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1

Radiological Assistance Program  

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

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

1992-04-10T23:59:59.000Z

2

ORISE: Radiological program assessment services  

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

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

3

E-Print Network 3.0 - action program radiological Sample Search...  

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

their SLAC supervisors and points of contact, ESH program managers, and SLAC Site Security. ... Source: Wechsler, Risa H. - Kavli Institute for Particle Astrophysics and...

4

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

5

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

SciTech Connect (OSTI)

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

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

1984-06-01T23:59:59.000Z

6

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

SciTech Connect (OSTI)

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

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

1984-04-01T23:59:59.000Z

7

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

SciTech Connect (OSTI)

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

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

1984-04-01T23:59:59.000Z

8

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

SciTech Connect (OSTI)

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

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

1984-04-01T23:59:59.000Z

9

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

SciTech Connect (OSTI)

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

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

2012-02-26T23:59:59.000Z

10

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

11

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

12

Corrective Action Program Guide  

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

This Guide was developed to assist the Department of Energy (DOE) organizations and contractors in the development, implementation, and followup of corrective action programs utilizing the feedback and improvement core safety function within DOE's Integrated Safety Management System. This Guide outlines some of the basic principles, concepts, and lessons learned that DOE managers and contractors might consider when implementing corrective action programs based on their specific needs. Canceled by DOE G 414.1-2B. Does not cancel other directives.

2006-03-02T23:59:59.000Z

13

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

14

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

15

Radiological Health Program (New Hampshire)  

Broader source: Energy.gov [DOE]

The Statute establishes programs and procedures for regulation of sources of radiation within the state, among states, and between the federal government and the state. A regulatory program...

16

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

17

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

18

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

SciTech Connect (OSTI)

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

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

1984-04-01T23:59:59.000Z

19

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

20

ORISE: Radiological program assessment services  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory |CHEMPACKRadiological program assessment services Minimizing the

Note: This page contains sample records for the topic "action program radiological" 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

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

SciTech Connect (OSTI)

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

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

1980-01-01T23:59:59.000Z

22

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

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

23

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

24

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

25

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

26

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

SciTech Connect (OSTI)

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

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

1984-05-01T23:59:59.000Z

27

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

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

28

Description of the Formerly Utilized Sites Remedial Action Program  

SciTech Connect (OSTI)

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

Not Available

1980-09-01T23:59:59.000Z

29

DOE Radiological Calibrations Intercomparison Program: Results of fiscal year 1987  

SciTech Connect (OSTI)

This report presents the FY 1987 results of the radiological calibrations intercomparison program. The intercomparison operation is discussed, and the equipment is described, particularly the instrument set, the beta source set, and relevant calculations. Solutions to problems and improvements in the program are suggested, and conclusions are then introduced. 9 refs., 3 figs., 8 tabs.

Cummings, F.M.; McDonald, J.C.

1988-06-01T23:59:59.000Z

30

EM-Led Radiological Incident Response Program Receives Honors  

Broader source: Energy.gov [DOE]

A program led by EMs Carlsbad Field Office (CBFO) that coordinates analytical capabilities throughout DOE for response to potential national radiological incidents recently received recognition for the best-in-track poster at a waste management conference earlier this year.

31

Nuclear and Radiological Engineering and Medical Physics Programs  

E-Print Network [OSTI]

Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants one of the highest among all engineers #12;Westinghouse AP1000 Areva EPR GE Nuclear ESBWR B&W m

Weber, Rodney

32

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT  

Office of Legacy Management (LM)

RADIOLOGICAL HEALTH LABORATORY) WINCHESTER, MASSACHUSE'ITS Department of Energy Office of Nuclear Energy Office of Remedial Action and Waste Technology Division of Facility and...

33

Radiological Assistance Program, DOE Region 6 response plan  

SciTech Connect (OSTI)

This program plan meets all the requirements identified in DOE Order 5530.3, Radiological Assistance Program and supports those requirements leading to the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC) as required by DOE 5530-5. Requests for radiological assistance may come from other DOE facilities, Federal or state agencies, tribal officials, or from any private corporation or individual. Many of the requests will be handled by a telephone call, a conference or a letter, teletype or memorandum. Other requests for assistance may involve radioactive material in serious accidents, fire, personal injuries, contamination or possible hazards to the general public. Some occurrences may require the dispatch of trained personnel equipped with radiation monitoring instruments and related equipment necessary to evaluate, control and neutralize the hazard. The primary responsibility for incidents involving radioactive material always remains with the party having custody of the radioactive materials. In addition, the DOE recognizes that the assistance provided shall not in any way preempt state, tribal, or local authority and/or responsibility on state or tribal properties. Toward this end, DOE assistance for non-DOE radioactive materials, is limited to technical assistance, advice, measurement and other resources as deemed necessary by the local authorities but excludes DOE interface with the public media. This is a function handled by the local or state Incident Commander.

Jakubowski, F.M.

1993-02-01T23:59:59.000Z

34

Lawrence Berkeley Laboratory Affirmative Action Program. Revised  

SciTech Connect (OSTI)

The Lawrence Berkeley Laboratory`s Affirmative Action Program (AAP) serves as a working document that describes current policies, practices, and results in the area of affirmative action. It represents the Laboratory`s framework for an affirmative approach to increasing the representation of people of color and women in segments of our work force where they have been underrepresented and taking action to increase the employment of persons with disabilities and special disabled and Vietnam era veterans. The AAP describes the hierarchy of responsibility for Laboratory affirmative action, the mechanisms that exist for full Laboratory participation in the AAP, the policies and procedures governing recruitment at all levels, the Laboratory`s plan for monitoring, reporting, and evaluating affirmative action progress, and a description of special affirmative action programs and plans the Laboratory has used and will use in its efforts to increase the representation and retention of groups historically underrepresented in our work force.

NONE

1995-06-01T23:59:59.000Z

35

Radiological assessment and remedial action report for the ''Son of Lansdowne'' property, 186 North Lansdowne Avenue, Lansdowne, Pennsylvania  

SciTech Connect (OSTI)

This document reports the results of a radiological assessment and remedial action program conducted by Argonne National Laboratory personnel at a radioactively contaminated private residence in Lansdowne, Pennsylvania. The program was conducted on the residence at 186 Lansdowne Avenue. The survey conducted by the ANL personnel indicated that several dozen areas or spots of contamination were present on all floors and the basement of the three-story house. Contamination was found on furniture, carpeting, walls, floors, woodwork, and ceilings. Remedial action undertaken to remove the contamination ranged from scrubbing, to scraping, to shaving of wood, to removal and disposal of items and material that could not be adequately decontaminated. Outdoors, contaminated soil was removed from the backyard, and the driveway was dug up so the contaminated subsurface material could be removed. The remedial action generated quantities of radioactive waste, including four 55-gallon drums and one M-III bin (120 ft/sup 3/) containing floor tile, concrete, personal items, furniture, floor scrapings, vermiculite absorbed scrub water, and other items. In addition, there were 24 M-III bins containing approximately 112 tons of contaminated soil and rock from the two contaminated areas in the backyard and from the contaminated subsurface of the driveway. 2 refs., 39 figs., 12 tabs.

Smith, W.H.; Wynveen, R.A.

1987-08-01T23:59:59.000Z

36

RCRA corrective action program guide (Interim)  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is responsible for compliance with an increasingly complex spectrum of environmental regulations. One of the most complex programs is the corrective action program proposed by the US Environmental Protection Agency (EPA) under the authority of the Resource Conservation and Recovery Act (RCRA) as amended by the Hazardous and Solid Waste Amendments (HSWA). The proposed regulations were published on July 27, 1990. The proposed Subpart S rule creates a comprehensive program for investigating and remediating releases of hazardous wastes and hazardous waste constituents from solid waste management units (SWMUs) at facilities permitted to treat, store, or dispose of hazardous wastes. This proposed rule directly impacts many DOE facilities which conduct such activities. This guidance document explains the entire RCRA Corrective Action process as outlined by the proposed Subpart S rule, and provides guidance intended to assist those persons responsible for implementing RCRA Corrective Action at DOE facilities.

Not Available

1993-05-01T23:59:59.000Z

37

Risk assessment in the DOE Assurance Program for Remedial Action  

SciTech Connect (OSTI)

This document provides information obtained during the performance of risk assessment tasks in support of the Assurance Program for Remedial Action (APRA) sponsored by the Office of Operational Safety of the Department of Energy. We have presented a method for the estimation of projected health effects at properties in the vicinity of uranium mill tailing piles due to transported tailings or emissions from the piles. Because radon and radon daughter exposure is identified as the principal factor contributing to health effects at such properties, the basis for estimating lung cancer risk as a result of such exposure is discussed in detail. Modeling of health risk due to a secondary pathway, ingestion of contaminated, home-grown food products, is also discussed since it is a potentially important additional source of exposure in certain geographic locations. Risk assessment methods used in various mill tailings reports are reviewed. The protocols for radiological surveys conducted in DOE-sponsored remedial action programs are critically reviewed with respect to their relevance to the needs of health risk estimation. The relevance of risk assessment to the APRA program is discussed briefly.

Marks, S.; Cross, F.T.; Denham, D.H.; Kennedy, W.E.; Stenner, R.D.

1985-08-01T23:59:59.000Z

38

SymposiumandIndustrialAffiliatesProgramLightinAction Industrial Affiliates Program  

E-Print Network [OSTI]

SymposiumandIndustrialAffiliatesProgramLightinAction #12;Industrial Affiliates Program Friday, 8 Session I Abstract: Recently Additive Manufacturing (AM) has been hailed as the "third industrial revolution" by Economist magazine [April -2012]. Precision of the product manufactured by AM largely depends

Van Stryland, Eric

39

Transcript of See Action and Technical Assistance Program Webcast...  

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

Transcript of See Action and Technical Assistance Program Webcast: Energy Audit and Retro-Commissioning Policies for Public and Commercial Buildings Transcript of See Action and...

40

U.S. Department of Energy Region 6 Radiological Assistance Program response plan. Revision 2  

SciTech Connect (OSTI)

Upon request, the DOE, through the Radiological Assistance Program (RAP), makes available and will provide radiological advice, monitoring, and assessment activities during radiological incidents where the release of radioactive materials is suspected or has occurred. Assistance will end when the need for such assistance is over, or if there are other resources available to adequately address the incident. The implementation of the RAP is usually accomplished through the recommendation of the DOE Regional Coordinating Office`s (RCO) on duty Regional Response Coordinator (RRC) with the approval of the Regional Coordinating Office Director (RCOD). The DOE Idaho Operations Office (DOE-ID) is the designated RCO for DOE Region 6 RAP. The purpose of this document is: to describe the mechanism for responding to any organization or private citizen requesting assistance to radiological incidents; to coordinate radiological assistance among participating federal agencies, states, and tribes in DOE Region 6; and to describe the RAP Scaled Response concept of operations.

Jakubowski, F.M.

