs along the Hanford Site shoreline has been studied, less attention has been given to characterizing the radionuclides that may be present in shoreline vegetation. The objective of this study was to characterize radionuclide concentrations in shoreline plants along the Hanford Reach of the Columbia River that were usable by humans for food or other purposes. Vegetation in two areas was found to have elevated levels of radionuclides. Those areas were the 100-N Area and the Old Hanford Townsite. There was also some indication of uranium accumulation in milfoil and onions collected from the 300 Area. Tritium was elevated above background in all areas; {sup 60}Co and {sup 9O}Sr were found in highest concentrations in vegetation from the 100-N Area. Technetium-99 was found in 2 of 12 plants collected from the Old Hanford Townsite and 1 of 10 samples collected upstream from the Vernita Bridge. The concentrations of {sup 137}Cs, {sup 238}Pu, {sup 239,240}Pu, and isotopes of uranium were just above background in all three areas (100-N Area, Old Hanford Townsite, and 300 Area).

Antonio, E.J.; Poston, T.M.; Rickard, W.H. Jr.

1993-09-01T23:59:59.000Z

140

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

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141

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

Science Conference Proceedings (OSTI)

Results of a radiological survey of the inactive uranium-mill tailings near Maybell, Colorado are presented. Measurements of external gamma exposure rate at 1 m above the tailings ranged 16 to 340 ..mu..R/hr with an average value of 65 ..mu..R/hr. Radionuclide analysis of offsite soil and sediment samples, as well as above-ground gamma exposure rate measurements defined the spread of contamination around the tailings pile. This spread is greatest toward the east, in the direction of surface water runoff. Calculated concentrations of /sup 226/Ra in all of the holes drilled in the tailngs, based on gamma monitoring data, showed maximum concentrations in the range 100 to 800 pCi/g.

Haywood, F.F.; Perdue, P.T.; Ellis, B.S.

1980-03-01T23:59:59.000Z

142

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

SciTech Connect

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

Berry, H.A.

1987-02-01T23:59:59.000Z

143

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

Science Conference Proceedings (OSTI)

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

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

2012-11-12T23:59:59.000Z

144

Confirmatory radiological survey of portions of the former A. H. Robins Research Center, Richmond, Virginia  

SciTech Connect

The former A.H. Robins Research Center, in Richmond, VA, was devoted primarily to the research and development of pharmaceuticals. The use of radionuclides at the A.H. Robins Research Center was first begun in the early 1960s and the facility is now operating under Nuclear Regulatory Commission (NRC) License No. 45-09042-01. A. H. Robins' Drug Metabolism Department used radioactive material (H-3, C-14, Na-22, P-32, S-35, CI-36, Ca-45, Cr-51, Ni-63, Rb-86, I-125, I-129, I-131, and Cs-137) in laboratory tracer studies on animals, for calibration of instrumentation, and for research analyses. The radionuclides were used in various,rooms throughout the facility. Following its acquisition by American Home Products in 1990, radionuclide activities were discontinued at this facility. The process for the termination of the material license for A.H. Robins (AHR) was initiated by the Corporate Radiation Health Safety Officer of Wyeth-Ayerst Research (WAR), another wholly owned subsidiary of American Home Products (AHP). In June 1990, WAR developed and submitted a decommissioning plan to the NRC. A radiological survey of the areas in which radionuclides were known to have been handled was performed to determine the extent of the contamination. During the cleanup and survey of the facility, the licensee identified H-3 and C-14 as the major

Adams, W.C.

1992-05-01T23:59:59.000Z

145

2010 Ecological Survey of the Pacific Northwest National Laboratory Site  

Science Conference Proceedings (OSTI)

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

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

2011-02-16T23:59:59.000Z

146

DOE - Office of Legacy Management -- Project Gnome Site - NM...  

Office of Legacy Management (LM)

Materials Handled: Radiological Survey(s): Site Status: Also see Gnome-Coach, New Mexico, Site Documents Related to Project Gnome Site Fact Sheet Gnome-Coach: The Gnome-Coach...

147

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

Science Conference Proceedings (OSTI)

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

Cummins, C.L.

1994-09-01T23:59:59.000Z

148

2011 Annual Ecological Survey: Pacific Northwest National Laboratory Site  

Science Conference Proceedings (OSTI)

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

Becker, James M.; Chamness, Michele A.

2012-02-27T23:59:59.000Z

149

An evaluation of the chemical, radiological, and ecological conditions of West Lake on the Hanford site  

Science Conference Proceedings (OSTI)

West Lake and its immediate surrounding basin represent a unique habitat that is dominated by highly saline water and soil. The basin offers a valuable research site for studies of a rare and complex wetland area in the desert. This report is an evaluation of the chemical, radiological, and ecological conditions at West Lake and describes how ground water influences site properties. The scope of this evaluation consisted of a sampling program in 1989 and a review of data from the perspective of assessing the impact of Hanford Site operations on the physical, chemical, and ecological conditions of West Lake and its surrounding basin. The water level in West Lake fluctuates in relation to changes in the water table. The connection between West Lake and ground water is also supported by the presence of {sup 3}H and {sup 99}Tc in the ground water and in the lake. There are relatively high concentrations of uranium in West Lake; the highest concentrations are found in the northernmost isolated pool. Analyses of water, sediment, vegetation, and soil indicate possible shifts of isotropic ratios that indicate a reduction of {sup 235}U. Uranium-236 was not detected in West Lake water; its presence would indicate neutron-activated {sup 235}U from fuel reprocessing at Hanford. Trace metals are found at elevated concentrations in West Lake. Arsenic, chromium, copper, and zinc were found at levels in excess of US Environmental Protection Agency water quality criteria. Levels of radiological and chemical contamination in the West Lake basin are relatively low. Concentrations of fission isotopes exceed those that could be explained by atmospheric fallout, but fall short of action levels for active waste management areas. 31 refs., 8 figs., 18 tabs.

Poston, T.M.; Price, K.L.; Newcomer, D.R.

1991-03-01T23:59:59.000Z

150

AUTOMATED RADIOLOGICAL MONITORING AT A RUSSIAN MINISTRY OF DEFENCE NAVAL SITE.  

SciTech Connect

The Arctic Military Environmental Cooperation (AMEC) Program is a cooperative effort between the military establishments of the Kingdom of Norway, the Russian Federation, and the US. This paper discusses joint activities conducted over the past year among Norwegian, Russian, and US technical experts on a project to develop, demonstrate and implement automated radiological monitoring at Russian Navy facilities engaged in the dismantlement of nuclear-powered strategic ballistic missile launching submarines. Radiological monitoring is needed at these facilities to help protect workers engaged in the dismantlement program and the public living within the footprint of routine and accidental radiation exposure areas. By providing remote stand-alone monitoring, the Russian Navy will achieve added protection due to the defense-in-depth strategy afforded by local (at the site), regional (Kola) and national-level (Moscow) oversight. The system being implemented at the Polyaminsky Russian Naval Shipyard was developed from a working model tested at the Russian Institute for Nuclear Safety, Moscow, Russia. It includes Russian manufactured terrestrial and underwater gamma detectors, smart controllers for graded sampling, radio-modems for offsite transmission of the data, and a data fusion/display system: The data fusion/display system is derived from the Norwegian Picasso AMEC Environmental Monitoring software package. This computer package allows monitoring personnel to review the real-time and historical status of monitoring at specific sites and objects and to establish new monitoring protocols as required, for example, in an off-normal accident situation. Plans are being developed to implement the use of this system at most RF Naval sites handling spent nuclear fuel.

MOSKOWITZ,P.D.; POMERVILLE,J.; GAVRILOV,S.; KISSELEV,V.; DANIYLAN,V.; BELIKOV,A.; EGORKIN,A.; SOKOLOVSKI,Y.; ENDREGARD,M.; KROSSHAVN,M.; SUNDLING,C.V.; YOKSTAD,H.

2001-02-25T23:59:59.000Z

151

AUTOMATED RADIOLOGICAL MONITORING AT A RUSSIAN MINISTRY OF DEFENSE NAVAL SITE.  

SciTech Connect

The Arctic Military Environmental Cooperation (AMEC) Program is a cooperative effort between the military establishments of the Kingdom of Norway, the Russian Federation, and the US. This paper discusses joint activities conducted over the past year among Norwegian, Russian, and US technical experts on a project to develop, demonstrate and implement automated radiological monitoring at Russian Navy facilities engaged in the dismantlement of nuclear-powered strategic ballistic missile launching submarines. Radiological monitoring is needed at these facilities to help protect workers engaged in the dismantlement program and the public living within the footprint of routine and accidental radiation exposure areas. By providing remote stand-alone monitoring, the Russian Navy will achieve added protection due to the defense-in-depth strategy afforded by local (at the site), regional (Kola) and national-level (Moscow) oversight. The system being implemented at the Polyaminsky Russian Naval Shipyard was developed from a working model tested at the Russian Institute for Nuclear Safety, Moscow, Russia. It includes Russian manufactured terrestrial and underwater gamma detectors, smart controllers for graded sampling, radio-modems for offsite transmission of the data, and a data fusion/display system: The data fusion/display system is derived from the Norwegian Picasso AMEC Environmental Monitoring software package. This computer package allows monitoring personnel to review the real-time and historical status of monitoring at specific sites and objects and to establish new monitoring protocols as required, for example, in an off-normal accident situation. Plans are being developed to implement the use of this system at most RF Naval sites handling spent nuclear fuel.

MOSKOWITZ,P.D.; POMERVILLE,J.; GAVRILOV,S.; KISSELEV,V.; DANIYLAN,V.; BELIKOV,A.; EGORKIN,A.; SOKOLOVSKI,Y.; ENDREGARD,M.; KROSSHAVN,M.; SUNDLING,C.V.; YOKSTAD,H.

2001-02-25T23:59:59.000Z

152

Radiologic characterization of the Mexican Hat, Utah, uranium mill tailings remedial action site: Addendum D1  

Science Conference Proceedings (OSTI)

This radiologic characterization of the inactive uranium millsite at Mexican Hat, Utah, was conducted by Bendix Field Engineering Corporation for the US Department of Energy (DOE), Grand Junctions 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

153

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

154

Results of the radiological survey at the former Herring-Hall-Marvin Safe Company (3rd floor), 1550 Grand Boulevard, Hamilton, Ohio (HO001)  

SciTech Connect

At the request of the US Department of Energy (DOE), a group from the Oak Ridge National Laboratory conducted a radiological survey at the former Herring-Hall-Marvin Safe Company (third floor), 1550 Grand Boulevard, Hamilton, Ohio (HO001) in August 1993. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, derived from the former Manhattan Engineer District project. The survey included gamma scans; direct and transferable measurements of alpha, beta, and gamma radiation levels; and debris sampling for radionuclide analyses. Results of the survey demonstrated {sup 238}U surface contamination in excess of the DOE criteria for surface contamination. The third floor was generally contaminated over 25 percent of its area with isolated spots in the remaining area. Although three isolated spots of contamination were found in areas other than on the third floor (in the same southeastern comer of the facility), they were remediated by sampling. Based on the survey results, this site is recommended for remediation.