1998-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

Radiation Protection Considerations at USACE Formerly Utilized Sites Remedial Action Program (FUSRAP) Projects  

SciTech Connect (OSTI)

The Formerly Utilized Sites Remedial Action Program (FUSRAP) was initially authorized by Congress in 1974. FUSRAP was enacted to address residual radioactive contamination associated with numerous sites across the U.S. at which radioactive material (primarily Uranium ores and related milling products) had been processed in support of the nation's nuclear weapons program dating back to the Manhattan Project and the period immediately following World War II. In October 1997, Congress transferred the management of this program from the Department of Energy to the United States Corp of Engineers. Through this program, the Corps addresses the environmental remediation of certain sites once used by DOE's predecessor agencies, the Manhattan Engineer District and the Atomic Energy Commission. The waste at FUSRAP sites consists mainly of low levels of uranium, thorium and radium, along with some mixed wastes. Upon completion of remedial activities, these sites are transferred to DOE for long-term stewardship activities. This paper presents and contrasts the radiological conditions and recent monitoring results associated with five large ongoing FUSRAP projects including Maywood, N.J.; the Linde site near Buffalo, N.Y.; Colonie in Albany N.Y. and the St Louis, Mo. airport and downtown sites. The radiological characteristics of soil and debris at each site and respective regulatory clean up criteria is presented and contrasted. Some differences are discussed in the radiological characteristics of material at some sites that result in variations in radiation protection monitoring programs. Additionally, summary data for typical personnel radiation exposure monitoring results are presented. In summary: 1. The FUSRAP projects for which data and observations are reported in this paper are considered typical of the radiological nature of FUSRAP sites in general. 2. These sites are characterized by naturally occurring uranium and thorium series radionuclides in soil and debris, at concentrations typically < E4 pCi/ gram total activity. 3. Although external exposure rates are generally low resulting in few exposures above background, occasional 'hot spots' are observed in the 1- 10 mR / hr range or higher. However personnel and general area external exposure monitoring programs consistently demonstrate very low potential for external exposure at theses sites. 4. Potential for airborne exposure is controlled by wetting and misting techniques during excavation and movement of materials. Air sampling and bioassay programs confirm low potential for airborne exposure of workers at these sites. 5. Radiation protection and health physics monitoring programs as implemented at these sites ensure that exposures to personal are maintained ALARA. (authors)

Brown, S.H. [CHP, SHB INC., Centennial, Colorado (United States)

2008-07-01T23:59:59.000Z

42

action program fusrap: Topics by E-print Network  

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

Corps that can affect a project's cost and schedule. Earlier this year, Buffalo District project teams reached US Army Corps of Engineers 22 How will the RealWorld Action Program...

43

24 Command Fire Improvement Action Program Plan  

SciTech Connect (OSTI)

Fluor Hanford (FH) is responsible for providing support to the Department of Energy Richland Operations Office (RL) in the implementation of the Hanford Emergency Preparedness (EP) program. During fiscal year 2000, a number of program improvements were identified from various sources including a major range fire (24 Command Fire). Evaluations of the emergency preparedness program have confirmed that it currently meets all requirements and that performance of personnel involved is good, however the desire to effect continuous improvement resulted in the development of this improvement program plan. This program plan defines the activities that will be performed in order to achieve the desired performance improvements.

GRIFFIN, G.B.

2000-12-01T23:59:59.000Z

44

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users Manual  

SciTech Connect (OSTI)

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Dr. Bradley J Schrader

2010-10-01T23:59:59.000Z

45

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual  

SciTech Connect (OSTI)

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Dr. Bradley J Schrader

2009-03-01T23:59:59.000Z

46

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

SciTech Connect (OSTI)

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

Ludlam, J.R.

1985-01-01T23:59:59.000Z

47

Overview of the U.S. Department of Energy Formerly Utilized Sites Remedial Action Program - 12189  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP) was established in 1974 to address residual radiological contamination at sites where work was performed for the Manhattan Engineer District and U.S. Atomic Energy Commission. Initially, FUSRAP activities began with a records search for sites that had the potential to contain residual radiological contamination; 46 sites were identified that were eligible for and required remediation. Remedial action began in 1979. In 1997, Congress assigned responsibility for the remediation of FUSRAP sites to the U.S. Army Corps of Engineers (USACE). DOE retains responsibility for determining if sites are eligible for FUSRAP remediation and for providing long-term surveillance and maintenance (LTS&M) of remediated FUSRAP sites. DOE LTS&M activities are designed to ensure that FUSRAP sites remain protective of human health and the environment and to preserve knowledge regarding FUSRAP sites. Additional elements include eligibility determinations, transition of remediated sites from USACE to DOE, LTS&M operations such as inspections and institutional controls management, stakeholder support, preservation of records, and real property and reuse. DOE maintains close coordination with USACE and regulators to ensure there is no loss of protectiveness when sites transition to DOE for LTS&M.

Clayton, Christopher [U.S. Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S. Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S. Department of Energy Office of Legacy Management, Westminster, Colorado; Gillespie, Joey [S.M. Stoller Corporation, Contractor for the U.S. Department of Energy Office of Legacy Management, Grand Junction, Colorado; Widdop, Michael [S.M. Stoller Corporation, Contractor for the U.S. Department of Energy Office of Legacy Management, Grand Junction, Colorado; none,

2012-02-26T23:59:59.000Z

48

Idaho National Engineering Laboratory Radiological Environmental Surveillance Program 1995 annual report  

SciTech Connect (OSTI)

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

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

1996-08-01T23:59:59.000Z

49

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

50

NNSA PERSONNEL SECURITY CLEARANCE ACTION REQUEST Program Code: NA  

E-Print Network [OSTI]

NNSA PERSONNEL SECURITY CLEARANCE ACTION REQUEST Program Code: NA OFFICIAL USE ONLY (UPON sections and fields are required to be completed. The National Nuclear Security Administration (NNSA material (SNM). AL F 470.1 Form is used by NNSA Personnel Security Department to initiate background

Fuerschbach, Phillip

51

Current activities handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the activities each of the thirteen state legislatures potentially affected by the Formerly Utilized Sites Remedial Action Program. It contains a description of the state legislative procedural rules and a schedule of each legislative session; a summary of pending relevant legislation; the name and telephone number of legislative and state agency contacts; and the full text of all bills identified.

none,

1981-02-27T23:59:59.000Z

52

Hazardous Waste Remedial Actions Program annual progress report, FY 1990  

SciTech Connect (OSTI)

The Hazardous Waste Remedial Actions Programs (HAZWRAP), a unit of Martin Marietta Energy Systems, Inc., supports the Department of Energy (DOE) Oak Ridge Operations Office in broadly environmental areas, especially those relating to waste management and environmental restoration. HAZWRAP comprises six program areas, which are supported by central administrative and technical organizations. Existing programs deal with airborne hazardous substances, pollution prevention, remedial actions planning, environmental restoration, technology development, and information and data systems. HAZWRAP's mission to develop, promote, and apply-cost-effective hazardous waste management and environmental technologies to help solve national problems and concerns. HAZWRAP seeks to serve as integrator for hazardous waste and materials management across the federal government. It applies the unique combination of research and development (R D) capabilities, technologies, management expertise, and facilities in the Energy Systems complex to address problems of national importance. 24 figs., 10 tabs.

Not Available

1990-12-01T23:59:59.000Z

53

Alternatives for management of wastes generated by the formerly utilized sites remedial action program and supplement  

SciTech Connect (OSTI)

Alternatives for disposal or stabilization of the wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP) are identified and compared, with emphasis on the long-term aspects. These wastes consist of soil material and rubble containing trace amounts of radionuclides. A detailed pathway analysis for the dose to the maximally exposed individual is carried out using an adaptation of the natural analogue method. Comparisons of the different alternatives, based on the results of the pathway analysis and qualitative cost considerations, indicate that, if the hazard is such that the wastes must be removed and disposed of rather than stabilized in place, disposal by immediate dispersal is preferable to containment, and containment followed by slow planned dispersal is preferable to containment without dispersal. The Supplement presents refinements of work that was reported at the 1982 International Decommissioning Symposium. The new material consists of revisions of the estimates of the predicted potential dose to the maximally exposed individual and a more detailed comparative assessment of the radiological impacts of alternatives for management of wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP).

Gilbert, T.L.; Peterson, J.M.; Vocke, R.W.; Alexander, J.K.

1983-03-01T23:59:59.000Z

54

Massachusetts state information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the state of Massachusetts. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; the full text of relevant statutes and regulations.

None

1981-02-09T23:59:59.000Z

55

California state information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the state of California. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; the full text of relevant statutes and regulations.

none,

1981-02-09T23:59:59.000Z

56

Pennsylvania state information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and State levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Pennsylvania. It contains a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

none,

1980-12-31T23:59:59.000Z

57

Maryland State information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Handbook Series Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Maryland. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

none,

1980-12-31T23:59:59.000Z

58

Florida state information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with DOE, Office of Nuclear Waste Management, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the federal and state levels, the pertinent programs they administer, each affected state legislature, and current federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Florida. It contains a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

None

1981-02-27T23:59:59.000Z

59

Oregon state information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Oregon. It contains a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

none,

1980-12-31T23:59:59.000Z

60

Oregon state information handbook formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administater, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Oregon. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

none,

1980-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

Iowa state information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, By Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the state of Iowa. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; the full test of relevant statutes and regulations.

None

1981-02-09T23:59:59.000Z

62

Annual Radiological Environmental Monitoring Program Report for the Fort St. Vrain Independent Spent Fuel Storage Installation (2003)  

SciTech Connect (OSTI)

This report presents the results of the 2003 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Fort St. Vrain Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the predominant radiation exposure pathway, direct radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.

J. R. Newkirk; F. J. Borst, CHP

2004-02-01T23:59:59.000Z

63

Shiprock case study 1986 annual DOE Remedial Action Programs meeting, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This document contains primarily reproductions of slides presented at the 1986 Annual Doe Remedial Action Programs Meeting, Oak Ridge, Tennessee.

Themelis, J.; Baker, K.; Meyer, R.; Thiers, J.

1986-12-31T23:59:59.000Z

64

Book Review: Radiological Conditions in the Dnieper River Basin: Assessment by an International Expert Team and Recommendations for an Action Plan  

SciTech Connect (OSTI)

This article is a book review of a report from the International Atomic Energy Agency that was prepared by a team of scientists from Belarus, the Russian Federation, and Ukraine as an assessment of radiological contamination of the Dnieper River, which flows through these three countries. The topics covered begin with radioactive sources (actual and potential) including areas affected by the Chernobyl nuclear accident, nuclear power plants along the river and its tributaries, uranium mining and ore processing, radioactive waste storage and disposal sites, and non-power sources, such as medicine, industry, and research. The report continues with an assessment of human exposures to radiation from these sources. An additional area of consideration is radiological hot spots in the region. The report finishes with conclusions and recommendations to the regional governments for a strategic action plan and individual government national plans.

Napier, Bruce A.

2007-12-31T23:59:59.000Z

65

Missouri State information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Missouri. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature chairmen, and a summary of recent relevant legislative action; a description of the organization and structure of local governments affected by remedial action at the St. Louis area sites; a summary of relevant local ordinances and regulations; an identification of relevant public interest groups; a list of radio stations, television stations, and newspapers that provide public information to the St. Louis area or to Jefferson City; and the full text of relevant statutes and regulations.

none,

1980-12-31T23:59:59.000Z

66

Letter Report - Verification Results for the Non-Real Property Radiological Release Program at the West Valley Demonstration Project, Ashford, New York  

SciTech Connect (OSTI)

The objective of the verification activities is to provide an independent review of the design, implementation, and performance of the radiological unrestricted release program for personal property, materials, and equipment (non-real property).

M.A. Buchholz

2009-04-29T23:59:59.000Z

67

Formerly Used Sites Remedial Action Program (FUSRAP) W. R. Grace Building 23 Remedial Action-Challenges and Successes - 12247  

SciTech Connect (OSTI)

Monazite sand processing was conducted at the W. R. Grace Curtis Bay Facility (Baltimore, Maryland) from mid-May 1956 through the spring of 1957 under license to the Atomic Energy Commission (AEC), for the extraction of source material in the form of thorium, as well as rare earth elements. The processing was conducted in the southwest quadrant of a ca. 100 year old, five-story, building (Building 23) in the active manufacturing portion of the facility. Building components and equipment in the southwest quadrant of Building 23 exhibited residual radiological activity remaining from the monazite sand processing. U.S. Army Corps of Engineers (USACE) conducted a remedial investigation (RI) and feasibility study (FS) and prepared a Record of Decision (ROD) to address residual radioactivity on building components and equipment in the southwest quadrant of Building 23. The remedy selected for the southwest quadrant of Building 23, which was documented in the ROD (dated May 2005), was identified as 'Alternative 2: Decontamination With Removal to Industrial Use Levels'. The selected remedy provided for either decontaminating or removing areas of radioactivity to meet the RGs. Demonstration of compliance with the selected ARAR was performed using the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) and other appropriate guidance, as well as appropriate dose modeling codes where necessary. USACE-Baltimore District along with its private industry partner worked together under the terms of a 2008 Settlement Agreement to implement the remedial action (RA) for the southwest quadrant of Building 23. The RA was conducted in two phases: Phase 1 was completed to improve the building condition for support of subsequent remedial action and decrease scope uncertainty of the remedial action, and Phase 2 included decontamination and removal activities to meet the RGs and demonstration of compliance with the selected ARAR. Challenges encountered during the RA include: coordination with stakeholders, coordination between multiple RA contractors, addressing unique structural challenges for Building 23, nonradiological hazards associated with the RA, weather issues, and complex final status survey (FSS) coordination. The challenges during the Phase 1 RA were handled successfully. The challenges for the Phase 2 RA, which is anticipated to be complete by late-summer of 2012, have been handled successfully so far. By fall of 2012, USACE is expecting to finalize a robust RA Closure Report, including the Final Status Survey Report, which summarizes the RA activities and documents compliance with the ROD. During the ongoing RA at Building 23, there have been and still are many challenges both technically and from a project management perspective, due in part to the nature and extent of impact at the site (residual radioactivity within an active processing building), dual oversight by the property owner and USACE, and site-specific challenges associated with a complex RA and multiple contractors. Currently, USACE and its industry partner are overseeing the completion of RA field activities. RA closure documentation for the remediation of Building 23 to address residual contamination in building materials will be reviewed/approved by USACE and its industry partner upon completion of the field activities. USACE and its industry partner are working well together, through the Settlement Agreement, to conduct a cost-efficient and effective remedial action to address the legacy issues at Building 23. This cooperative effort has set a firm foundation for achieving a successful RA at the RWDA using a 'forward think' approach, and it is a case study for other sites where an industry partner is involved. The collaborative effort led to implementation of an RA which is acceptable to the site owner, the regulators, and the public, thus allowing USACE to move this project forward successfully in the FUSRAP program. (authors)

Barber, Brenda; Honerlah, Hans [U.S. Army Corps of Engineers - Baltimore District, 10 S. Howard St., Baltimore, Maryland, 21201 (United States); O'Neill, Mike [EA Engineering, Science, and Technology, 15 Loveton Circle, Baltimore, Maryland, 21152 (United States); Young, Carl [Cabrera Services, Inc., 1106 N. Charles St., Suite 300, Baltimore, MD 21201 (United States)

2012-07-01T23:59:59.000Z

68

State Energy Program (SEP) Strengthening Building Retrofit Markets and Stimulating Energy Efficiency Action  

Broader source: Energy.gov [DOE]

National Energy Technology Laboratory (NETL) presentation on State Energy Program (SEP) Strengthening Building Retrofit Markets and Stimulating Energy Efficiency Action DE-FOA-0000251, Stimulating Energy Efficiency Action from State Public Utility Commissions DE-FOA-0000266

69

Federal government information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the Federal Government. It contains a summary of the organization and responsibilities of agencies within the executive branch of the Federal government which may be relevant to FUSRAP activities; a brief summary of relevant Federal statutes and regulations; a description of the structure of the US Congress, identification of the officers, relevant committees and committee chairmen; a description of the Federal legislative process; a summary of legislation enacted and considered in the recently-adjourned 96th Congress; a description of the Federal budgetary process; a summary of the Carter Administration's comprehensive radioactive waste management program; and excerpts from the text of relevant federal statutes and regulations.

Not Available

1980-12-31T23:59:59.000Z

70

Transcript of See Action and Technical Assistance Program Webinar: Strategic Energy Management  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy (DOE) See Action Network and Weatherization and Intergovernmental Program Technical Assistance Program sponsored this webinar about strategic management in the public sector on November 7, 2012.

71

radiological | EMSL  

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

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

72

affirmative action program: Topics by E-print Network  

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

programming Air pollution modeling: proportional rollback, Gaussian transport, emissions trading Location of waste disposal facilities, integer linear programming Dissolved...

73

RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel  

SciTech Connect (OSTI)

This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors.

Yuan, Y.C. [Square Y, Orchard Park, NY (United States); Chen, S.Y.; LePoire, D.J. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Rothman, R. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

1993-02-01T23:59:59.000Z

74

action program sites: Topics by E-print Network  

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

profoundly Calvanese, Diego 29 Reconnaissance Soil Geochemistry at the Riverton Uranium Mill Tailings Remedial Action Site, Fremont Environmental Sciences and Ecology Websites...

75

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT  

Office of Legacy Management (LM)

PITTSBURGH PLANT FOREST HILLS PITTSBURGH, PENNSYLVANIA Department of Energy Office of Nuclear Energy Office of Remedial Action and Waste Technology Division of Facility and...

76

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT  

Office of Legacy Management (LM)

SYLVANIA-CORNING NUCLEAR CORPORATION BAYSIDE, NEW YORK VW. Department of Energy Office of Nuclear Energy Office of Remedial Action and Waste Technology Division of Facility and...

77

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT  

Office of Legacy Management (LM)

OF ARIZONA (U.S. BUREAU OF MINES) TUCSON, ARIZONA Department of Energy Office of Nuclear Energy Office of Remedial Action and Waste Technology Division of Facility and...

78

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program  

SciTech Connect (OSTI)

The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

Not Available

1991-09-01T23:59:59.000Z

79

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

SciTech Connect (OSTI)

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

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

1997-04-01T23:59:59.000Z

80

The American Board of Radiology Holman Research Pathway: 10-Year Retrospective Review of the Program and Participant Performance  

SciTech Connect (OSTI)

Introduction: In 1999, the American Board of Radiology (ABR) implemented an innovative training program track in diagnostic radiology (DR) and radiation oncology (RO) designed to stimulate development of a cadre of future academic researchers and educators in the 2 disciplines. The program was designated the Holman Research Pathway (HRP). An in-depth retrospective review of initial certification examination performance, post-training career choices, and academic productivity has not been written. This report represents a 10-year retrospective review of post-training performance of a cohort of trainees who have had sufficient time to complete their training and initial certification process and to enter practice. Methods and Materials: All pertinent proceedings of the ABR and Accreditation Council for Graduate Medical Education (ACGME) Residency Review Committees for DR and RO between 1997 and May 2011 were reviewed. Thirty-four HRP candidates who fulfilled the established evaluation criteria were identified, and their ABR data files were analyzed regarding performance on the qualifying and certifying examinations. All candidates were contacted directly to obtain a current curriculum vitae. Results: Twenty candidates in RO and 14 candidates in DR were identifiable for review. All candidates attained initial certification. At the time of analysis, 23 of 33 (66.6%) candidates were employed in full-time academic practice (1 DR candidate remained in a fellowship and was not evaluated regarding employment status). Fifteen of 20 (75%) RO candidates were in faculty positions compared with 7 of 13 (53.8%) DR trainees. Additional academic productivity metrics are reported. Conclusions: A high percentage of HRP trainees remained in academic practice and demonstrated significant academic productivity as measured by manuscript authorship and research support. Additional time and observation will be needed to determine whether these findings will be sustained by past, current, and future HRP trainees.

Wallner, Paul E., E-mail: pwallner@theabr.org [21st Century Oncology, LLC, Fort Myers, Florida, and American Board of Radiology, Tucson, Arizona (United States); Ang, K. Kian [University of Texas MD Anderson Cancer Center, Houston, Texas (United States)] [University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Zietman, Anthony L. [Harvard Medical School and Massachusetts General Hospital, Boston, Massachusetts (United States)] [Harvard Medical School and Massachusetts General Hospital, Boston, Massachusetts (United States); Harris, Jay R. [Harvard Medical School and Dana-Farber Cancer Institute, Boston, Massachusetts (United States)] [Harvard Medical School and Dana-Farber Cancer Institute, Boston, Massachusetts (United States); Ibbott, Geoffrey S. [University of Texas MD Anderson Cancer Center, Houston, Texas (United States)] [University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Mahoney, Mary C. [University of Cincinnati Medical Center, Cincinnati, Ohio (United States)] [University of Cincinnati Medical Center, Cincinnati, Ohio (United States); Mezwa, Duane G. [Oakland University William Beaumont School of Medicine, Royal Oaks, Michigan (United States)] [Oakland University William Beaumont School of Medicine, Royal Oaks, Michigan (United States); Wilson, Lynn D. [Yale University School of Medicine, New Haven, Connecticut (United States)] [Yale University School of Medicine, New Haven, Connecticut (United States); Becker, Gary J. [American Board of Radiology, Tucson, Arizona (United States)] [American Board of Radiology, Tucson, Arizona (United States)

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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.


81

Local action for the global environment : municipal government participation in a voluntary climate protection program  

E-Print Network [OSTI]

The Cities for Climate ProtectionTM (CCP) campaign is a voluntary environmental program for municipalities, which is increasingly being applied around the world by local governments taking action on climate change. This ...

Ravin, Amelia L., 1977-

2004-01-01T23:59:59.000Z

82

RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel  

SciTech Connect (OSTI)

This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows{trademark} environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident.

Yuan, Y.C. [Square Y Consultants, Orchard Park, NY (US); Chen, S.Y.; Biwer, B.M.; LePoire, D.J. [Argonne National Lab., IL (US)

1995-11-01T23:59:59.000Z

83

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

SciTech Connect (OSTI)

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

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

1995-09-01T23:59:59.000Z

84

EM International Program Action Table - June 2014 | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in Review: TopEnergy DOEDealingVehicle1:Energy Independence &December 11, 2014Action

85

action program revised: Topics by E-print Network  

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

First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Revision Programming CiteSeer Summary: In this paper...

86

EMSL - radiological  

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

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

87

Technology needs for environmental restoration remedial action. Environmental Restoration Program  

SciTech Connect (OSTI)

This report summarizes the current view of the most important technology needs for the US Department of Energy (DOE) facilities operated by Martin Marietta Energy Systems, Inc. These facilities are the Oak Ridge National Laboratory, the Oak Ridge K-25 Site, the Oak Ridge Y-12 Plant, the Paducah Gaseous Diffusion Plant, and the Portsmouth Gaseous Diffusion Plant. The sources of information used in this assessment were a survey of selected representatives of the Environmental Restoration (ER) programs at each facility, results from a questionnaire distributed by Geotech CWM, Inc., for DOE, and associated discussions with individuals from each facility. This is not a final assessment, but a brief look at an ongoing assessment; the needs will change as the plans for restoration change and, it is hoped, as some technical problems are solved through successful development programs.

Watson, J.S.

1992-11-01T23:59:59.000Z

88

Implementation of the Formerly Utilized Sites Remedial Action Program:  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartment of Energy MediaRequirementsto

89

Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation.

Not Available

1993-05-01T23:59:59.000Z

90

Uranium Mill Tailings remedial action project waste minimization and pollution prevention awareness program plan  

SciTech Connect (OSTI)

The purpose of this plan is to establish a waste minimization and pollution prevention awareness (WM/PPA) program for the U.S. Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The program satisfies DOE requirements mandated by DOE Order 5400.1. This plan establishes planning objectives and strategies for conserving resources and reducing the quantity and toxicity of wastes and other environmental releases.

Not Available

1994-07-01T23:59:59.000Z

91

DOE standard: Radiological control  

SciTech Connect (OSTI)

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

Not Available

1999-07-01T23:59:59.000Z

92

Radiological Protection for DOE Activities  

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

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

1995-09-29T23:59:59.000Z

93

New York state information handbook formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying our the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of New York. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

None

1980-12-31T23:59:59.000Z

94

New Mexico state information handbook: formerly utilized sites remedial action program  

SciTech Connect (OSTI)

This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of New Mexico. It contains a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

none,

2014-12-31T23:59:59.000Z

95

Groundwater protection management program plan. [Uranium Mill Tailings Remedial Action (UMTRA) Project  

SciTech Connect (OSTI)

US Department of Energy (DOE) Order 5400.1 requires the establishment of a groundwater protection management program to ensure compliance with DOE requirements and applicable Federal, state, and local laws and regulations. The Uranium Mill Tailings Remedial Action (UMTRA) Project Office has prepared a Groundwater Protection Management Program Plan'' (groundwater protection plan) of sufficient scope and detail to reflect the program's significance and address the seven activities required in DOE Order 5400.1, Chapter 3, for special program planning. The groundwater protection plan highlights the methods designed to preserve, protect, and monitor groundwater resources at UMTRA Project processing and disposal sites. The plan includes an overview of the remedial action status at the 24 designated processing sites and identifies project technical guidance documents and site-specific documents for the UMTRA groundwater protection management program. In addition, the groundwater protection plan addresses the general information required to develop a water resources protection strategy at the permanent disposal sites. Finally, the plan describes ongoing activities that are in various stages of development at UMTRA sites (long-term care at disposal sites and groundwater restoration at processing sites). This plan will be reviewed annually and updated every 3 years in accordance with DOE Order 5400.1.