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

1994-03-01T23:59:59.000Z

155

Final Status Survey and Site Release Experience Report  

Science Conference Proceedings (OSTI)

Several U.S. nuclear power plants entered decommissioning in the 1990's. The ultimate goal of the decommissioning of a reactor site (unless otherwise delayed due to a decision to place the plant in a SAFSTOR mode to be decommissioned at a later date) is to release the site for future use. This report provides detailed information concerning the preparation of release criteria a utility must meet prior to the release of the site, and the experiences obtained in performing the Final Status Surveys which de...

2008-03-31T23:59:59.000Z

156

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  

Science Conference Proceedings (OSTI)

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

157

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

Science Conference Proceedings (OSTI)

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

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

1983-04-01T23:59:59.000Z

158

Radiological survey of the inactive uranium-mill tailings at Ambrosia Lake, New Mexico  

Science Conference Proceedings (OSTI)

The inactive uranium-mill tailings pile at Ambrosia Lake, New Mexico, contains approximately 1520 Ci of /sup 226/Ra in 2.4 million metric tons of tailings covering an area of 43 hectares. All of the former mill buildings were intact and, at the time of this survey, several were in use. The tailings have not been stabilized, but the crusty surface is reported to be resistant to wind erosion. The average gamma-ray exposure rate 1 m above the tailings is 720 ..mu..R/h while the average rate in the former mill area is 150 ..mu..R/h. The adjacent area, between the mill site, ponds, and tailings pile, has an average exposure rate of 230 ..mu..R/h. Gamma radiation measurements outside these areas, as well as the results of analyses of surface or near-surface sediment and soil samples, show fairly wide dispersion of contamination around the site. The subsurface distribution of /sup 226/Ra in 18 holes drilled at the site, calculated from gamma-ray monitoring data, is presented graphically and compared with measured concentrations in two holes.

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

1980-06-01T23:59:59.000Z

159

Trojan Nuclear Plant Decommissioning: Final Survey for the Independent Spent Fuel Storage Installation Site  

Science Conference Proceedings (OSTI)

This report describes the final radiological survey for the area where Portland General Electric (PGE) will construct the Independent Spent Fuel Storage Installation (ISFSI) at Trojan nuclear power plant. The survey fulfills the requirements for release of this area from Trojan's 10 CFR 50 license before radiation levels increase with spent fuel storage in the ISFSI.

1998-05-13T23:59:59.000Z

160

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;

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
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161

An aerial radiological survey of the Oyster Creek Nuclear Power Plant and surrounding area, Forked River, New Jersey. Date of survey: September 18--25, 1992  

SciTech Connect

An aerial radiological survey was conducted over the Oyster Creek Nuclear Power Plant in Forked River, New Jersey, during the period September 18 through September 24, 1992. The survey was conducted at an altitude of 150 feet (46 meters) over a 26-square-mile (67-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Oyster Creek Nuclear Power plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 4 and 10 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey of the power plant was conducted in August 1969 during its initial startup phase. Exposure rates and radioactive isotopes revealed in both surveys were consistent and within normal terrestrial background levels.

Hopkins, H.A.; McCall, K.A.

1994-05-01T23:59:59.000Z

162

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

SciTech Connect

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

Millsap, William J.; Brush, Daniel J.

2013-11-13T23:59:59.000Z

163

Ornithological Survey of the Proposed Geothermal Well Site No. 2  

DOE Green Energy (OSTI)

The U.S. Fish and Wildlife Service (USFWS 1983) and the State of Hawaii (DLNR 1986) have listed as endangered six forest bird species for the Island of Hawaii. Two of these birds, the O'u (Psittirostra psittacea) and the Hawaiian hawk (Buteo solitarius) may be present within the Geothermal resource sub-zone (Scott et al. 1986). Thus, their presence could impact future development within the resource area. This report presents the results of a bird survey conducted August 11 and 12, 1990 in the sub-zone in and around the proposed well site and pad for True/Mid Pacific Geothermal Well No.2.

Jeffrey, Jack

1990-08-16T23:59:59.000Z

164

Acquisition Information Management system telecommunication site survey results  

SciTech Connect

The Army acquisition community currently uses a dedicated, point-to-point secure computer network for the Army Material Plan Modernization (AMPMOD). It must transition to the DOD supplied Defense Secure Network 1 (DSNET1). This is one of the first networks of this size to begin the transition. The type and amount of computing resources available at individual sites may or may not meet the new network requirements. This task surveys these existing telecommunications resources available in the Army acquisition community. It documents existing communication equipment, computer hardware, associated software, and recommends appropriate changes.

Hake, K.A. [Oak Ridge National Lab., TN (United States); Key, B.G. [COR, Inc., Oak Ridge, TN (United States)

1993-09-01T23:59:59.000Z

165

Bioremediation of Petroleum and Radiological Contaminated Soils at the Savannah River Site: Laboratory to Field Scale Applications  

DOE Green Energy (OSTI)

In the process of Savannah River Site (SRS) operations limited amounts of waste are generated containing petroleum, and radiological contaminated soils. Currently, this combination of radiological and petroleum contaminated waste does not have an immediate disposal route and is being stored in low activity vaults. SRS developed and implemented a successful plan for clean up of the petroleum portion of the soils in situ using simple, inexpensive, bioreactor technology. Treatment in a bioreactor removes the petroleum contamination from the soil without spreading radiological contamination to the environment. This bioreactor uses the bioventing process and bioaugmentation or the addition of the select hydrocarbon degrading bacteria. Oxygen is usually the initial rate-limiting factor in the biodegradation of petroleum hydrocarbons. Using the bioventing process allowed control of the supply of nutrients and moisture based on petroleum contamination concentrations and soil type. The results of this work have proven to be a safe and cost-effective means of cleaning up low level radiological and petroleum-contaminated soil. Many of the other elements of the bioreactor design were developed or enhanced during the demonstration of a ''biopile'' to treat the soils beneath a Polish oil refinery's waste disposal lagoons. Aerobic microorganisms were isolated from the aged refinery's acidic sludge contaminated with polycyclic aromatic hydrocarbons (PAHs). Twelve hydrocarbon-degrading bacteria were isolated from the sludge. The predominant PAH degraders were tentatively identified as Achromobacter, Pseudomonas Burkholderia, and Sphingomonas spp. Several Ralstonia spp were also isolated that produce biosurfactants. Biosurfactants can enhance bioremediation by increasing the bioavailability of hydrophobic contaminants including hydrocarbons. The results indicated that the diversity of acid-tolerant PAH-degrading microorganisms in acidic oil wastes may be much greater than previously demonstrated and they have numerous applications to environmental restoration. Twelve of the isolates were subsequently added to the bioreactor to enhance bioremediation. In this study we showed that a bioreactor could be bioaugmented with select bacteria to enhance bioremediation of petroleum-contaminated soils under radiological conditions.

BRIGMON, ROBINL.

2004-06-07T23:59:59.000Z

166

An aerial radiological survey of the Babcock and Wilcox Nuclear Facilities and surrounding area, Lynchburg, Virginia. Date of survey: July 1988  

SciTech Connect

An aerial radiological survey was conducted from July 18 through July 25, 1988, over a 41-square-kilometer (16-square-mile) area surrounding the Babcock and Wilcox nuclear facilities located near Lynchburg, Virginia. The survey was conducted at a nominal altitude of 61 meters (200 feet) with line spacings of 91 meters (300 feet). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter above ground level (AGL) was prepared and overlaid on an aerial photograph. The terrestrial exposure rates varied from 8 to 12 microroentgens per hour ({mu}R/h). A search of the data for man-made radiation sources revealed the presence of three areas of high count rates in the survey area. Spectra accumulated over the main plant showed the presence of cobalt-60 ({sup 60}Co) and cesium-137 ({sup 137}Cs). A second area near the main plant indicated the presence of uranium-235 ({sup 235}U). Protactinium-234m ({sup 234m}Pa) and {sup 60}Co were detected over a building to the east of the main plant. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries in support of the aerial data.

Guss, P.P.

1993-04-01T23:59:59.000Z

167

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

168

Radiological Habits Survey: Hunterston, 2007 This page has been intentionally left blank  

E-Print Network (OSTI)

..................................................................................................23 4.7 Internal exposure..... .................................................................15 Figure 2 The Hunterston terrestrial (outer ring) and direct radiation (inner ring) survey areas AQUATIC RADIATION PATHWAYS ...........................................................................21 4

169

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

SciTech Connect

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

Ron Warren

2006-12-01T23:59:59.000Z

170

Radiological Dose Assessment 8 2003 SITE ENVIRONMENTAL REPORT8-1  

E-Print Network (OSTI)

proportional to the absorbed dose of radiation. The environmental TLDs used at BNL are composed of calcium fluoride and lithium fluoride. The TLDs' accuracy is verified by using TLDs exposed to known sources to Aquatic and Terrestrial Biota, provides the guidelines for screening methods to estimate radiological

Homes, Christopher C.

171

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_

172

Radiological Control Manual  

Science Conference Proceedings (OSTI)

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

Not Available

1993-04-01T23:59:59.000Z

173

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

Science Conference Proceedings (OSTI)

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

174

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

175

An aerial radiological survey of the project Rio Blanco and surrounding area  

SciTech Connect

A team from the Remote Sensing Laboratory in Las Vegas, Nevada, conducted an aerial radiation survey of the area surrounding ground zero of Project Rio Blanco in the northwestern section of Colorado in June 1993. The object of the survey was to determine if there were man-made radioisotopes on or near the surface resulting from a nuclear explosion in 1972. No indications of surface contamination were found. A search for the cesium-137 radioisotope was negative. The Minimum Detectable Activity for cesium-137 is presented for several detection probabilities. The natural terrestrial exposure rates in units of Roentgens per hour were mapped and are presented in the form of a contour map over-laid on an aerial photograph. A second team made independent ground-based measurements in four places within the survey area. The average agreement of the ground-based with aerial measurements was six percent.

Singman, L.V.

1994-11-01T23:59:59.000Z

176

Confirmatory radiological survey of portions of the former A. H. Robins Research Center, Richmond, Virginia. Final report  

SciTech Connect

The former A.H. Robins Research Center, in Richmond, VA, was devoted primarily to the research and development of pharmaceuticals. The use of radionuclides at the A.H. Robins Research Center was first begun in the early 1960s and the facility is now operating under Nuclear Regulatory Commission (NRC) License No. 45-09042-01. A. H. Robins` Drug Metabolism Department used radioactive material (H-3, C-14, Na-22, P-32, S-35, CI-36, Ca-45, Cr-51, Ni-63, Rb-86, I-125, I-129, I-131, and Cs-137) in laboratory tracer studies on animals, for calibration of instrumentation, and for research analyses. The radionuclides were used in various,rooms throughout the facility. Following its acquisition by American Home Products in 1990, radionuclide activities were discontinued at this facility. The process for the termination of the material license for A.H. Robins (AHR) was initiated by the Corporate Radiation Health Safety Officer of Wyeth-Ayerst Research (WAR), another wholly owned subsidiary of American Home Products (AHP). In June 1990, WAR developed and submitted a decommissioning plan to the NRC. A radiological survey of the areas in which radionuclides were known to have been handled was performed to determine the extent of the contamination. During the cleanup and survey of the facility, the licensee identified H-3 and C-14 as the major

Adams, W.C.

1992-05-01T23:59:59.000Z

177

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

178

An aerial radiological survey of the Davis-Monthan Air Force Base and surrounding area, Tucson, Arizona  

SciTech Connect

An aerial radiological survey, which was conducted from March 1 to 13, 1995, covered a 51-square-mile (132-square-kilometer) area centered on the Davis-Monthan Air Force Base (DMAFB) in Tucson, Arizona. The results of the survey are reported as contours of bismuth-214 ({sup 214}Bi) soil concentrations, which are characteristic of natural uranium and its progeny, and as contours of the total terrestrial exposure rates extrapolated to one meter above ground level. All data were scaled and overlaid on an aerial photograph of the DMAFB area. The terrestrial exposure rates varied from 9 to 20 microroentgens per hour at one meter above the ground. Elevated levels of terrestrial radiation due to increased concentrations of {sup 214}Bi (natural uranium) were observed over the Southern Pacific railroad yard and along portions of the railroad track bed areas residing both within and outside the base boundaries. No man-made, gamma ray-emitting radioactive material was observed by the aerial survey. High-purity germanium spectrometer and pressurized ionization chamber measurements at eight locations within the base boundaries were used to verify the integrity of the aerial results. The results of the aerial and ground-based measurements were found to be in agreement. However, the ground-based measurements were able to detect minute quantities of cesium-137 ({sup 137}Cs) at six of the eight locations examined. The presence of {sup 137}Cs is a remnant of fallout from foreign and domestic atmospheric nuclear weapons testing that occurred in the 1950s and early 1960s. Cesium-137 concentrations varied from 0.1 to 0.3 picocuries per gram, which is below the minimum detectable activity of the aerial system.

NONE

1995-09-01T23:59:59.000Z

179

Radiological Habits Survey: Torness, 2006 This page has been intentionally left blank  

E-Print Network (OSTI)

cover 25 5.3 Novel radiation pathways 25 5.4 Internal exposure 25 6. DIRECT RADIATION 27 6.1 Direct.5 Wildfowling 19 4.6 The use of seaweed as a fertiliser 19 4.7 Internal exposure 19 4.8 External exposure 22 4 ratios for use in dose assessments 13 4. AQUATIC RADIATION PATHWAYS 14 4.1 Aquatic survey area 14 4

180

Radiological survey of the inactive uranium-mill tailings at Ray Point, Texas  

SciTech Connect

The mill site and tailings pile near Ray Point, Texas, cover an area of approximately 140 hectares located 1.6 km west of Ray Point. The dry portion of the tailings pile is stabilized, and the whole pile is surrounded by a dike. It contains approximately 445,000 metric tons of material with an estimated average /sup 226/Ra concentration of 518 pCi/g. The average gamma-ray exposure rate 1 m above the pile is 300 ..mu..R/hr while the corresponding average for the mill site, including the former ore storage area, is 87 ..mu..R/hr. Soil and sediment sample analyses, as well as gamma-ray exposure rate measurements, show some spread of contamination off the site; however, it appears that control measures at this site have been effective in limiting the spread of tailings. Access to the area is limited by chain-link and barbed-wire fences, and continued surveillance of the area is maintained. The mill buildings have been maintained for possible future use.

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

1980-11-01T23:59:59.000Z

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


181

Power Quality Site Surveys: Fact, Fiction, and Fallacies  

Science Conference Proceedings (OSTI)

... Because normal use of electricity gener- ates disturbances ... in these surveys led to the generation of some ... development of a solid-state circuit which ...

2013-05-17T23:59:59.000Z

182

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

SciTech Connect

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

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

1980-03-01T23:59:59.000Z

183

Regulatory Supervision of Radiological Protection in the Russian Federation as Applied to Facility Decommissioning and Site Remediation  

Science Conference Proceedings (OSTI)

The Russian Federation is carrying out major work to manage the legacy of exploitation of nuclear power and use of radioactive materials. This paper describes work on-going to provide enhanced regulatory supervision of these activities as regards radiological protection. The scope includes worker and public protection in routine operation; emergency preparedness and response; radioactive waste management, including treatment, interim storage and transport as well as final disposal; and long term site restoration. Examples examined include waste from facilities in NW Russia, including remediation of previous shore technical bases (STBs) for submarines, spent fuel and radioactive waste management from ice-breakers, and decommissioning of Radio-Thermal-Generators (RTGs) used in navigational devices. Consideration is given to the identification of regulatory responsibilities among different regulators; development of necessary regulatory instruments; and development of regulatory procedures for safety case reviews and compliance monitoring and international cooperation between different regulators. (authors)

Sneve, M.K. [Norwegian Radiation Protection Authority (Norway); Shandala, N.K. [Institute of Biophysics, Moscow (Russian Federation)

2007-07-01T23:59:59.000Z

184

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

185

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

186

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.

187

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.

188

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

Science Conference Proceedings (OSTI)

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

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

2012-12-27T23:59:59.000Z

189

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

190

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

191

Concerns Regarding Lead Contamination and Radiological Controls...  

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

Home Concerns Regarding Lead Contamination and Radiological Controls at the Nevada Test Site, INS-O-06-02 Concerns Regarding Lead Contamination and Radiological Controls at...

192

Radiological status of the ground water beneath the Hanford Site, January-December 1981  

Science Conference Proceedings (OSTI)

During 1981, 299 monitoring wells were sampled at various times for radionuclide chemical contaminants. This report is one of a series prepared annually to document and evaluate the status of ground water at the Hanford Site. Two substances, tritium and nonradioactive nitrate, are easily transported in ground water; therefore, these substances are used as primary tracers to monitor the movement of contaminated ground water. Data collected during 1981 describe the movement of tritium and the nonradioactive nitrate plumes as well as their response to the influences of ground-water flow, ionic dispersion, and radioactive decay. The gross beta (/sup 106/Ru) levels have become so low that it will no longer be considered a major radionuclide contaminant. The tritium plume continues to show increasing concentrations near the Columbia River. While it is mapped as having reached the Columbia River, its contribution to the river has not been distinguished from other sources at this time. This plume shows much the same configuration as in 1977, 1978, 1979, and 1980. The size of the nitrate plume appears stable. Concentrations of nitrate in the vicinity of the 100-H Area continue to be high as a result of past leaks from the evaporation facility. The overall quality of the ground water at the Hanford Site is generally comparable to that of other ground waters in eastern Washington. Any exceptions to this statement will be noted in this report.

Eddy, P.A.; Cline, C.S.; Prater, L.S.

1982-04-01T23:59:59.000Z

193

Long-Term Overvoltage on Medical Radiology and Treatment Equipment Detected by First Power-Line Monitoring Survey  

Science Conference Proceedings (OSTI)

This case study describes an equipment-to-electromagnetic environment incompatibility that occurred in a cancer research and treatment center radiology laboratory that is part of a large teaching and research hospital.

2003-12-31T23:59:59.000Z

194

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...

195

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory (ORNL) was conducted intermittently from February 1992 through May 1992. The investigation was performed by the Measurement Applications and Development Group of the Health and Safety Research Division of ORNL at the request of the US Department of Energy`s Oak Ridge Operations Office and the ORNL Environmental Restoration Program. Results of this investigation indicate that the source of radioactive contamination at the point of the contamination incident is from one of the underground abandoned lines. The contamination in soil is likely the result of residual contamination from years of waste transport and maintenance operations (e.g., replacement of degraded joints, upgrading or replacement of entire pipelines, and associated landscaping activities). However, because (1) there is currently an active LLW line positioned in the same subsurface trench with the abandoned lines and (2) the physical condition of the abandoned lines may be brittle, this inquiry could not determine which abandoned line was responsible for the subsurface contamination. Soil sampling at the location of the contamination incident and along the pipeline route was performed in a manner so as not to damage the active LLW line and abandoned lines. Recommendations for corrective actions are included.

Williams, J.K.; Foley, R.D.; Tiner, P.F.; Hatmaker, T.L.; Uziel, M.S.; Swaja, R.E.

1993-05-01T23:59:59.000Z

196

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado. Attachment 5, Supplemental radiological data: Final report  

Science Conference Proceedings (OSTI)

Diffusion coefficients for radon gas in earthen materials are required to design suitable radon-barrier covers for uranium tailings impoundments and other materials that emit radon gas. Many early measurements of radon diffusion coefficients relied on the differences in steady-state radon fluxes measured from radon source before and after installation of a cover layer of the material being tested. More recent measurements have utilized the small-sample transient (SST) technique for greater control on moistures and densities of the test soils, greater measurement precision, and reduced testing time and costs. Several of the project sites for the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Program contain radiologically contaminated subsurface material composed predominantly of cobbles, gravels andsands. Since remedial action designs require radon diffusion coefficients for the source materials as well as the cover materials, these cobbly and gravelly materials also must be tested. This report contains the following information: a description of the test materials used and the methods developed to conduct the SST radon diffusion measurements on cobbly soils; the protocol for conducting radon diffusion tests oncobbly soils; the results of measurements on the test samples; and modifications to the FITS computer code for analyzing the time-dependent radon diffusion data.