Not Available

1992-06-01T23:59:59.000Z

96

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

SciTech Connect (OSTI)

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

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

1994-01-01T23:59:59.000Z

97

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

SciTech Connect (OSTI)

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

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

1995-07-01T23:59:59.000Z

98

Annual status report on the Uranium Mill Tailings Remedial Action Program  

SciTech Connect (OSTI)

This eleventh annual status report summarizes activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project undertaken during Fiscal Year (FY) 1989 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1990 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95--604. The DOE will continue to submit an annual report through project completion in order to inform the public of yearly project status. Title I of the UMTRCA authorizes the DOE, in cooperation with affected states and Indian tribes within whose boundaries designated uranium processing sites are located, to provide a program of assessment and remedial action at such sites. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive materials located on the inactive uranium processing sites in a safe and environmentally sound manner and to minimize or eliminate potential radiation health hazards. Commercial and residential properties in the vicinity of designated processing sites that are contaminated with material from the sites, herein referred to as vicinity properties,'' are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated vicinity properties located in 10 states, and the vicinity properties associated with Edgemont, South Dakota, an inactive uranium mill currently owned by the Tennessee Valley Authority (TVA).

Not Available

1989-12-01T23:59:59.000Z

99

Rev. 04/2014: JAB Environmental and Radiological Health Sciences  

E-Print Network [OSTI]

Rev. 04/2014: JAB Environmental and Radiological Health Sciences Academic Policies, Guidelines....................................................................................................................... 3 Plan A Master of Science Program......................................................................................... 3 Plan B Master of Science Program

100

Environmental compliance assessment findings for Weldon Spring Site Remedial Action Program  

SciTech Connect (OSTI)

This report presents the results of an environmental assessment conducted at Weldon Spring Site Remedial Action Project (WSSRAP) in St. Charles County, Missouri, in accordance with the Formerly Utilized Sites Remedial Action Program (FUSRAP) Environmental Compliance Assessment Checklists. The purpose of this assessment was to evaluate the compliance of the site with applicable federal and Missouri environment regulations. Assessments activities included the following: review of site records, reports ,and files; inspection of the WSSRAP storage building, other selected buildings, and the adjacent grounds; and interviews with project personnel. This assessment was conducted on August 28-30, 1989. The assessment covered five management areas as set forth in the Checklist: Hazardous Waste Management, Polychlorinated Biphenyls (PCBs) Management; Air Emissions; Wastewater Discharges and Petroleum Management. No samples were collected. 1 ref., 2 figs., 1 tab.

Sigmon, C.F.; Levine, M.B.

1990-03-02T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

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

SciTech Connect (OSTI)

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

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

1996-04-01T23:59:59.000Z

102

[Uranium Mill Tailings Remedial Action Project Office Quality Assurance Program Plan]. Revision 4  

SciTech Connect (OSTI)

The Uranium Mill Tailings Remedial Action (UMTRA) Project was established to accomplish remedial actions at inactive uranium mill tailings sites in accordance with Public Law 95-604, the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRA Project`s mission is to stabilize and control the residual radioactive materials at designated sites in a safe and environmentally sound manner so as to minimize or eliminate radiation health hazards to the public. The US Department of Energy (DOE) UMTRA Project Office (UMTRA PO) directs the overall project. Since these efforts may involve possible risks to public health and safety, a quality assurance (QA) program that conforms to the applicable criteria (set forth in the reference documents) has been established to control the quality of the work. This document, the Quality Assurance Program Plan (QAPP), brings into one document the essential criteria to be applied on a selective basis, depending upon the nature of the activity being conducted, and describes how those criteria shall be applied to the UMTRA Project. The UMTRA PO shall require each Project contractor to prepare and submit for approval a more detailed QAPP that is based on the applicable criteria of this QAPP and the referenced documents. All QAPPs on the UMTRA Project shall fit within the framework of this plan.

Not Available

1992-06-01T23:59:59.000Z

103

[Uranium Mill Tailings Remedial Action Project Office Quality Assurance Program Plan  

SciTech Connect (OSTI)

The Uranium Mill Tailings Remedial Action (UMTRA) Project was established to accomplish remedial actions at inactive uranium mill tailings sites in accordance with Public Law 95-604, the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRA Project's mission is to stabilize and control the residual radioactive materials at designated sites in a safe and environmentally sound manner so as to minimize or eliminate radiation health hazards to the public. The US Department of Energy (DOE) UMTRA Project Office (UMTRA PO) directs the overall project. Since these efforts may involve possible risks to public health and safety, a quality assurance (QA) program that conforms to the applicable criteria (set forth in the reference documents) has been established to control the quality of the work. This document, the Quality Assurance Program Plan (QAPP), brings into one document the essential criteria to be applied on a selective basis, depending upon the nature of the activity being conducted, and describes how those criteria shall be applied to the UMTRA Project. The UMTRA PO shall require each Project contractor to prepare and submit for approval a more detailed QAPP that is based on the applicable criteria of this QAPP and the referenced documents. All QAPPs on the UMTRA Project shall fit within the framework of this plan.

Not Available

1992-06-01T23:59:59.000Z

104

Women in pediatric radiology  

E-Print Network [OSTI]

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

Boechat, M. Ines

2010-01-01T23:59:59.000Z

105

Yakima Tributary Access and Habitat Program : Action Plan Final Report 2002.  

SciTech Connect (OSTI)

This report covers activities conducted by the Yakima Tributary Access and Habitat Program under Bonneville Power Administration (BPA) grant project No. 2002-025-00 for fiscal year 2002. The Yakima Tributary Access and Habitat Program (YTAHP, Program) was organized to restore salmonid passage to Yakima tributaries that historically supported salmonids and improve habitat in areas where access is restored. Specifically, this program is designed to (a) screen unscreened diversion structures to prevent fish entrainment into artificial waterways; (b) provide for fish passage at man-made barriers, such as diversion dams, culverts, siphons and bridges; and (c) provide information and assistance to landowners interested in to contributing to the improvement of water quality, water reliability and stream habitat. The YTAHP developed from a number of groups actively engaged in watershed management, and/or habitat restoration within the Yakima River Basin. These groups include the Washington State Fish and Wildlife (WDFW), Kittitas County Conservation District (KCCD), North Yakima Conservation District (NYCD), Kittitas County Water Purveyors (KCWP), and Ahtanum Irrigation District (AID). The US Bureau of Reclamation (Reclamation) and Yakama Nation (YN) both participated in the development of the objectives of YTAHP. Other entities that will be involved during permitting or project review may include the YN, the federal Natural Resources Conservation Service (NRCS), the US Fish and Wildlife Service (USFWS), the National Marine Fisheries Service (NMFS), and US Army Corps of Engineers (COE). Achievements of YTAHP with BPA Action Plan funding during FY 2002 were to: (1) Establish contracts with RC&D and YTAHP participants. (2) Determine contract mechanism for MWH engineering services. (3) Provide engineering designs and services for 11 early action projects, including inverted siphons, pump and gravity diversion screening, diversion metering, rock weirs for improved fish passage, headgates and fishways. These designs were used to submit for project implementation funding through the WA Salmon Recovery Funding Board. (4) Complete 6 early action projects on Ahtanum Creek--One gravity diversion was replaced with a pump and pump end screen and 5 pump end screens were installed. (5) Conduct two topographic surveys--For the City of Yakima on the Fruitvale diversion for the North Yakima Conservation District to support the installation of a pumping plant which would eliminate the need to divert directly from the Naches River and build the gravel berm each year during low flows. For the Taylor Ditch system for the North Yakima Conservation District to support as feasibility of opening the ditch for habitat and at the same time maintaining irrigation deliveries. (6) Procure materials for use in future YTAHP projects, including siphon pipe, delivery pipe, rock, screens, and water meters. These materials will act as match and support the completion of these subsequent YTAHP projects. Overall, with broad agency support and Action Plan funding through BPA, the YTAHP has achieved substantial enhancements that support aquatic species and which will leverage subsequent work through engineering designs and materials. The program was also able to establish the personnel and equipment support for beginning the stream assessment process on tributaries in Yakima and Kittitas Counties. Completion of this year's effort has provided significant inroads to working on the private lands in two counties which will be vital to future efforts by YTAHP and others to protect and enhance Yakima River Basin habitat.

Myra, David (South Central Washington Resource Conservation and Development Council, Ellensburg, WA); Ready, Carol A. (Kittitas County Water Purveyors, Ellensburg, WA)

2003-04-01T23:59:59.000Z

106

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

SciTech Connect (OSTI)

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

NONE

1997-11-01T23:59:59.000Z

107

Nevada Test Site Radiological Control Manual  

SciTech Connect (OSTI)

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

Radiological Control Managers' Council Nevada Test Site

2010-02-09T23:59:59.000Z

108

Nevada Test Site Radiological Control Manual  

SciTech Connect (OSTI)

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

Radiological Control Managers' Council - Nevada Test Site

2009-10-01T23:59:59.000Z

109

Management and overview Quality Assurance Program Plan. [Uranium Mill Tailings Remedial Action (UMTRA) Project  

SciTech Connect (OSTI)

The Uranium Mill Tailings Remedial Action (UMTRA) Project Office (DOE/ UMTRA-PO) is the US Department of Energy (DOE) Albuquerque Operations Office (AL) organization charged with the responsibility of managing and coordinating the activities of the various participating organizations and support contractors working on the UMTRA Project. This Quality Assurance Program Plan (QAPP) describes how the DOE/UMTRA-PO, as assisted by the Technical Assistance Contractor (TAC), performs the quality assurance (QA) aspects of managing and coordinating UMTRA Project activities. This QAPP was developed to comply with DOE Order 5700.6A, August, 1981, and AL Order 5700.6B, April, 1984, which contain the criteria applicable to Project QA activities.

Not Available

1986-08-01T23:59:59.000Z

110

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program  

SciTech Connect (OSTI)

This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

111

RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT  

E-Print Network [OSTI]

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

Holland, Jeffrey

112

US Department of Energy Radiological Control Manual  

SciTech Connect (OSTI)

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

Not Available

1992-06-01T23:59:59.000Z

113

US Department of Energy Radiological Control Manual  

SciTech Connect (OSTI)

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

Not Available

1992-06-01T23:59:59.000Z

114

Radiological Control Manual  

SciTech Connect (OSTI)

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

Not Available

1993-04-01T23:59:59.000Z

115

Radiological safety training for uranium facilities  

SciTech Connect (OSTI)

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

NONE

1998-02-01T23:59:59.000Z

116

HANFORD TANK FARM RESOURCE CONVERVATION & RECOVERY ACT (RCRA) CORRECTIVE ACTION PROGRAM  

SciTech Connect (OSTI)

As a consequence of producing special nuclear material for the nation's defense, large amounts of extremely hazardous radioactive waste was created at the US Department of Energy's (DOE) Hanford Site in south central Washington State. A little over 50 million gallons of this waste is now stored in 177 large, underground tanks on Hanford's Central Plateau in tank farms regulated under the Atomic Energy Act and the Resource, Conservation, and Recovery Act (RCRA). Over 60 tanks and associated infrastructure have released or are presumed to have released waste in the vadose zone. In 1998, DOE's Office of River Protection established the Hanford Tank Farm RCRA Corrective Action Program (RCAP) to: (1) characterize the distribution and extent of the existing vadose zone contamination; (2) determine how the contamination will move in the future; (3) estimate the impacts of this contamination on groundwater and other media; (4) develop and implement mitigative measures; and (5) develop corrective measures to be implemented as part of the final closure of the tank farm facilities. Since its creation, RCAP has made major advances in each of these areas, which will be discussed in this paper.