Not Available

1992-10-01T23:59:59.000Z

197

"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

198

Radiological audit of remedial action activities at the processing sites Mexican Hat, Utah and Monument Valley, Arizona. Audit date: May 3--7, 1993, Final report  

SciTech Connect

The Uranium Mill Tailings Remedial Action (UMTRA) Project`s Technical Assistance Contractor (TAC) performed a radiological audit of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing sites in Mexican Hat, Utah, and Monument Valley, Arizona. This audit was conducted May 3--7, 1993, by Bill James and Gerry Simiele of the TAC. Three site-specific findings and four observations were identified during the audit and are presented in this report. The overall conclusion from the audit is that the majority of the radiological aspects of the Mexican Hat, Utah, and Monument Valley, Arizona, remedial action programs are performed adequately. However, the findings identify that there is some inconsistency in following procedures and meeting requirements for contamination control, and a lack of communication between the RAC and the DOE on variances from the published remedial action plan (RAP).

NONE

1993-05-01T23:59:59.000Z

199

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

200

An aerial radiological survey of Technical Areas 2, 21, and 53 and surroundings, Los Alamos National Laboratory, Los Alamos, New Mexico  

SciTech Connect

An aerial radiological survey of the entire Los Alamos National Laboratory was flown in September 1982. The data from a part of the survey, Technical Areas 2, 21, and 53, are presented here along with pertinent data from an October 1975 survey of limited areas of Los Alamos. The data from Technical Area 15, another part of the survey, will be published in another report. Contour maps of the gamma survey data show some Cs-137 activity in Los Alamos Canyon as well as in DP Canyon beside TA-21. Some Be-7, Sb-124, and Co-58 apparently exist in the canyon immediately below the Los Alamos Meson Physics Facility (LAMPF) ponds. Estimates on the Cs-137 inventory in the canyons range from 210 mCi to 1270 mCi. An exposure rate contour map at 1 meter above ground level (AGL) was constructed from the gamma data and overlaid on an aerial photograph and map of the area. The terrestrial exposure rates ranged from 6{mu}R/h to about 18{mu}R/h. 25 figs., 3 tabs.

Fritzsche, A.E.

1990-09-01T23:59:59.000Z

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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Radiological surveillance of Remedial Action activities at the processing site, Ambrosia Lake, New Mexico, April 12--16, 1993. Final report  

SciTech Connect

The Uranium Mill Tailings Remedial Action (UMTRA) Project`s Technical Assistance Contractor (TAC) performed a radiological surveillance of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site in Ambrosia Lake, New Mexico. The requirements and attributes examined during the audit were developed from reviewing working-level procedures developed by the RAC. Objective evidence, comments, and observations were verified based on investigating procedures, documentation, records located at the site, personal interviews, and tours of the site. No findings were identified during this audit. Ten site-specific observations, three good practice observations, and five programmatic observations are presented in this report. The overall conclusion from the surveillance is that the radiological aspects of the Ambrosia Lake, New Mexico, remedial action program are performed adequately. The results of the good practice observations indicate that the site health physics (HP) staff is taking the initiative to address and resolve potential issues, and implement suggestions useful to the UMTRA Project. However, potential exists for improving designated storage areas for general items, and the RAC Project Office should consider resolving site-specific and procedural inconsistencies.

NONE

1993-04-01T23:59:59.000Z

202

Supplemental Radiological Survey Plan for the Lease of the Rooms Associated with C107 of Building K-1006 at the East Tennessee Technology Park, Oak Ridge, Tennessee  

SciTech Connect

In 1998, a portion of Bldg. K-1006 was leased to the Community Reuse Organization of East Tennessee (CROET) as part of the reindustrialization efforts at the East Tennessee Technology Park (ETTP). The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include rooms C107, C107-A, C107-B, C107-C, and C107-D. The lease of these rooms is now desired. These rooms comprise the area to be surveyed. The building was constructed as a laboratory facility to support the gaseous diffusion uranium enrichment process. It also contains offices and administrative spaces for laboratory personnel. After the gaseous diffusion process was shut down in the mid-1980s, the building was used to provide research and development support to ETTP environmental, safety, and health programs; the Toxic Substances Control Act Incinerator; the Central Neutralization Facility; and other multi-site waste treatment activities. It also served as the chemistry laboratory for the Environmental Technology Technical Services Organization. The activities currently conducted in Bldg. K-1006 utilize a variety of analytical techniques. Some of the major techniques being employed are X-ray analysis, electron microanalysis, and spectrochemical analysis. In 1998, a portion of Bldg. K-1006 was leased to CROET as part of the reindustrialization efforts at ETTP. The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include Rooms C107, C107-A, C107-B, C107-C, and C107-D. Some demolition of furniture and decontamination activities has taken place for Rooms C 107 and C 107-B since the last radiological survey of those rooms. In March 2009, a final remedial action (RA) was performed for the Bldg. K-1006 north basement sump. The Bldg. K-1006 north basement sump is a nominal 30-in.-diameter, 36-in.-deep concrete structure in the north corner of room C107B. The building receives groundwater in-leakage that is periodically pumped to the sewer system via this float-controlled pump. Solids in the bottom of the sump consisted of an estimated 1-ft{sup 3} coarse-grained material that varied in thickness from 0 to 4 in. with no suspended fraction. The RA consisted of removing the water in the sump and then removing and sampling the solids. The solids were mixed with grout after removal and allowed to set. The solids were then disposed off-site at an approved disposal facility. The building sump will remain until the K-1006 building is demolished. The actions for the K- 1006 sump are described in the revised Phased Construction Completion Report for Exposure Unit (EU) Z2-33, which received regulatory approval in December 2009.

Blevins M.F.

2010-09-01T23:59:59.000Z

203

Magnetic field survey at PG&E photovoltaic sites  

DOE Green Energy (OSTI)

Public awareness has aroused concerns over the possible effects of magnetic fields on human health. While research continues to determine if magnetic fields do, in fact, affect human health, concerned individuals are requesting data on magnetic field sources in their environments to base personal decisions about limiting their exposure to these sources. Timely acceptance and implementation of photovoltaics (PV), particularly for distributed applications such as PV rooftops, windows, and vehicles, may be hampered by the lack of PV magnetic field data. To address this situation, magnetic flux density was measured around equipment at two PVUSA (Photovoltaics for Utility Scale Applications) project sites in Kerman and Davis, California. This report documents the data and compares the PV magnetic fields with published data on more prevalent magnetic field sources. Although not comprehensive, electric and magnetic field (EMF) data taken at PVUSA indicate that 60-Hz magnetic fields (the EMF type of greatest public concern) are significantly less for PV arrays than for household applications. Therefore, given the present EMF research knowledge, PV array EMF may not merit considerable concern. The PV system components exhibiting significant AC magnetic fields are the transformers and power conditioning units (PCUs). However, the AC magnetic fields associated with these components are localized and are not detected at PV system perimeters. Concern about transformer and PCU EMF would apply to several generation and storage technologies.

Chang, G.J.; Jennings, C.

1994-08-01T23:59:59.000Z

204

An inventory survey at the site of the proposed Kilauea Middle East Rift Zone (KMERZ), Well Site No. 2  

DOE Green Energy (OSTI)

At the request of True Mid Pacific Geothermal, Archaeological Consultants of Hawaii, Inc. has conducted an inventory survey at the site of the proposed Kilauea Middle East Rift Zone (KMERZ), Well Site No.2, TMK: 1-2-10:3. The Principal Investigator was Joseph Kennedy M.A., assisted by Jacob Kaio, Field Supervisor and field crew Mark Borrello B.A., Michael O'Shaughnessy B.A., and Randy Adric. This report supercedes all previous reports submitted to the Historic Presentation Section of the Department of Land and Natural Resources. In addition to 100% surface coverage of the 400 x 400 foot well pad itself, 100% surface coverage of a substantial buffer zone was also completed. This buffer zone was established by the Department of Land and Natural Resources, Historic Preservation personnel and extends 1000 feet east and west of the well site and 500 feet north and south of the well site.

Kennedy, Joseph

1991-03-01T23:59:59.000Z

205

Fort St. Vrain Decommissioning: Final Site Radiation Survey: Summary Report and Lessons Learned  

Science Conference Proceedings (OSTI)

This report describes the final step in the decommissioning process at Public Service Company of Colorado's (PSCo) Fort St. Vrain nuclear power plant. The final site radiation survey documents that all nuclear facility surfaces meet the established release limits for unrestricted use. The survey formed the legal basis for the termination of the Fort St. Vrain nuclear license, which occurred in August 1997. The lessons learned in this process will be valuable to other utilities with permanently shutdown p...

1998-02-13T23:59:59.000Z

206

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

207

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

208

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

209

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

210

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

211

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

212

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

213

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

214

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.

215

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

216

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

Science Conference Proceedings (OSTI)

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

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

1990-03-01T23:59:59.000Z

217

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

218

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

219

Health and Safety Research Division RESULTS OF THE RADIOLOGICAL...  

Office of Legacy Management (LM)

Contaninated material was discovered in the area during an EG&G aerial radiological survey,l and confirmed by a ground-level radiological survey by the Nuclear Regulatory...

220

Health and Safety Research Divlsion RESULTS OF THE RADIOLOGICAL...  

Office of Legacy Management (LM)

Contaminated material was discovered in the area during an. EG&G aerial radiological survey,l and confirmed by a ground-level radiological survey by the Nuclear Regulatory...

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

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

222

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

Science Conference Proceedings (OSTI)

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

P.C. Weaver

2009-02-17T23:59:59.000Z

223

A Survey of Department of Energy-Sponsored Geophysical Research for Shallow Waste Site Characterization  

Science Conference Proceedings (OSTI)

Subsurface contamination plagues many U.S. Department of Energy (DOE) sites and threatens groundwater supplies. This survey discusses research sponsored by the DOE Environmental Management Science Program (EMSP) for geophysical characterization of the vadose zone at the Idaho National Engineering and Environmental Laboratory (INEEL) and other contaminated sites. Various types of geophysical imaging techniques are used to characterize the shallow subsurface—electromagnetic, ground-penetrating radar, electrical, seismic, and nuclear magnetic resonance. Three common themes appear in the research surveyed in this article: (1) the development of high-resolution imaging capabilities to capture important details of the heterogeneous nature of subsurface properties and processes, (2) the coupling of non-intrusive survey geophysical measurements (e.g., electrical surveys) with detailed quantitative precise point-sensor measurements (e.g., lysimeters and vapor-port systems) or borehole (e.g., nuclear magnetic resonance, neutron-based moisture, and geochemical tools) measurements to extend high-precision knowledge away from the borehole, and finally (3) the application of multiple geophysical methods to constrain the uncertainty in determining critical subsurface physical properties. Laboratory, field, theoretical, and computational studies are necessary to develop our understanding of the manner in which contaminants travel through the vadose zone. Applications of geophysical methods to various contaminated areas at the INEEL are given.

Donna Post Guillen

2004-01-01T23:59:59.000Z

224

DOE/OR/20722-34 Formerly Utilized Sites Remedial Action Program...  

Office of Legacy Management (LM)

4 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-AC05-810R20722 RADIOLOGICAL SURVEY REPORT FOR THE RESIDENTIAL PROPERTY AT 10 GROVE AVENUE Rochelle Park,...

225

DOE/OR/20722-41 Formerly Utilized Sites Remedial Action Program...  

Office of Legacy Management (LM)

1 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-AC05-810R20722 RADIOLOGICAL SURVEY REPORT FOR THE RESIDENTIAL PROPERTY AT 38 GROVE AVENUE Rochelle Park,...

226

DOE/OR/20722-40 Formerly Utilized Sites Remedial Action Program...  

Office of Legacy Management (LM)

40 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-AC05-810R20722 RADIOLOGICAL SURVEY REPORT FOR THE RESIDENTIAL PROPERTY AT 34 GROVE AVENUE Rochelle Park,...

227

DOE/OR/20722-42 Formerly Utilized Sites Remedial Action Program...  

Office of Legacy Management (LM)

2 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-AC05-810R20722 RADIOLOGICAL SURVEY REPORT FOR THE RESIDENTIAL PROPERTY AT 42 GROVE AVENUE Rochelle Park,...

228

DOE/OR/20722-37 Formerly Utilized Sites Remedial Action Program...  

Office of Legacy Management (LM)

7 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-AC05-810R20722 RADIOLOGICAL SURVEY REPORT FOR THE RESIDENTIAL PROPERTY AT 22 GROVE AVENUE Rochelle Park,...

229

DOE/OR/20722-39 Formerly Utilized Sites Remedial Action Program...  

Office of Legacy Management (LM)

39 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-AC05-810R20722 RADIOLOGICAL SURVEY REPORT FOR THE RESIDENTIAL PROPERTY AT 30 GROVE AVENUE Rochelle Park,...

230

DOE/OR/20722-38 Formerly Utilized Sites Remedial Action Program...  

Office of Legacy Management (LM)

8 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-AC05-810R20722 RADIOLOGICAL SURVEY REPORT FOR THE RESIDENTIAL PROPERTY AT 26 GROVE AVENUE Rochelle Park,...

231

Release criteria and pathway analysis for radiological remediation  

Science Conference Proceedings (OSTI)

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

232

OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL  

Office of Legacy Management (LM)

W. D. Cottrell - FUSRAP Project Director M. G. Yalcintas - Field Survey Supervisor Work performed as part of the RADIOLOGICAL SURVEY ACTIVITIES PROGRAM Prepared by the OAK...

233

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

234

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

235

Reconnaissance survey of site 7 of the proposed Three Rivers Regional Landfill and Technology Center, Savannah River Site, Aiken County, South Carolina  

SciTech Connect

This report documents the archaeological investigation of Site 7 of the proposed Three Rivers Regional Landfill and Technology Center in Aiken County on the United States Department of Energy`s Savannah River Site (SRS) in Aiken and Barnwell Counties, South Carolina. Pedestrian and subsurface survey techniques were used to investigate the 1,403-acre project area. Survey resulted in the discovery of 23 previously unrecorded sites and 11 occurrences; six previously recorded sites were also investigated. These sites consist of six prehistoric sites, nine historic sites, and 14 sites with both prehistoric and historic components. Sites locations and project area boundaries are provided on a facsimile of a USGS 7.5 topographic map. The prehistoric components consist of very small, low-density lithic and ceramic scatters; most contain less than 10 artifacts. Six of the prehistoric components are of unknown cultural affiliation, the remaining prehistoric sites were occupied predominately in the Woodland period. The historic sites are dominated by postbellum/modem home places of tenant and yeoman farmers but four historic sites were locations of antebellum house sites (38AK136, 38AK613, 38AK660, and 38AK674). The historic sites also include an African-American school (38AK677).

Cabak, M.A.; Beck, M.L.; Gillam, C.; Sassaman, K.E.

1996-02-01T23:59:59.000Z

236

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

237

Radiological-dose assessments of atolls in the northern Marshall Islands  

Science Conference Proceedings (OSTI)

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

Robison, W.L.

1983-04-01T23:59:59.000Z

238

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

239

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

SciTech Connect

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

P.C. Weaver

2008-10-17T23:59:59.000Z

240

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

SciTech Connect

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

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

2012-02-28T23:59:59.000Z

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

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

242

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

243

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

244

Nuclear and Radiological Material Security | National Nuclear...  

National Nuclear Security Administration (NNSA)

to intensive site security efforts, NNSA is also working to build international standards and criteria for nuclear and radiological security. This includes NNSA's work to...

245

RADIOLOGICAL ASSESSMENT OF BALLOD AND ASSOCIATES PROPERTY  

Office of Legacy Management (LM)

Cotton, Robert Gosslee, Jonathan Sowell, Clayton Weaver FINAL REPORT July 30, 1981 Work performed by Radiological Site Assessment Program Manpower Education, Research, and...

246

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

247

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

248

Radiological Habits Survey, Torness 2001  

E-Print Network (OSTI)

............................................................................ 30 4.5 Internal exposure................................................................................................................ 39 5.4 Internal Exposure ................................................................................ 12 4 AQUATIC RADIATION PATHWAYS

249

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

250

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

251

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

252

Radiological Worker Training - Radiological Contamination Control...  

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

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....

253

Radiological Worker Training - Radiological Control Training...  

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

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...

254

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

Science Conference Proceedings (OSTI)

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

255

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,

256

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

257

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

258

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,

259

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

260

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

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

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

262

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

263

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

264

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

265

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.

266

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 . . :

267

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

268

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

269

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:

270

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

271

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.

272

Intensive archaeological survey of the proposed Central Sanitary Wastewater Treatment Facility, Savannah River Site, Aiken and Barnwell Counties, South Carolina  

SciTech Connect

The project area for the proposed Central Sanitary Wastewater Treatment Facility on the Savannah River Site includes a six-acre tract along Fourmile Branch and 18 mi of trunk line corridors. Archaeological investigations of the six-acre parcel resulted in the discovery of one small prehistoric site designated 38AK465. This cultural resource does not have the potential to add significantly to archaeological knowledge of human occupation in the region. The Savannah River Archaeological Research Program (SRARP) therefore recommends that 38AK465 is not eligible for nomination to the National Register of Historic Places (NRHP) and further recommends a determination of no effect. Archaeological survey along the trunk line corridors implicated previously recorded sites 38AK92, 38AK145, 38AK415, 38AK417, 38AK419, and 38AK436. Past disturbance from construction had severely disturbed 38AK92 and no archaeological evidence of 38AK145, 38AK419, and 38AK436 was recovered during survey. Lacking further evidence for the existence of these sites, the SRARP recommends that 38AK92, 38AK145, 38AK419, and 38AK436 are not eligible for nomination to the NRHP and thus warrant a determination of no effect. Two of these sites, 38Ak415 and 38AK417, required further investigation to evaluate their archaeological significance. Both of the sites have the potential to yield significant data on the prehistoric period occupation of the Aiken Plateau and the SRARP recommends that they are eligible for nomination to the NRHP. The Savannah River Archaeological Research Program recommends that adverse effects to sites 38AK415 and 38AK417 from proposed construction can be mitigated through avoidance.

Stephenson, D.K.; Sassaman, K.E.

1993-11-01T23:59:59.000Z

273

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

SciTech Connect

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

WADE C. ADAMS

2012-04-09T23:59:59.000Z

274

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

275

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

276

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

277

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

278

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

279

Survey of ecological resources at selected US Department of Energy sites  

Science Conference Proceedings (OSTI)

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

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

1996-09-01T23:59:59.000Z

280

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

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 - 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

282

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

SciTech Connect

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

P.C. Weaver

2008-03-19T23:59:59.000Z

283

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

284

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.

285

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

286

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

287

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

288

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,

289

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...

290

Nuclear and Radiological Field Training Center | Y-12 National...  

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

Field Training Center A site used for nuclear research in Oak Ridge, Tennessee during the Manhattan Project is now the Y-12 National Security Complex's Nuclear and Radiological...

291

JOM Salary Survey - TMS  

Science Conference Proceedings (OSTI)

JOM Salary Survey. This survey is currently closed. Please contact the author of this survey for further assistance. Javascript is required for this site to function, ...

292

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

293

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

294

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

295

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"

296

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

297

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

298

An in situ survey of Clean Slate 1, 2, and 3, Tonopah Test Range, Central Nevada. Date of survey: September--November 1993  

SciTech Connect

A ground-based in situ radiological survey was conducted downwind of the Clean Slate 1, 2, and 3 nuclear safety test sites at the Tonopah Test Range in central Nevada from September through November 1993. The purpose of the study was to corroborate the americium-241 ({sup 241}Am) soil concentrations that were derived from the aerial radiological survey of the Clean Slate areas, which was conducted from August through October 1993. The presence of {sup 241}Am was detected at 140 of the 190 locations, with unrecoverable or lost data accounting for fifteen (15) of the sampling points. Good agreement was obtained between the aerial and in situ results.

NONE

1995-08-01T23:59:59.000Z

299

Radiological control manual. Revision 1  

SciTech Connect

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

Kloepping, R.

1996-05-01T23:59:59.000Z

300

Improving Water Management: Applying ModelBuilder to site water impoundments using AEM survey data  

Science Conference Proceedings (OSTI)

ArcGIS ModelBuilder was used to create a GIS-based decision support model that incorporated digital elevation data and electromagnetic geophysical results gathered by helicopter to screen potential sites for water disposal impoundments produced from coal bed natural gas.

Sams, J.I.; Lipinski, B.A.; Harbert, W.P.; Ackman, T.E.

2007-01-01T23:59:59.000Z

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.