KRISTOFZSKI, J.G.

2007-01-15T23:59:59.000Z

117

E-FUSRAP: AUTOMATING THE CASE FILE FOR THE FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM  

SciTech Connect (OSTI)

The Department of Energy's (DOE) Office of Site Closure, EM-30, houses the document library pertaining to sites that are related to the Formerly Utilized Sites Remedial Action Program (FUSRAP) and regularly addresses ongoing information demands, primarily from Freedom of Information Act (FOIA) requests, interested members of the public, the DOE, and other Federal Agencies. To address these demands more efficiently, DOE has begun to implement a new multi-phase, information management process known as e-FUSRAP. The first phase of e-FUSRAP, the development of the Considered Sites Database, summarizes and allows public access to complex information on over 600 sites considered as candidates for FUSRAP. The second phase of e-FUSRAP, the development of the Document Indexing Database, will create an internal index of more than 10,000 documents in the FUSRAP library's case file, allowing more effective management and retrieval of case file documents. Together, the phases of e-FUSRAP will allow EM-30 to become an innovative leader in enhancing public information sources.

Mackenzie, D.; Marshall, K.

2003-02-27T23:59:59.000Z

118

Determination of ecologically vital groundwaters at selected sites in the Formerly Utilized Sites Remedial Action Program  

SciTech Connect (OSTI)

The US Department of Energy is classifying groundwaters at sites in its Formerly Utilized Sites Remedial Action Program (FUSRAP). Of particular concern is the potential presence of groundwaters that are highly vulnerable to contamination and that are either (1) irreplaceable sources of drinking water or (2) ecologically vital. Conditions at nine FUSRAP sites were evaluated to determine if ecologically vital groundwaters are present. The sites evaluated were Wayne Interim Storage Site, Maywood Interim Storage Site, and Middlesex Sampling Plant in New Jersey; Ashland 2 Site, Seaway Industrial Park, Colonie Interim storage Site, and Niagara Falls Storage Site in New York; and the St. Louis Airport Site and Hazelwood Interim Storage Site in Missouri. The analyses indicated that groundwaters are vulnerable to contamination at all but two of the sites -- the Ashland 2 and Seaway Industrial Park sites in New York. Groundwater discharge points were identified within a 2-mile radius (i.e., the classification review area) of all of the sites. No ecologically vital groundwater areas exist in the vicinities of any of the nine FUSRAP sites evaluated. 35 refs., 17 figs.

Vinikour, W.S.; Yin, S.C.L.

1989-08-01T23:59:59.000Z

119

Formerly utilized MED/AEC sites Remedial Action Program. Report of the decontamination of Jones Chemical Laboratory, Ryerson Physical Laboratory, and Eckhart Hall, the University of Chicago, Chicago, Illinois  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has implemented a program to decontaminate radioactively contaminated sites that were formerly utilized by the Manhattan Engineer District (MED) and/or the Atomic Energy Commission (AEC) for activities that included handling of radioactive material. This program is referred to as the ''Formerly Utilized Sites Remedial Action Program'' (FUSRAP). Among these sites are Jones Chemical Laboratory, Ryerson Physical Laboratory, Kent Chemical Laboratory, and Eckhart Hall of The University of Chicago, Chicago, Illinois. Since 1977, the University of Chicago decontaminated Kent Chemical Laboratory as part of a facilities renovation program. All areas of Eckhart Hall, Ryerson Physical Laboratory, and Jones Chemical Laboratory that had been identified as contaminated in excess of current guidelines in the 1976-1977 surveys were decontaminated to levels where no contamination could be detected relative to natural backgrounds. All areas that required defacing to achieve this goal were restored to their original condition. The radiological evaluation of the sewer system, based primarily on the radiochemical analyses of sludge and water samples, indicated that the entire sewer system is potentially contaminated. While this evaluation was defined as part of this project, the decontamination of the sewer system was not included in the purview of this effort. The documentation included in this report substantiates the judgment that all contaminated areas identified in the earlier reports in the three structures included in the decontamination effort (Eckhart Hall, Ryerson Physical Laboratory, and Jones Chemical Laboratory) were cleaned to levels commensurate with release for unrestricted use.

Wynuveen, R.A.; Smith, W.H.; Sholeen, C.M.; Flynn, K.F.

1984-08-01T23:59:59.000Z

120

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

SciTech Connect (OSTI)

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

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

1995-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

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

SciTech Connect (OSTI)

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

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

1995-05-01T23:59:59.000Z

122

Rev. 10/24/2014 -JAB Environmental and Radiological Health Sciences  

E-Print Network [OSTI]

Rev. 10/24/2014 - JAB Environmental and Radiological Health Sciences Academic Policies, Guidelines....................................................................................................................... 3 Plan A Master of Science Program......................................................................................... 3 Plan B Master of Science Program

123

Environmental audit of the Maywood Site: Formerly Utilized Sites Remedial Action Program, Maywood Interim Storage Site vicinity properties  

SciTech Connect (OSTI)

This report presents the results of the Environmental Audit of the Maywood Site managed by the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Audit was carried out from November 7 through 16, 1990. The Audit Team found overall technical competence and knowledge of management and staff to be excellent. This applies to DOE as well as to Bechtel National, Incorporated (BNI). In particular, there was excellent knowledge of federal, state, and local environmental regulations, as well as analysis for applicability of these regulations to FUSRAP. Project management of the Maywood Site is also excellent. BNI and DOE project staff have made frequent contact with members of the community, and all removal actions and remedial investigation activities have been planned, scheduled, and accomplished with competence and attention to total quality principles. To date, all actions taken for the Maywood Site cleanup have been completed ahead of schedule and on or under budget. Weakness noted include self-assessment efforts by DOE, failure to fully implement DOE Order requirements throughout the program, and some discrepancies in formally documenting and reviewing procedures. 7 figs., 10 tabs.

Not Available

1990-12-01T23:59:59.000Z

124

Transcript of See Action and Technical Assistance Program Webcast: Energy Audit and Retro-Commissioning Policies for Public and Commercial Buildings  

Broader source: Energy.gov [DOE]

U.S. Department of Energy Office (DOE) of Energy Efficiency and Renewable Energy (EERE) transcript of See Action and Technical Assistance Program Webcast: Energy Audit and Retro-Commissioning Policies for Public and Commercial Buildings.

125

UCF-3.001 Non-Discrimination; Affirmative Action Programs. (1) The University shall actively promote equal opportunity policies and practices  

E-Print Network [OSTI]

UCF-3.001 Non-Discrimination; Affirmative Action Programs. (1) The University shall actively, the military, ROTC, and private employers, only to the extent of state and federal requirements. (2 is defined as taking an adverse action against an individual because that individual, in good faith: (i

Wu, Shin-Tson

126

Annual status report on the Uranium Mill Tailings Remedial Action Program  

SciTech Connect (OSTI)

This fourteenth annual status report for the Uranium Mill Tailings Remedial Action (UMTRA) Project Office summarizes activities of the Uranium Mill Tailings Remedial Action Surface (UMTRA-Surface) and Uranium Mill Tailings Remedial Action Groundwater (UMTRA-Groundwater) Projects undertaken during fiscal year (FY) 1992 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1993 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604. The DOE will continue to submit annual reports to DOE-Headquarters, the states, tribes, and local representatives through Project completion in order to inform the public of the yearly Project status. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive material (RRM) located on the inactive uranium processing sites in a safe and environmentally sound manner, and to minimize or eliminate potential health hazards. Commercial and residential properties near designated processing sites that are contaminated with material from the sites, herein referred to as ``vicinity properties (VP),`` are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated VPs located in 10 states, and the VPs associated with the Edgemont, South Dakota, uranium mill currently owned by the Tennessee Valley Authority (TVA) (Figure A.1, Appendix A).

Not Available

1992-12-01T23:59:59.000Z

127

Follow-up inspection of the Formerly Utilized Sites Remedial-Action Program  

SciTech Connect (OSTI)

Corrective actions had been taken in four of the six areas of concern that were addressed in the 1982 report. The remaining two areas are summarized as follows: Certification of Remedial Actions. We found, in the initial inspection, that FUSRAP properties were not being certified as decontaminated in a timely manner following remedial action. This problem has not yet been resolved. The Assistant Secretary for Nuclear Energy acknowledged that the certification process is lengthy but maintained that progress was being made. The Assistant Secretary stated that attempts will be made to speed up the process; and Permanent Waste Disposal. The lack of permanent repositories for FUSRAP wastes continues to be a major issue. The Assistant Secretary for Nuclear Energy indicated to us that meetings are being held with state and congressional representatives to impress on them the need for locating disposal sites for FUSRAP wastes in their states.

Not Available

1983-10-19T23:59:59.000Z

128

Funding Opportunity Announcement State Energy Program (SEP) Strengthening Building Retrofit Markets and Stimulating Energy Efficiency Action  

Broader source: Energy.gov [DOE]

The Department of Energy (DOE) National Energy Technology Laboratory (NETL), on behalf of the Office of Energy Efficiency and Renewable Energys (EEREs) State Energy Program (SEP), is seeking applications to advance policies, programs, and market strategies that accelerate job creation and reduce energy bills while achieving energy and climate security for the nation.

129

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

130

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

131

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

132

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

SciTech Connect (OSTI)

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

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

1992-07-01T23:59:59.000Z

133

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

SciTech Connect (OSTI)

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

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

1992-07-01T23:59:59.000Z

134

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

135

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

136

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

137

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

138

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

139

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

SciTech Connect (OSTI)

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

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

1992-07-01T23:59:59.000Z

140

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

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


141

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

142

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

143

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

SciTech Connect (OSTI)

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

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

1992-05-01T23:59:59.000Z

144

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

SciTech Connect (OSTI)

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

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

1992-07-01T23:59:59.000Z

145

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

SciTech Connect (OSTI)

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

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

1992-07-01T23:59:59.000Z

146

Viewing biology in action | EMSL  

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

Viewing biology in action Viewing biology in action DOE-funded pilot program will create mesoscale biological imaging platform James Evans EMSL received first-year funding of...

147

U.S. EPA State Clean Energy and Climate Program (2009). Clean Energy Lead by Example Guide: Strategies, Resources, and Action Steps for State Programs.  

E-Print Network [OSTI]

State governments can achieve substantial energy cost savings across their facilities, operations, and fleets through clean energy Lead by Example (LBE) programs. They can also demonstrate energy and environmental leadership, raise public awareness of the benefits of clean energy technologies, improve air quality, reduce greenhouse gas (GHG) emissions, improve energy supply and reliability, and foster markets for environmentally preferable products. The LBE Guide provides information to assist state governments as they develop and implement effective LBE programs to achieve their clean energy goals. It presents strategies, resources, and tools state decision makers can use throughout the process. EPA and other organizations recognize leading by example as a key policy option for states seeking to achieve their clean energy goals. For example, the importance of LBE programs is documented in the the National Action Plan for Energy Efficiency Vision for 2025 report. The Vision identifies LBE as a critical component of achieving the long-term goal of all cost-effective energy efficiency by 2025. Goal Six of the Visions ten implementation goals is to develop state policies such as LBE for pursuing robust energy efficiency practices. DocUmEnt maP ChAPtER onE introduction ChAPtER two Potential lBE activities and measures ChAPtER thREE

Prepared Joanna Pratt; Joe Donahue; Niko Dietsch

148

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

SciTech Connect (OSTI)

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

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

1994-05-01T23:59:59.000Z

149

Geothermal Program Review XII: proceedings. Geothermal Energy and the President's Climate Change Action Plan  

SciTech Connect (OSTI)

Geothermal Program Review XII, sponsored by the Geothermal Division of US Department of Energy, was held April 25--28, 1994, in San Francisco, California. This annual conference is designed to promote effective technology transfer by bringing together DOE-sponsored researchers; utility representatives; geothermal energy developers; suppliers of geothermal goods and services; representatives from federal, state, and local agencies; and others with an interest in geothermal energy. In-depth reviews of the latest technological advancements and research results are presented during the conference with emphasis on those topics considered to have the greatest potential to impact the near-term commercial development of geothermal energy.