301

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

302

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

303

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

E-Print Network (OSTI)

RCRA 10/89 closure approved 9/95 9204-3 0928-U 1966 1989 200 Gasoline Removed RIR, closure NA NA 5 oil Closed in RCRA Closure letter Site place subtitle C 1994 monitored 7560 40 Unknown Unknown 1000 9722-6 2312-U 1987 1994 550 Diesel Inert filled CR (4/95) NA Closure approval 2/95 (6/96) 9722-5 2313-U

304

Survey of Physical and Chemical Properties of Soils Collected From Former Manufactured Gas Plant Sites  

Science Conference Proceedings (OSTI)

This report presents technical information and data from a study of the physical and chemical nature of soils at former manufactured gas plant (MGP) sites. Included in the report is a comparison of chemical analysis methods for determination of monocyclic aromatic hydrocarbons (MAHs), polycyclic aromatic hydrocarbons (PAHs), and total petroleum hydrocarbons (TPH). One of the specific objectives of the research was determining relationships between total soil and leachate concentrations of analytes of int...

1999-12-15T23:59:59.000Z

305

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

SciTech Connect

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

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

1983-01-01T23:59:59.000Z

306

General Employee Radiological Training (GERT)  

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

General Employee Radiological Training (GERT) Radiological Training for NSLS Access has been replaced with BNL General Employee Radiological Training (GERT). Please read the...

307

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.

308

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

309

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

310

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

311

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

312

Confirmatory Survey Report for the Quehanna Decommissioning Project, Karthaus, PA  

Science Conference Proceedings (OSTI)

The survey activities consisted of visual inspections and radiological surveys including beta and gamma surface scans and surface beta activity measurements.

W. C. Adams

2007-10-30T23:59:59.000Z

313

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

314

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

315

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

316

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

DOE Green Energy (OSTI)

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

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

2005-02-01T23:59:59.000Z

317

Site Manager Enclosure  

E-Print Network (OSTI)

This radiological release survey for the west property at the Canonsburg UMTRCA Title I disposal site is a precursor for selling the approximately 2.5 acres of land that lie west and outside of the disposal cell fence line. The basic design philosophy underlying this plan was agreed to a conference call with your office in July. We are planning to conduct the survey in late October or early November to allow effective use of a GPS unit after the leaves have fallen in the wooded area of the property. It is requested that you review the attached document and provide your concurrence, or comments, within time for us to meet this schedule. If you have any questions, please contact me at (412) 386-4754 or email me at

Mr. Paul Michalak; Cc W/o Enclosure; R. Ransbottom

2007-01-01T23:59:59.000Z

318

Radiological Control Division  

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

Support personnel, an accredited Personnel Monitoring service, a fully functional Instrumentation & Calibration facility, expertise in Radiological Engineering and the...

319

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.

320

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.

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

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.

322

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

323

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

324

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

325

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

326

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

Science Conference Proceedings (OSTI)

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

Robison, W. L., LLNL

1997-11-01T23:59:59.000Z

327

Routine Radiological Environmental Monitoring Plan. Volume 1  

SciTech Connect

The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

Bechtel Nevada

1999-12-31T23:59:59.000Z

328

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

329

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

330

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

331

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

332

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. : .: "

333

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.

334

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

SciTech Connect

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

P.C. Weaver

2008-06-12T23:59:59.000Z

335

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

336

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...

337

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

338

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

339

Intensive archaeological survey of the F/H Surface Enhancement Project Area, Savannah River Site, Aiken and Barnwell Counties, South Carolina  

Science Conference Proceedings (OSTI)

Twelve archaeological sites and four artifact occurrences were located by intensive survey of two tracts of land for the F and H Surface Enhancement Project on the Savannah River Site, Aiken and Barnwell Counties, South Carolina. Fieldwork in the 480-acre project area included surface reconnaissance of 3.6 linear kilometers of transects, 140 shovel tests along 4.2 linear kilometers of transects, an additional 162 shovel tests at sites and occurrences, and the excavation of six l {times} 2 m test units. All but one of the sites contained artifacts of the prehistoric era; the twelfth site consists of the remains of a twentieth-century home place. The historic site and six of the prehistoric sites consist of limited and/or disturbed contexts of archaeological deposits that have little research potential and are therefore considered ineligible for nomination to the National Register of Historic Places (NRHP). The remaining five sites have sufficient content and integrity to yield information important to ongoing investigations into upland site use. These sites (38AK146, 38AK535, 38AK539, 38AK541, and 38AK543) are thus deemed eligible for nomination to the NRHP and the Savannah River Archaeological Research Program (SRARP) recommends that they be preserved through avoidance or data recovery.

Sassaman, K.E.; Gillam, J.C.

1993-08-01T23:59:59.000Z

340

Intensive archaeological survey of the proposed Savannah River Ecology Laboratory Conference Center and Educational Facility, Savannah River Site, Aiken County, South Carolina  

Science Conference Proceedings (OSTI)

Documented in this report are the methods and results of an intensive archaeological survey for the proposed University of Georgia Savannah River Ecology Laboratory (SREL) Conference Center and Educational Facility on the DOE Savannah River Site (SRS). Archaeological investigations conducted by the Savannah River Archaeological Research Program (SRARP) on the 70-acre project area and associated rights-of-way consisted of subsurface testing at two previously recorded sites and the discovery of one previously unrecorded site. The results show that 2 sites contain archaeological remains that may yield significant information about human occupations in the Aiken Plateau and are therefore considered eligible for nomination to the National Register of Historic Places. Adverse impacts to these sites can be mitigated through avoidance.

Stephenson, K.; Crass, D.C.; Sassaman, K.E.

1993-02-01T23:59:59.000Z

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


341

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

342

Radiological assessment of the town of Edgemont  

SciTech Connect

Congress, in 1980, gave the Nuclear Regulatory Commission (NRC) the responsibility to coordinate and conduct a monitoring, engineering assessment, and remedial cleanup program in Edgemont, South Dakota. The Congressional intent was to locate public properties in Edgemont that had been contaminated by radioactive materials from a local uranium mill, and to clean up those properties. Because the Atomic Energy Act of 1954 gave NRC the authority to monitor for contamination but not to clean up contamination, Congress later assigned the remedial cleanup responsibility to the Department of Energy (DOE). NRC, through Battelle Pacific Northwest Laboratory (PNL), conducted a radiological survey of 96% of the properties in Edgemont and vicinity during the time period of September 1980 through April 1984. (Out of 976 total properties, 941 were surveyed.) The strategy of the survey was to screen properties for the possible presence of contamination by using short- and long-term radon progeny measurements, indoor and outdoor gamma exposure rate measurements, and soil radium-226 measurements. Properties that failed the screening surveys were measured more extensively to determine whether the elevated readings were due to residual radioactive materials from the uranium mill. This report contains the historical perspective of the Edgemont survey, explains the development and modifications of survey protocols, examines the problems encountered during the survey, and lists a summary of the results. The report also presents conclusions about the effectiveness of the survey techniques and about the rationale of a comprehensive survey of a whole community. The appendices section of this report contains all the protocols, a list of all the properties showing survey results for each, and reports on special studies conducted during the survey. These special studies contain many valuable insights that may prove beneficial to future radiological assessment surveys.

Jackson, P.O.; Thomas, V.W.; Young, J.A.

1985-01-01T23:59:59.000Z

343

Luminescence analysis for radiological and nuclear forensic application  

Science Conference Proceedings (OSTI)

This paper briefly discusses recombination luminescence and its use in forensic radiation dosimetry. Recombination luminescence techniques offer a new capability for radiological forensic analysis of sites and vehicles previously cleared of isotopic ... Keywords: OSL, TL, environmental dosimetry, forensic, optically stimulated luminescence, radiological, retrospective population dosimetry, thermoluminescence

Nigel A. Spooner; Barnaby W. Smith

2008-01-01T23:59:59.000Z

344

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

345

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

346

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

347

Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities  

Science Conference Proceedings (OSTI)

The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys.

Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E. [Iberdrola Ingenieria y Construccion (Spain); Martin, N. [ENRESA (Spain)

2008-01-15T23:59:59.000Z

348

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

349

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

350

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

351

Radiological Worker Training  

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

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...

352

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

353

DOE standard: Radiological control  

Science Conference Proceedings (OSTI)

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

Not Available

1999-07-01T23:59:59.000Z

354

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

Science Conference Proceedings (OSTI)

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

Evan Harpeneau

2011-06-24T23:59:59.000Z

355

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

356

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

357

Aerial survey finds no increase in radioactivity for Los Alamos...  

National Nuclear Security Administration (NNSA)

Alamos County and Los Alamos National Laboratory. The radiological surveys, conducted in August 2011 and June 2012, found that radioisotopes and their associated exposure rates...

358

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

SciTech Connect

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

EVAN M. HARPENAU

2012-06-28T23:59:59.000Z

359

Ecological survey for the siting of the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility  

SciTech Connect

This report summarizes the results of field ecological surveys conducted by the Center for Integrated Environmental Technologies (CIET) on the Idaho National Engineering Laboratory (INEL) at four candidate locations for the siting of the Mixed and Low-Level Waste Treatment Facility (MLLWTF) and the Idaho Waste Processing Facility (IWPF). The purpose of these surveys was to comply with all Federal laws and Executive Orders to identify and evaluate any potential environmental impacts because of the project. The boundaries of the candidate location were marked with blaze-orange lath survey marker stakes by the project management. Global Positioning System (GPS) measurements of the marker stakes were made, and input to the Arc/Info{reg_sign} geographic information system (GIS). Field surveys were conducted to assess any potential impact to any important species, important habitats, and to any environmental study areas. The GIS location data was overlayed onto the INEL vegetation map and an analysis of vegetation classes on the locations was done. Results of the field surveys indicate use of Candidate Location {number_sign}1 by pygmy rabbits (Sylvilagus idahoensis) and expected use by them of Candidate Locations {number_sign}3 and {number_sign}9. Pygmy rabbits are categorized as a C2 species by the US Fish and Wildlife Service (USFWS). Two other C2 species, the ferruginous hawk (Buteo regalis) and the loggerhead shrike (Lanius ludovicianus) would also be expected to frequent the candidate locations. Candidate Location {number_sign}5 at the north end of the INEL is in the winter range of a large number of pronghorn antelope (Antilocapra americana).

Hoskinson, R.L.

1994-05-01T23:59:59.000Z

360

Bibliography of publications related to the Yucca Mountain Site Characterization Project prepared by U.S. Geological Survey personnel through April 1991  

Science Conference Proceedings (OSTI)

Personnel of the US Geological Survey have participated in nuclear-waste management studies in the State of Nevada since the mid-1970`s. A bibliography of publications prepared principally for the US Department of Energy Yucca Mountain Site Characterization Project (formerly Nevada Nuclear Waste Storage Investigations) through April 1991 contains 475 entries in alphabetical order. The listing includes publications prepared prior to the inception of the Nevada Nuclear Waste Storage Investigations Project in April 1977 and selected publications of interest to the Yucca Mountain region. 480 refs.

Glanzman, V.M.

1991-11-01T23:59:59.000Z

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


361

Survey of Electric and Gas Rights-of-Way Practitioners: Current Practices and Views of Future Transmission Line Siting Issues  

Science Conference Proceedings (OSTI)

The adequacy of the nation's power grid is a topic of great concern, particularly the extent of new construction and upgrades required over the next decade to meet increasing energy demand. This report compiles the survey responses of energy company professionals associated with the task of developing rights-of-way. Respondents provided information on current industry practices, as well as the social and regulatory environment in which they operate to secure rights-of-way for new transmission lines and u...

2003-12-04T23:59:59.000Z

362

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

363

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

364

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

Science Conference Proceedings (OSTI)

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

DIEDIKER, L.P.

1999-07-29T23:59:59.000Z

365

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

366

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

367

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)

368

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

369

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

370

324 Building Baseline Radiological Characterization  

SciTech Connect

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

R.J. Reeder, J.C. Cooper

2010-06-24T23:59:59.000Z

371

NV/YMP RADIOLOGICAL CONTROL MANUAL  

SciTech Connect

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

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

2004-11-01T23:59:59.000Z

372

CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 115: AREA 25 TEST CELL A FACILITY, NEVADA TEST SITE, NEVADA  

SciTech Connect

This Closure Report (CR) describes the activities performed to close CAU 115, Area 25 Test Cell A Facility, as presented in the NDEP-approved SAFER Plan (NNSA/NSO, 2004). The SAFER Plan includes a summary of the site history, process knowledge, and closure standards. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical and radiological data to confirm that the remediation goals were met and to document final site conditions. The approved closure alternative as presented in the SAFER Plan for CAU 115 (NNSA/NSO, 2004) was clean closure; however, closure in place was implemented under a Record of Technical Change (ROTC) to the SAFER Plan when radiological surveys indicated that the concrete reactor pad was radiologically activated and could not be decontaminated to meet free release levels. The ROTC is included as Appendix G of this report. The objectives of closure were to remove any trapped residual liquids and gases, dispose regulated and hazardous waste, decontaminate removable radiological contamination, demolish and dispose aboveground structures, remove the dewar as a best management practice (BMP), and characterize and restrict access to all remaining radiological contamination. Radiological contaminants of concern (COCs) included cobalt-60, cesium-137, strontium-90, uranium-234/235/236/238, and plutonium-239/240. Additional COCs included Resource Conservation and Recovery Act (RCRA) metals, polychlorinated biphenyls (PCBs), and asbestos.

NA

2006-03-01T23:59:59.000Z

373

2012 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

2013-02-01T23:59:59.000Z

374

2010 Radiological Monitoring Results Associated with the Advance 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

2011-02-01T23:59:59.000Z

375

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

376

Real Time Quantitative Radiological Monitoring Equipment for Environmental Assessment  

SciTech Connect

The Idaho National Laboratory (INL) has developed a suite of systems that rapidly scan, analyze, and characterize radiological contamination in soil. These systems have been successfully deployed at several Department of Energy (DOE) laboratories and Cold War Legacy closure sites. Traditionally, these systems have been used during the characterization and remediation of radiologically contaminated soils and surfaces; however, subsequent to the terrorist attacks of September 11, 2001, the applications of these systems have expanded to include homeland security operations for first response, continuing assessment and verification of cleanup activities in the event of the detonation of a radiological dispersal device. The core system components are a detector, a spectral analyzer, and a global positioning system (GPS). The system is computer controlled by menu-driven, user-friendly custom software designed for a technician-level operator. A wide variety of detectors have been used including several configurations of sodium iodide (NaI) and high-purity germanium (HPGe) detectors, and a large area proportional counter designed for the detection of x-rays from actinides such as Am-241 and Pu-238. Systems have been deployed from several platforms including a small all-terrain vehicle (ATV), hand-pushed carts, a backpack mounted unit, and an excavator mounted unit used where personnel safety considerations are paramount. The INL has advanced this concept, and expanded the system functionality to create an integrated, field-deployed analytical system through the use of tailored analysis and operations software. Customized, site specific software is assembled from a supporting toolbox of algorithms that streamline the data acquisition, analysis and reporting process. These algorithms include region specific spectral stripping, automated energy calibration, background subtraction, activity calculations based on measured detector efficiencies, and on-line data quality checks and measures. These analyses are combined to provide real-time areal activity and coverage maps that are displayed to the operator as the survey progresses. The flexible functionality of the INL systems are well suited to multiple roles supporting homeland security needs.

John R. Giles; Lyle G. Roybal; Michael V. Carpenter

2006-03-01T23:59:59.000Z

377

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

378

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

379

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

380

Role of the inclusion survey contractor in the Uranium Mill Tailings Remedial Action Program  

Science Conference Proceedings (OSTI)

Twenty-four former uranium mills are involved in the Department of Energy's Uranium Mill Tailings Remedial Action Program (UMTRAP). The Radiological Survey Activities project at Oak Ridge National Laboratory serves as the Inclusion Survey Contractor (ISC) in the UMTRA program. Responsibilities of the ISC are: (1) to identify potentially contaminated sites in the vicinity of these former uranium mills; (2) conduct radiological surveys to assess whether the property is contaminated with material originating from the mill in excess of Environmental Protection Agency criteria formulated specifically for the UMTRA program (40 CFR 192); and (3) provide recommendations to DOE regarding remedial action. Properties are identified by the ISC using historical information, serial and ground-level gamma scanning, and surveying erosional pathways (wind and water movement of contamination from primary sources). Currently, over 8000 vicinity properties have been identified that warrant further investigation. Once identified, an inclusion survey is conducted to assess whether a property is sufficiently contaminated to warrant inclusion into the UMTRA program. The inclusion survey includes a complete gamma scan of the surfaces of the property outdoors and the lowest habitable level indoors, and collection of soil samples outdoors and/or radon daughter samples indoors if required. Survey methods are described. 8 references.

Berven, B.A.; Little, C.A.

1985-01-01T23:59:59.000Z

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.


381

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

382

Disabling Radiological Dispersal Terror  

SciTech Connect

Terror resulting from the use of a radiological dispersal device (RDD) relies upon an individual's lack of knowledge and understanding regarding its significance. Disabling this terror will depend upon realistic reviews of the current conservative radiation protection regulatory standards. It will also depend upon individuals being able to make their own informed decisions merging perceived risks with reality. Preparation in these areas will reduce the effectiveness of the RDD and may even reduce the possibility of its use.

Hart, M

2002-11-08T23:59:59.000Z

383

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

384

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado: Final report. Volume 4, Addenda D1--D5 to Appendix D  

SciTech Connect

This radiologic characterization of tho two inactive uranium millsites at Rifle, Colorado, was conducted by Bendix Field Engineering Corporation (Bendix) for the US Department of Energy (DOE), Grand Junction Projects Office, in accord with a Statement of Work prepared by the DOE Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor, Jacobs Engineering Group, Inc. (Jacobs). The purpose of this project is to define the extent of radioactive contamination at the Rifle sites that exceeds US Environmental Protection Agency, (EPA) standards for UMTRA sites. The data presented in this report are required for characterization of the areas adjacent to the tailings piles and for the subsequent design of cleanup activities. An orientation visit to the study area was conducted on 31 July--1 August 1984, in conjunction with Jacobs, to determine the approximate extent of contaminated area surrounding tho piles. During that visit, survey control points were located and baselines were defined from which survey grids would later be established; drilling requirements were assessed; and radiologic and geochemical data were collected for use in planning the radiologic fieldwork. The information gained from this visit was used by Jacobs, with cooperation by Bendix, to determine the scope of work required for the radiologic characterization of the Rifle sites. Fieldwork at Rifle was conducted from 1 October through 16 November 1984.

Not Available

1990-02-01T23:59:59.000Z

385

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

386

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

SciTech Connect

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

NSTec Environmental Restoration

2012-07-17T23:59:59.000Z

387

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

388

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

SciTech Connect

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

Adams, Wade C.

2012-01-24T23:59:59.000Z

389

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

390

PRELIMINARY SURVEY OF TEXAS CITY CHEMICALS, INC.  

Office of Legacy Management (LM)

(DOE), a preliminary survey was performed at the Borden Chemical Division plant in Texas City, Texas (see Fig. l), on November 17, 1977, to assess the radiological status of those...

391

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

392

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

393

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,

394

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

395

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

396

PNNL: Available Technologies: Nuclear & Radiological  

PNNL has more than 40 years of experience in radiological science and radiochemical separations based on its activities at the U.S. Department of ...

397

Radiological Toolbox User's Manual  

Science Conference Proceedings (OSTI)

A toolbox of radiological data has been assembled to provide users access to the physical, chemical, anatomical, physiological and mathematical data relevant to the radiation protection of workers and member of the public. The software runs on a PC and provides users, through a single graphical interface, quick access to contemporary data and the means to extract these data for further computations and analysis. The numerical data, for the most part, are stored within databases in SI units. However, the user can display and extract values using non-SI units. This is the first release of the toolbox which was developed for the U.S. Nuclear Regulatory Commission.

Eckerman, KF

2004-07-01T23:59:59.000Z

398

Smart Radiological Dosimeter  

DOE Patents (OSTI)

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

Kosslow, William J.; Bandzuch, Gregory S.

2004-07-20T23:59:59.000Z

399

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,

400

Radiological consequence analysis with HEU and LEU fuels  

SciTech Connect

A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and non-site specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. 10 references, 3 figures, 7 tables.

Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

1984-01-01T23:59:59.000Z

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.


401

REMOTE RADIOLOGICAL MONITORING  

SciTech Connect

A gamma-radiation telemetering system was utilized to measure fall-out levels at the Ncvada Test Site. Two methods of signal transmission were used: directcoupled field lines for on-site installations and commercial telephone lines for areas out to 330 miles. Graphic and tabular data cover on-site and off- site residual gamma-radiation dose rate measurements taken as a function of time after selected events. (auth)

Sigoloff, S.C.; Borella, H.M.