Not Available

1994-12-31T23:59:59.000Z

150

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

SciTech Connect (OSTI)

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

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

1997-09-01T23:59:59.000Z

151

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

SciTech Connect (OSTI)

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

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

1997-09-01T23:59:59.000Z

152

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

SciTech Connect (OSTI)

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

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

1997-09-01T23:59:59.000Z

153

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

SciTech Connect (OSTI)

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

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

1997-09-01T23:59:59.000Z

154

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

SciTech Connect (OSTI)

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

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

1996-06-01T23:59:59.000Z

155

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

156

St. Louis Airport Site. Annual site environmental report, calendar year 1985. Formerly Utilized Sites Remedial Action Program (FUSRAP). Revision 1  

SciTech Connect (OSTI)

During 1985, the environmental monitoring program was continued at the St. Louis Airport Site (SLAPS) in St. Louis County, Missouri. The ditches north and south of the site have been designated for cleanup as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). The monitoring program at the SLAPS measures radon gas concentrations in air; external gamma radiation dose rates; and uranium, thorium, and radium concentrations in surface water, groundwater, and sediment. Potential radiation doses to the public are also calculated. Because the site is not controlled or regulated by the DOE, the DOE Derived Concentration Guides (DCGs) are not applicable to SLAPS, but are included only as a basis for comparison. The DOE DCGs and the DOE radiation protection standard have been revised. (Appendix B). During 1985, annual average radon levels in air at the SLAPS were below the DCG for uncontrolled areas. External gamma monitoring in 1985 showed measured annual gamma dose rates ranging from 3 to 2087 mrem/y, with the highest value occurring in an area known to be contaminated. The calculated maximum dose at the site boundary, assuming limited occupancy, would be 6 mrem/y. Average annual concentrations of /sup 230/Th, /sup 226/Ra, and total uranium in surface waters remained below the DOE DCG. The on-site groundwater measurements showed that average annual concentrations of /sup 230/Th, /sup 226/Ra and total uranium were within the DOE DCGs. Although there are no DCGs for sediments, all concentrations of total uraniu, /sup 230/Th, and /sup 226/Ra were below the FUSRAP Guidelines.

Not Available

1986-09-01T23:59:59.000Z

157

Remedial action work plan for the Colonie site. Revision 1  

SciTech Connect (OSTI)

The Colonie site is a DOE Formerly Utilized Sites Remedial Action Program (FUSRAP) site located in the Town of Colonie, New York, and consisting of an interim storage site and several vicinity properties. The Colonie Interim Storage Site (CISS) is the former National Lead (NL) Industries plant located at 1130 Central Avenue. There are 11 vicinity properties that received remedial action in 1984: 7 located south of the site on Yardboro and Palmer Avenues just across the Colonie-Albany town limits in Albany, and 4 located northwest of the site along Central Avenue in Colonie. Of these properties, nine are residences and two are commercial properties. This document describes the engineering design, construction, and associated plans for remedial action on the vicinity properties and the interim storage site. These plans include both radiological and chemical work. Radiological work includes: excavating the above-guideline radioactive wastes on the vicinity properties; designing required facilities for the interim storage site; preparing the interim storage site to receive these contaminated materials; transporting the contaminated materials to the interim waste storage stockpile; and preparing necessary schedules for accomplishing the remedial actions. Chemical work involves: developing the Resource Conservation and Recovery Act (RCRA) closure plans; neutralizing chemical hazards associated with plating solutions; inventorying on-site chemicals; and disposal of chemicals and/or residues. 17 refs., 5 figs., 1 tab.

Not Available

1985-08-01T23:59:59.000Z

158

Radiological worker training  

SciTech Connect (OSTI)

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

NONE

1998-10-01T23:59:59.000Z

159

324 Building Baseline Radiological Characterization  

SciTech Connect (OSTI)

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

R.J. Reeder, J.C. Cooper

2010-06-24T23:59:59.000Z

160

Radiological standards and calibration laboratory capabilities  

SciTech Connect (OSTI)

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

Goles, R.W.

1995-01-01T23:59:59.000Z

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


161

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

SciTech Connect (OSTI)

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

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

1989-05-01T23:59:59.000Z

162

Radiology of thoracic diseases  

SciTech Connect (OSTI)

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

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

1989-01-01T23:59:59.000Z

163

NV/YMP RADIOLOGICAL CONTROL MANUAL  

SciTech Connect (OSTI)

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

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

2004-11-01T23:59:59.000Z

164

EA-1919: Recycle of Scrap Metals Originating from Radiological Areas  

Broader source: Energy.gov [DOE]

This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.)

165

Colonie Interim Storage Site: Annual site environmental report, Colonie, New York, Calendar year 1986: Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

During 1986, the environmental monitoring program continued at the Colonie Interim Storage Site (CISS), a US Department of Energy (DOE) facility located in Colonie, New York. The CISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has mandated DOE to remedy. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action is being conducted at the site and at vicinity properties by Bechtel National Inc. (BNI), Project Management Contractor for FUSRAP. The environmental monitoring program is also carried out by BNI. The monitoring program at the CISS measures external gamma radiation levels as well as uranium and radium-226 concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess the potential effect of the site on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, the maximally exposed individual would receive an annual external exposure approximately equivalent to 5% of the DOE radiation protection standard of 100 mrem/y. Results of 1986 monitoring show that the CISS is in compliance with the DOE radiation protection standard. 14 refs., 9 figs., 9 tabs.

Not Available

1987-06-01T23:59:59.000Z

166

Hanford Radiological Protection Support Services Annual Report for 2000  

SciTech Connect (OSTI)

During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.

Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A.; Piper, Roman K.

2001-05-07T23:59:59.000Z

167

Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement  

SciTech Connect (OSTI)

Missions that the Radiological Laboratory, utility, Office Building (RLUOB) supports are: (1) Nuclear Materials Handling, Processing, and Fabrication; (2) Stockpile Management; (3) Materials and Manufacturing Technologies; (4) Nonproliferation Programs; (5) Waste Management Activities - Environmental Programs; and (6) Materials Disposition. The key capabilities are actinide analytical chemistry and material characterization.

Seguin, Nicole R. [Los Alamos National Laboratory

2012-07-18T23:59:59.000Z

168

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

SciTech Connect (OSTI)

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

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

1997-09-01T23:59:59.000Z

169

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program  

SciTech Connect (OSTI)

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

170

Nuclear & Radiological Activity Center (NRAC)  

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

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

171

Nevada National Security Site Radiological Control Manual  

SciTech Connect (OSTI)

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

Radiological Control Managers Council

2012-03-26T23:59:59.000Z

172

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

173

Radiological Control Technician Training  

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

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

174

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

SciTech Connect (OSTI)

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

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

1992-07-01T23:59:59.000Z

175

Pacific Northwest National Laboratory Potential Impact Categories for Radiological Air Emission Monitoring  

SciTech Connect (OSTI)

In 2002, the EPA amended 40 CFR 61 Subpart H and 40 CFR 61 Appendix B Method 114 to include requirements from ANSI/HPS N13.1-1999 Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stack and Ducts of Nuclear Facilities for major emission points. Additionally, the WDOH amended the Washington Administrative Code (WAC) 246-247 Radiation protection-air emissions to include ANSI/HPS N13.1-1999 requirements for major and minor emission points when new permitting actions are approved. A result of the amended regulations is the requirement to prepare a written technical basis for the radiological air emission sampling and monitoring program. A key component of the technical basis is the Potential Impact Category (PIC) assigned to an emission point. This paper discusses the PIC assignments for the Pacific Northwest National Laboratory (PNNL) Integrated Laboratory emission units; this revision includes five PIC categories.

Ballinger, Marcel Y.; Gervais, Todd L.; Barnett, J. M.

2012-06-05T23:59:59.000Z

176

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

SciTech Connect (OSTI)

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

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

1986-11-01T23:59:59.000Z

177

Nuclear and Radiological Forensics and Attribution Overview  

SciTech Connect (OSTI)

The goal of the U.S. Department of Homeland Security (DHS) Nuclear and Radiological Forensics and Attribution Program is to develop the technical capability for the nation to rapidly, accurately, and credibly attribute the origins and pathways of interdicted or collected materials, intact nuclear devices, and radiological dispersal devices. A robust attribution capability contributes to threat assessment, prevention, and deterrence of nuclear terrorism; it also supports the Federal Bureau of Investigation (FBI) in its investigative mission to prevent and respond to nuclear terrorism. Development of the capability involves two major elements: (1) the ability to collect evidence and make forensic measurements, and (2) the ability to interpret the forensic data. The Program leverages the existing capability throughout the U.S. Department of Energy (DOE) national laboratory complex in a way that meets the requirements of the FBI and other government users. At the same time the capability is being developed, the Program also conducts investigations for a variety of sponsors using the current capability. The combination of operations and R&D in one program helps to ensure a strong linkage between the needs of the user community and the scientific development.

Smith, D K; Niemeyer, S

2005-11-04T23:59:59.000Z

178

Colonie Interim Storage Site environmental report for calendar year 1992, 1130 Central Avenue, Colonie, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

This report describes the environmental surveillance program at the Colonie Interim Storage Site (CISS) and provides the results for 1992. The site is located in eastern New York State, approximately 6.4 km (4.0 mi) northwest of downtown Albany. From 1958 to 1984, National Lead (NL) Industries used the facility to manufacture various components from depleted and enriched uranium natural thorium. Environmental monitoring of CISS began in 1984 when Congress added, the site to the US Department of Energy`s (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental surveillance program at CISS includes sampling networks for external gamma radiation exposure and for thorium-232 and total uranium concentrations in surface water, sediment, and groundwater. Several chemical parameters are also measured in groundwater, including total metals, volatile organics, and water quality parameters. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements.

Not Available

1993-05-01T23:59:59.000Z

179

Radiological Work Planning and Procedures  

E-Print Network [OSTI]

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

Kurtz, J E

2000-01-01T23:59:59.000Z

180

Radiological Release Accident Investigation Report - Phase 1...  

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

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

Note: This page contains sample records for the topic "action program radiological" 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

Standardized radiological dose evaluations  

SciTech Connect (OSTI)

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

Peterson, V.L.; Stahlnecker, E.

1996-05-01T23:59:59.000Z

182

April 2007 Standards Actions  

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

and Injury Surveillance Program Guidelines, 03222007; DOE-STD-1190-2007, OCSH-0005 2.0 Non-Government Standards Actions 2.1 American National Standards Institute (ANSI)...

183

Energy Action Month  

Broader source: Energy.gov [DOE]

The Federal Energy Management Program (FEMP) supports Energy Action Month by offering materials that promote energy- and water-saving practices in Federal facilities. This year's outreach materials call on Federal employees to take action and empower leadership, innovation, and excellence to realize a secure energy future.

184

Radiological Threat Reduction | ornl.gov  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, and 323Program AccomplishmentsScienceRadiological

185

Radiological Assessment System for Consequence Analysis (RASCAL) Version 3.0  

SciTech Connect (OSTI)

The Radiological Assessment System for Consequence AnaLysis, Version 3.0 (RASCAL 3.0) is the U.S. Nuclear Regulatory Commission?s (NRC) main computational tool for use during radiological emergencies. RASCAL estimates doses from radiological accidents for comparison with Protective Action Guides and acute health effects thresholds. It includes six computational tools: ST-Dose, FM-Dose, Decay, BackCalc, UF6Plume, and MetProc. ST-Dose computes time-dependent nuclide release rates, atmospheric transport, radiological decay, and doses. FM-Dose computes doses from environmental concentrations of nuclides. Decay computes radiological decay and daughter in-growth. BackCalc estimates a distribution of possible release rates from field measurements. UF6Plume computes uranium exposures and HF concentrations from a UF6 release. MetProc prepares meteorological data for use by ST-Dose and UF6Plume.