1958-11-01T23:59:59.000Z

402

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 -- _.. .-___

403

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:

404

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

SciTech Connect

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

Not Available

1990-08-01T23:59:59.000Z

405

2011 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

2012-02-01T23:59:59.000Z

406

Assessment of SRS radiological liquid and airborne contaminants and pathways  

Science Conference Proceedings (OSTI)

This report compiles and documents the radiological critical-contaminant/critical-pathway analysis performed for SRS. The analysis covers radiological releases to the atmosphere and to surface water, which are the principal media that carry contaminants off site. During routine operations at SRS, limited amounts of radionuclides are released to the environment through atmospheric and/or liquid pathways. These releases potentially result in exposure to offsite people. Though the groundwater beneath an estimated 5 to 10 percent of SRS has been contaminated by radionuclides, there is no evidence that groundwater contaminated with these constituents has migrated offsite (Arnett, 1996). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people.

Jannik, G.T.

1997-04-01T23:59:59.000Z

407

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

Force Established Nuclear Radiological Threat Task Force Established November 03, 2003 Washington, DC Nuclear Radiological Threat Task Force Established NNSA's Administrator...

408

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

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

Radiological Controls - Idaho Accelerated Retrieval Project Phase II CRAD, Radiological Controls - Idaho Accelerated Retrieval Project Phase II February 2006 A section of Appendix...

409

Site investigation report for Waste Area Grouping 4 at Oak Ridge National Laboratory. Volume 2, Appendixes: Environmental Restoration Program  

SciTech Connect

This report documents the UltraSonic Ranging and Data Systems (USRADS) survey conducted for radiological characterization of approximately 5 acres located at the Oak Ridge National Laboratory (ORNL) Waste Area Grouping (WAG) 4. The survey was conducted by Chemrad Tennessee Corporation under subcontract No. 7908-RS-00902 to CDM Federal Programs Corporation. The field survey began June 23, 1994 (Chemrad survey team was unable to actually enter field until June 24 awaiting sign-off of CDM plans by MMES) and was terminated on June 29, 1994. The designated survey area is located on the DOE X-10 facility and South of the main X-10 building complex. The entire north boundary of the site is adjacent to SWSA 4, with the Bath Tubbing Trench Seep Area (BTT) actually being a part of that SWSA (See Figure 1). Approximately one-third of the designated area was actually surveyed. The BTT area slopes moderately eastward toward a small stream in the WAG 4 area. The area is open and had recently been trimmed for the survey. The balance of the designated survey area lies along the small stream within WAG 4 and is densely wooded with heavy underbrush. The area had not been cleared or brushed. Survey reference points for the BTT area mere directly tied into the X-10 coordinate system while the t bale,ice of the designated survey area mere tied into an existing relative metric grid system. The designated area was surveyed for radiological characterization using near-surface gamma and beta detectors as well as an energy independent dosimeter. This report describes the survey method and presents the survey findings.

NONE

1995-08-01T23:59:59.000Z

410

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

SciTech Connect

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

P.C. Weaver

2009-04-29T23:59:59.000Z

411

Radiological Dose Calculations for Fusion Facilities  

Science Conference Proceedings (OSTI)

This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

Michael L. Abbott; Lee C. Cadwallader; David A. Petti

2003-04-01T23:59:59.000Z

412

Environmental Survey preliminary report  

SciTech Connect

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

Not Available

1988-04-01T23:59:59.000Z

413

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

414

DECOMMISSIONING PLAN AND RADIOLOGICAL  

E-Print Network (OSTI)

Cabot Performance Materials (Cabot) holds NRC License SMC-1562, covering storage of radioactive materials at both their Revere and Reading sites in Pennsylvania. Former ore processing at the Revere facility generated waste slag contaminated with uranium and thorium. In 1988, Cabot began onsite decommissioning activities for the Revere facility, including site

unknown authors

2001-01-01T23:59:59.000Z

415

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

416

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

417

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  

Science Conference Proceedings (OSTI)

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

Weaver, Phyllis C.

2012-08-29T23:59:59.000Z

418

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.

Phyllis C. Weaver

2012-08-29T23:59:59.000Z

419

w. T. Thorntot-l, OR RADIOLOGICAL STATUS OF FORMER VIRGINIA-CAROLINA...  

Office of Legacy Management (LM)

()r' 2J ;3:7 . - w. T. Thorntot-l, OR RADIOLOGICAL STATUS OF FORMER VIRGINIA-CAROLINA CHEMICAL CORPORATION SITE AT.818 PERRY STREET, RICHFIOND, VIRGINIA Your memorandum report of...

420

Radiological Threat Reduction: Dealing with Dirty Bombs  

E-Print Network (OSTI)

Nonproliferation and National Security Department May 2, 2007 #12;Topics What is a Radiological Dispersal Device

Homes, Christopher C.

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

Homeland Security Chemical/Biological/Radiological/Nuclear ...  

Science Conference Proceedings (OSTI)

... Information at NIST. Homeland Security Chemical/Biological/Radiological/ Nuclear/Explosives (CBRNE) Information at NIST. ...

2010-09-24T23:59:59.000Z

422

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

Science Conference Proceedings (OSTI)

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

Wickline, Alfred

2005-12-01T23:59:59.000Z

423

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...

424

Marshall Islands radiological followup  

SciTech Connect

In August, 1968, President Johnson announced that the people of Bikini Atoll would be able to return to their homeland. Thereafter, similar approval was given for the return of the peoples of Enewetak. These two regions, which comprised the Pacific Nuclear Testing Areas from 1946 to 1958, will probably be repopulated by the original inhabitants and their families within the next year. As part of its continuing responsibility to insure the public health and safety in connection with the nuclear programs under its sponsorship, ERDA (formerly AEC) has contracted Brookhaven National Laboratory to establish radiological safety and environmental monitoring programs for the returning Bikini and Enewetak peoples. These programs are described in the following paper. They are designed to define the external radiation environment, assess radiation doses from internal emitters in the human food chain, make long range predictions of total doses and dose commitments to individuals and to each population group, and to suggest actions which will minimize doses via the more significant pathways. (auth)

Greenhouse, N.A.; McCraw, T.F.

1976-04-30T23:59:59.000Z

425

Radiological design guide  

SciTech Connect

The purpose of this design guide is to provide radiological safety requirements, standards, and information necessary for designing facilities that will operate without unacceptable risk to personnel, the public, or the environment as required by the US Department of Energy (DOE). This design guide, together with WHC-CM-4-29, Nuclear Criticality Safety, WHC-CM-4-46, Nonreactor Facility Safety Analysis, and WHC-CM-7-5, Environmental Compliance, covers the radiation safety design requirements at Westinghouse Hanford Company (WHC). This design guide applies to the design of all new facilities. The WHC organization with line responsibility for design shall determine to what extent this design guide shall apply to the modifications to existing facilities. In making this determination, consideration shall include a cost versus benefit study. Specifically, facilities that store, handle, or process radioactive materials will be covered. This design guide replaces WHC-CM-4-9 and is designated a living document. This design guide is intended for design purposes only. Design criteria are different from operational criteria and often more stringent. Criteria that might be acceptable for operations might not be adequate for design.

Evans, R.A.

1994-08-16T23:59:59.000Z

426

Radiological training for tritium facilities  

Science Conference Proceedings (OSTI)

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

427

FDH radiological design review guidelines  

SciTech Connect

These guidelines discuss in more detail the radiological design review process used by the Project Hanford Management Contractors as described in HNF-PRO-1622, Radiological Design Review Process. They are intended to supplement the procedure by providing background information on the design review process and providing a ready source of information to design reviewers. The guidelines are not intended to contain all the information in the procedure, but at points, in order to maintain continuity, they contain some of the same information.

Millsap, W.J.

1998-09-29T23:59:59.000Z

428

Radiological Control Technician: Standardized technician Qualification Standard  

Science Conference Proceedings (OSTI)

The Qualification Standard states and defines the knowledge and skill requirements necessary for successful completion of the Radiological Control Technician Training Program. The standard is divided into three phases: Phase I concerns RCT Academic training. There are 13 lessons associated with the core academics program and 19 lessons associated with the site academics program. The staff member should sign the appropriate blocks upon successful completion of the examination for that lesson or group of lessons. In addition, facility specific lesson plans may be added to meet the knowledge requirements in the Job Performance Measures (JPM) of the practical program. Phase II concerns RCT core/site practical (JPMs) training. There are thirteen generic tasks associated with the core practical program. Both the trainer/evaluator and student should sign the appropriate block upon successful completion of the JPM. In addition, facility specific tasks may be added or generic tasks deleted based on the results of the facility job evaluation. Phase III concerns the oral examination board successful completion of the oral examination board is documented by the signature of the chairperson of the board. Upon completion of all of the standardized technician qualification requirements, final qualification is verified by the student and the manager of the Radiological Control Department and acknowledged by signatures on the qualification standard. The completed Qualification Standard shall be maintained as an official training record.

Not Available

1992-10-01T23:59:59.000Z

429

Radiological design criteria for fusion power test facilities  

Science Conference Proceedings (OSTI)

The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses.

Singh, M.S.; Campbell, G.W.

1982-02-12T23:59:59.000Z

430

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

431

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

432

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

SciTech Connect

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

E.N. Bailey

2009-03-18T23:59:59.000Z

433

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

434

Operational Implementation of the MARSSIM Process at the Wayne Interim Storage Site  

DOE Green Energy (OSTI)

This paper describes the methodologies behind the operational implementation of the Multi Agency Radiation Site Survey and Investigation Manual (MARSSIM) process at the Wayne Interim Storage Site (WISS). The United States Army Corps of Engineers (USACE) and Environmental Chemical Corporation (ECC) have implemented the MARSSIM process using various surveys producing raw data. The final remedial status of a survey unit is derived through data reduction, while maintaining a high degree of efficiency in the construction aspects of the remedial action. Data reduction of field measurements is accomplished by merging the data outputs of a Digital Global Positioning System, an exposure rate meter, and laboratory analyses to produce maps which present exposure rates, elevations, survey unit boundaries, direct measurement locations, and sampling locations on a single map. The map serves as a data-posting plot and allows the project team to easily judge the survey unit's remedial status. The operational implementation of the MARSSIM process has been successful in determining the eligibility of survey units for final status surveys at the WISS and also in demonstrating final status radiological and chemical conditions while maintaining an efficient remedial action effort.

Hays, D. C. Jr.; Trujillo, P. A. IV.; Zoller, S. G.

2002-02-27T23:59:59.000Z

435

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 foun