Athey, G.F.; Fosmire, C.; Mohseni, A.; Ramsdell, J.V., Jr.; Sjoreen, A.

1999-09-13T23:59:59.000Z

186

Middlesex Sampling Plant environmental report for calendar year 1992, 239 Mountain Avenue, Middlesex, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

This report describes the environmental surveillance program at the Middlesex Sampling Plant (MSP) and provides the results for 1992. The site, in the Borough of Middlesex, New Jersey, is a fenced area and includes four buildings and two storage piles that contain 50,800 m{sup 3} of radioactive and mixed hazardous waste. More than 70 percent of the MSP site is paved with asphalt. The MSP facility was established in 1943 by the Manhattan Engineer District (MED) to sample, store, and/or ship uranium, thorium, and beryllium ores. In 1955 the Atomic Energy Commission (AEC), successor to MED, terminated the operation and later used the site for storage and limited sampling of thorium residues. In 1967 AEC activities ceased, onsite structures were decontaminated, and the site was certified for unrestricted use under criteria applicable at that time. In 1980 the US Department of Energy (DOE) initiated a multiphase remedial action project to clean up several vicinity properties onto which contamination from the plant had migrated. Material from these properties was consolidated into the storage piles onsite. Environmental surveillance of MSP began in 1980 when Congress added the site to DOE`s Formerly Utilized Sites Remedial Action Program. The environmental surveillance program at MSP includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-230, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analyses are performed to detect metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling th DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses.

Not Available

1993-05-01T23:59:59.000Z

187

US Department of Energy radiological control manual. Revision 1  

SciTech Connect (OSTI)

This manual establishes practices for the conduct of Department of Energy radiological control activities. The Manual states DOE`s positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. This Manual is not a substitute for Regulations; it is intended to be consistent with all relevant statutory and regulatory requirements and shall be revised whenever necessary to ensure such consistency. Some of the Manual provisions, however, challenge the user to go well beyond minimum requirements. Following the course of action delineated in the Manual will result in achieving and surpassing related statutory or regulatory requirements.

Not Available

1994-04-01T23:59:59.000Z

188

Stanford Radiology LPCH Fast Pediatric MRI  

E-Print Network [OSTI]

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

California at Berkeley, University of

189

Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards.

Not Available

1993-05-01T23:59:59.000Z

190

Radiological Control Manual. Revision 0, January 1993  

SciTech Connect (OSTI)

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

Not Available

1993-04-01T23:59:59.000Z

191

Radiation Shielding and Radiological Protection  

E-Print Network [OSTI]

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

Shultis, J. Kenneth

192

Radiological Emergency Response Plan (Vermont)  

Broader source: Energy.gov [DOE]

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

193

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

E-Print Network [OSTI]

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

Blankinship, David Randle

1993-01-01T23:59:59.000Z

194

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

SciTech Connect (OSTI)

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

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

1995-11-01T23:59:59.000Z

195

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

NM; RAP Region 4 Chicago, IL; RAP Region 5 Idaho Falls, ID; RAP Region 6 Oakland, CA; RAP Region 7 Richland, WA; RAP Region 8 RAP team members surveying vehicles Each region...

196

Radiological Assistance Program | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar HomePromising Science for1 20115,PerformanceUsing

197

Radiological Control Programs for Special Tritium Compounds  

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

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

198

Radiological Control Programs for Special Tritium Compounds  

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

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

199

Hanford radiological protection support services annual report for 1988  

SciTech Connect (OSTI)

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

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

1989-06-01T23:59:59.000Z

200

Corrective Action  

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

Corrective Action Individual Permit: Corrective Action Certifications If confirmation monitoring sample results demonstrate that one or more TALs are exceeded at a Site, the...

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


201

Southwest Michigan Community Action Agency … Weatherization Assistance Program Funds Provided by the American Recovery and Reinvestment Act of 2009  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists' Research |RegulationRenewable EnergySouthwest Michigan Community Action Agency -

202

Needed improvements in the development of systemic corrective actions.  

SciTech Connect (OSTI)

There are indications that corrective actions, as implemented at Sandia National Laboratories are not fully adequate. Review of independent audits spanning multiple years provides evidence of recurring issues within the same or similar operations and programs. Several external audits have directly called into question the ability Sandia's assessment and evaluation processes to prevent recurrence. Examples of repeated findings include lockout/tagout programs, local exhaust ventilation controls and radiological controls. Recurrence clearly shows that there are underlying systemic factors that are not being adequately addressed by corrective actions stemming from causal analyses. Information suggests that improvements in the conduct of causal analyses and, more importantly, in the development of subsequent corrective actions are warranted. Current methodolgies include Management Oversight Risk Tree, developed in the early 1970s and Systemic Factors Analysis. Recommendations for improvements include review of other causal analysis systems, training, improved formality of operations, improved documentation, and a corporate method that uses truly systemic solutions. This report was written some years ago and is being published now to form the foundation for current, follow-on reports being developed. Some outdated material is recognized but is retained for report completeness.

Campisi, John A.

2009-07-01T23:59:59.000Z

203

Uncertainty analyses for radiological assessments of St. Louis FUSRAP Sites  

SciTech Connect (OSTI)

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

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

1996-06-01T23:59:59.000Z

204

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

Energy Savers [EERE]

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

205

SAVEnergy Action Plans  

SciTech Connect (OSTI)

The Department of Energy`s Federal Energy Management Program (FEMP) is charged with carrying out key sections of EPACT and Executive Order 12903, to make the Federal government operate more efficiently. A congressionally mandated energy and water conservation audit program is one component of this growing DOE program. This paper traces the SAVEnergy Action Plan program throughout its development from (1) identifying projects and Agency champions, (2) establishing a protocol and fitting auditors into the program, (3) developing a data base to track the audits and measure their success, and (4) evaluating the process, learning from mistakes, and charting and transferring successes. A major tenet of the SAVEnergy program is to proactively prescreen all audit activities to ensure that -- where audits are done and Action Plans completed -- projects will be done.

Mayo, K.; Westby, R. [National Renewable Energy Lab., Golden, CO (United States)] [National Renewable Energy Lab., Golden, CO (United States); deMonsabert, S. [George Mason Univ., Fairfax, VA (United States)] [George Mason Univ., Fairfax, VA (United States); Ginsberg, M. [USDOE, Washington, DC (United States)] [USDOE, Washington, DC (United States)

1994-04-01T23:59:59.000Z

206

Fall Protection Procedures for Sealing Bulk Waste Shipments by Rail Cars at Formerly Utilized Sites Remedial Action Program (FUSRAP) Sites - 13509  

SciTech Connect (OSTI)

Rail-cars loaded with radioactive materials must be closed and fastened to comply with United States Department of Transportation (DOT) requirements before they shipped. Securing waste shipments in a manner that meets these regulations typically results in the use of a sealable rail-car liner. Workers accessing the tops of the 2.74 m high rail-cars to seal and inspect liners for compliance prior to shipment may be exposed to a fall hazard. Relatively recent revisions to the Fall Protection requirements in the Safety and Health Requirements Manual (EM385-1-1, U.S. Army Corps of Engineers) have necessitated modifications to the fall protection systems previously employed for rail-car loading at Formerly Utilized Sites Remedial Action Program (FUSRAP) sites. In response these projects have developed site-specific procedures to protect workers and maintain compliance with the improved fall protection regulations. (authors)

Boyle, J.D. [U.S. Army Corps of Engineers - Buffalo District, Buffalo, New York 14207 (United States)] [U.S. Army Corps of Engineers - Buffalo District, Buffalo, New York 14207 (United States); Fort, E. Joseph; Lorenz, William [Cabrera Services (Cabrera) East Harford, CT 06108 (United States)] [Cabrera Services (Cabrera) East Harford, CT 06108 (United States); Mills, Andy [Shaw Environmental and Infrastructure, Inc. (Shaw) Baton Rouge, LA 70809 (United States)] [Shaw Environmental and Infrastructure, Inc. (Shaw) Baton Rouge, LA 70809 (United States)

2013-07-01T23:59:59.000Z

207

Radiological Work Planning and Procedure  

SciTech Connect (OSTI)

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

KURTZ, J.E.

2000-01-01T23:59:59.000Z

208

Radiological control manual. Revision 1  

SciTech Connect (OSTI)

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

Kloepping, R.

1996-05-01T23:59:59.000Z

209

Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit 106 comprises the four corrective action sites (CASs) listed below: 05-20-02, Evaporation Pond 05-23-05, Atmospheric Test Site - Able 05-45-04, 306 GZ Rad Contaminated Area 05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from groundwater pumping during the Radionuclide Migration study program (CAS 05-20-02), a weapons-related airdrop test (CAS 05-23-05), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). The presence and nature of contamination from surface-deposited radiological contamination from CAS 05-23-05, Atmospheric Test Site - Able, and other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) from the remaining three CASs will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 106 includes the following activities: Conduct radiological surveys. Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where the total effective dose at the site exceeds final action levels (i.e., corrective action boundary). Collect samples of investigation-derived waste, as needed, for waste management purposes.

Patrick Matthews

2011-07-01T23:59:59.000Z

210

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

SciTech Connect (OSTI)

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

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

1992-03-01T23:59:59.000Z

211

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

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

212

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Tuba City, Arizona. [Uranium Mill Tailings Remedial Action (UMTRA) Project  

SciTech Connect (OSTI)

This appendix assesses the present conditions and data for the inactive uranium mill site near Tuba City, Arizona. It consolidates available engineering, radiological, geotechnical, hydrological, meterological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill and tailings site so that the Remedial Action Contractor (RAC) may complete final designs of the remedial actions.

Not Available

1987-05-01T23:59:59.000Z

213

Hanford Radiological Protection Support Services annual report for 1993  

SciTech Connect (OSTI)

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

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

1994-07-01T23:59:59.000Z

214

Hanford Radiological Protection Support Services annual report for 1992  

SciTech Connect (OSTI)

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

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

1993-07-01T23:59:59.000Z

215

Hanford radiological protection support services annual report for 1997  

SciTech Connect (OSTI)

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

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

1998-06-01T23:59:59.000Z

216

Hanford radiological protection support services. Annual report for 1995  

SciTech Connect (OSTI)

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

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

1996-05-01T23:59:59.000Z

217

Hanford radiological protection support services annual report for 1996  

SciTech Connect (OSTI)

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

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

1997-06-01T23:59:59.000Z

218

Hanford radiological protection support services annual report for 1994  

SciTech Connect (OSTI)

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

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

1995-06-01T23:59:59.000Z

219

Best practice techniques for environmental radiological monitoring  

E-Print Network [OSTI]

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

220

International Data on Radiological Sources  

SciTech Connect (OSTI)

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

Martha Finck; Margaret Goldberg

2010-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

Departmental Radiological Emergency Response Assets  

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

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

2007-06-27T23:59:59.000Z

222

5 Putting Science into Action on Forest  

E-Print Network [OSTI]

5 Putting Science into Action on Forest Service Lands William M. Block u.s. Forest Service, Rocky into Action on Forest Service Lands t':: Research and Development, National Forest Systems, State and Private Forestry, International Programs

223

Understanding Mechanisms of Radiological Contamination  

SciTech Connect (OSTI)

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

Rick Demmer; John Drake; Ryan James, PhD

2014-03-01T23:59:59.000Z

224

Hanford radiological protection support services annual report for 1990  

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

225

Hanford radiological protection support services annual report for 1989  

SciTech Connect (OSTI)

Certain sitewide radiation protection services operated by Pacific Northwest Laboratory for the US Department of Energy-Richland Operations office and Hanford contractor are documented in this annual report on these services provided during calendar year 1989. These activities include internal dosimetry, in vivo measurements, external dosimetry, instrument calibration and evaluation, radiation source calibration, and radiological records keeping. In each case the routine program, program changes, associated tasks, investigations, and studies, as well as related publications, presentations, and other professional activities are discussed as applicable. 26 refs., 19 figs., 18 tabs.

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

1990-07-01T23:59:59.000Z

226

STUDENT DISCIPLINARY ACTION FORM INSTRUCTIONS  

E-Print Network [OSTI]

STUDENT DISCIPLINARY ACTION FORM INSTRUCTIONS Labor Program Office Berea College While one across campus. The "Student Disciplinary Action Form" was designed to provide labor supervisors directly with the student and discuss the matter in private. Calmly discuss the offense and the corrective

Baltisberger, Jay H.

227

EM International Program Action Table  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecember 2005Department ofDOEDisabilityContractors for CapitalHighlights EMProgramEM

228

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

E-Print Network [OSTI]

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

Sheridan, Scott

229

Nuclear facility decommissioning and site remedial actions  

SciTech Connect (OSTI)

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

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

1990-09-01T23:59:59.000Z

230

Radiological Triage | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

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

231

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

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

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

232

2012-2013 Diagnostic Radiology Fellows Cardiovascular Imaging  

E-Print Network [OSTI]

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

Sonnenburg, Justin L.

233

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

234

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

SciTech Connect (OSTI)

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

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

1993-06-01T23:59:59.000Z

235

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

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

236

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

237

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

238

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

239

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

240

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

SciTech Connect (OSTI)

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

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

1993-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

242

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

243

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

244

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

SciTech Connect (OSTI)

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

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

1992-10-01T23:59:59.000Z

245

NV/YMP radiological control manual, Revision 2  

SciTech Connect (OSTI)

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

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

1996-11-01T23:59:59.000Z

246

Technical basis for radiological release of Grand Junction Office Building 2. Volume 2, dose assessment supporting data  

SciTech Connect (OSTI)

The second volume of the Grand Junction Office Action Program Technical Basis for Radiological Release of Grand Junction Office Building 2 report includes the data quality objectives (DQO), sampling plan, collected data, and analysis used to model future radiation doses to members of the public occupying Building 2 on the U.S. Department of Energy (DOE) Grand Junction Office (GJO) site. This volume was assembled by extracting relevant components of the Grand Junction Projects Office Remedial Action Project Building 2 Public Dose Evaluation (DOE 1996) and inserting recent additional data that was gathered and dose pathway modeling that was performed. The intent of this document is to provide all derived guidance decisions, assumptions, measured data, testing results, and pathway modeling software input and output data that supports the discussion and determinations presented in Volume 1 of this report. For constructive employment of this document, the reader is encouraged to closely follow Volume 1 for proper association with the segment of information being examined.

NONE

1997-07-01T23:59:59.000Z

247

Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This CAIP presents a plan to investigate the nature and extent of the contaminants of potential concern (COPCs) at CAU 135. The purpose of the corrective action investigation described in this CAIP is to: (1) Identify the presence and nature of COPCs; (2) Determine the location of radiological contamination within the vault and determine the extent of COPCs in the sump area and on the floor; and (3) Provide sufficient information and data to develop and evaluate appropriate corrective actions for CAS 25-02-01. This CAIP was developed using the U.S. Environmental Protection Agency's (EPA) Data Quality Objectives (DQOs) (EPA, 1994) process to clearly define the goals for collecting environmental data, to determine data uses, and to design a data collection program that will satisfy these uses. A DQO scoping meeting was held prior to preparation of this plan; a brief summary of the DQOs is presented in Section 3.4. A more detailed summary of the DQO process and results is included in Appendix A.

DOE/NV

1999-05-01T23:59:59.000Z

248

Federal Radiological Monitoring and Assessment Center  

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

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

1992-12-02T23:59:59.000Z

249

Memorandum, Reporting of Radiological Sealed Sources Transactions  

Broader source: Energy.gov [DOE]

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

250

Radiological health aspects of uranium milling  

SciTech Connect (OSTI)

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

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

1983-05-01T23:59:59.000Z

251

INL@Work Radiological Search & Response Training  

ScienceCinema (OSTI)

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

Turnage, Jennifer

2013-05-28T23:59:59.000Z

252

Missouri Department of Natural Resources Hazardous Waste Program Weldon Spring site remedial action project - status of project to date January 1997  

SciTech Connect (OSTI)

This document describes the progress made by the Missouri Department of Natural Resources (MDNR) during the fourth year (1996) of the Agreement in Support (AIS) in its oversight role of the Weldon Springs Site Remedial Action Project (WSSRAP). The fourth year at the Weldon Springs Site shows sustained progress as the project moves through the final design and into the remedial action phases of the Chemical Plant Operable Unit. The remedial action phase includes the Foundations Removal work package, Chemical Solidification and Stabilization, and disposal cell.

NONE

1998-04-01T23:59:59.000Z

253

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

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

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

254

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

Office of Environmental Management (EM)

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

255

Mobile autonomous robotic apparatus for radiologic characterization  

DOE Patents [OSTI]

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

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

1999-01-01T23:59:59.000Z

256

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

257

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

258

Mobile autonomous robotic apparatus for radiologic characterization  

DOE Patents [OSTI]

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

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

1999-08-10T23:59:59.000Z

259

Estimating radiological background using imaging spectroscopy  

SciTech Connect (OSTI)

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

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

2014-06-13T23:59:59.000Z

260

Integrating pathology and radiology disciplines: an emerging opportunity?  

E-Print Network [OSTI]

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

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

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

eFRMAC Overview: Data Management and Enabling Technologies for Characterization of a Radiological Release A Case Study: The Fukushima Nuclear Power Plant Incident  

SciTech Connect (OSTI)

The eFRMAC enterprise is a suite of technologies and software developed by the United States Department of Energy, National Nuclear Security Administrations Office of Emergency Response to coordinate the rapid data collection, management, and analysis required during a radiological emergency. This enables the Federal Radiological Monitoring and Assessment Center assets to evaluate a radiological or nuclear incident efficiently to facilitate protective actions to protect public health and the environment. This document identifies and describes eFRMAC methods including (1) data acquisition, (2) data management, (3) data analysis, (4) product creation, (5) quality control, and (6) dissemination.

Blumenthal, Daniel J. [NNSA; Clark, Harvey W. [NSTec; Essex, James J. [NSTec; Wagner, Eric C. [NSTec

2013-07-01T23:59:59.000Z

262

The Health Physics and Radiological Health  

E-Print Network [OSTI]

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

263

Apparatus for safeguarding a radiological source  

DOE Patents [OSTI]

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

Bzorgi, Fariborz M

2014-10-07T23:59:59.000Z

264

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

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

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

265

Formerly Utilized MED/AEC Sites Remedial Action Program. Project management plan for the decontamination of Jones Laboratory, Ryerson Physical Laboratory, and Eckhart Hall, the University of Chicago, Chicago, Illinois  

SciTech Connect (OSTI)

The Department of Energy (DOE) has in place a plan for the decontamination and decommissioning of contaminated sites that had been formerly utilized by the Manhattan Engineering District (MED) and/or the Atomic Energy Commission. This plan is referred to as the Formerly Utilized Sites Remedial Action Program (FUSRAP). Among these sites are Jones Laboratory, Ryerson Physical Laboratory and Eckhart Hall of The University of Chicago at Chicago, Illinois. This document represents the Project Management Plan for the decontamination of these facilities. 13 references, 3 figures, 1 table.

Flynn, K.F.; Smith, W.H.; Wynveen, R.A.

1984-01-01T23:59:59.000Z

266

Contained radiological analytical chemistry module  

DOE Patents [OSTI]

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

Barney, David M. (Scotia, NY)

1989-01-01T23:59:59.000Z

267

Contained radiological analytical chemistry module  

DOE Patents [OSTI]

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

Barney, David M. (Scotia, NY)

1990-01-01T23:59:59.000Z

268

Applying radiological emergency planning experience to hazardous materials emergency planning within the nuclear industry  

SciTech Connect (OSTI)

The nuclear industry has extensive radiological emergency planning (REP) experience that is directly applicable to hazardous materials emergency planning. Recently, the Feed Materials Production Center near Cincinnati, Ohio, successfully demonstrated such application. The REP experience includes conceptual bases and standards for developing plans that have been tested in hundreds of full-scale exercises. The exercise program itself is also well developed. Systematic consideration of the differences between chemical and radiological hazards shows that relatively minor changes to the REP bases and standards are necessary. Conduct of full-scale, REP-type exercises serves to test the plans, provide training, and engender confidence and credibility.

Foltman, A.; Newsom, D.; Lerner, K.

1988-01-01T23:59:59.000Z

269

Y-12 Site environmental protection program implementation plan (EPPIP)  

SciTech Connect (OSTI)

The Y-12 Plant Environmental Protection Program is conducted to: (1) protect public health and the environment from chemical and radiological releases occurring from current plant operations and past waste management and operational practices; (2) ensure compliance with federal, state, and local environmental regulations and DOE directives; (3) identify potential environmental problems; (4) evaluate existing environmental contamination and determine the need for remedial actions and mitigative measures; (5) monitor the progress of ongoing remedial actions and cleanup measures; and (6) inform the public of environmental issues relating to DOE operations. DOE Order 5400.1, General Environmental Protection Program, defines the general requirements for environmental protection programs at DOE facilities. This Environmental Protection Program Implementation Plan (EPPIP) defines the methods by which the Y-12 Plant staff will comply with the order by: (1) referencing environmental protection goals and objectives and identifying strategies and timetables for attaining them; (2) providing the overall framework for the design and implementation of the Y-12 Environmental Protection Program; and (3) assigning responsibilities for complying with the requirements of the order. The EPPIP is revised and updated annually.

NONE

1996-11-01T23:59:59.000Z

270

Action Items  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power Systems EngineeringDepartment of EnergyAbout Us » FAQsUCNIOF ENERGYU.S.-BrazilACTION

271

Annual Report on Resident Fish Activities, 1986 Fiscal Year, Columbia River Basin Fish and Wildlife Program, Action Item 41.8.  

SciTech Connect (OSTI)

This report addresses the status of resident fish projects currently funded by the Bonneville Power Administration (BPA) under the Columbia River Basin Fish and Wildlife Program (Program) established pursuant to the Northwest Power Act (P.L. 96-501). The report provides a brief synopsis, review and discussion of 13 resident fish projects funded during September 1985 to May 1986. The resident fish section of the Program addresses measures which are intended to protect resident fish, mitigate fishery losses caused by hydroelectric projects, and compensate for past losses through enhancement measures. These measures include, but are not limited to: flow requirements, drawdown requirements, temperature control, and streambed protection.

United States. Bonneville Power Administration.

1986-05-01T23:59:59.000Z

272

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

SciTech Connect (OSTI)

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

Not Available

1993-10-01T23:59:59.000Z

273

A comparison of the RCRA Corrective Action and CERCLA Remedial Action Processes  

SciTech Connect (OSTI)

This document provides a comprehensive side-by-side comparison of the RCRA corrective action and the CERCLA remedial action processes. On the even-numbered pages a discussion of the RCRA corrective action process is presented and on the odd-numbered pages a comparative discussion of the CERCLA remedial action process can be found. Because the two programs have a difference structure, there is not always a direct correlation between the two throughout the document. This document serves as an informative reference for Departmental and contractor personnel responsible for oversight or implementation of RCRA corrective action and CERCLA remedial action activities at DOE environmental restoration sites.

Not Available

1994-02-01T23:59:59.000Z

274

Mitigation Action Plan  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment SurfacesResource Program PreliminaryA3,0Statements |Mission73 4.17Mitigation Action

275

Applicable or Relevant and Appropriate Requirements (ARARs) for Remedial Action at the Oak Ridge Reservation: A compendium of major environmental laws. Environmental Restoration Program  

SciTech Connect (OSTI)

Section 121 of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 specifies that remedial actions for cleanup of hazardous substances must comply with applicable or relevant and appropriate requirements (ARARS) or standards under federal and state environmental laws. The US Department of Energy (DOE) Oak Ridge Reservation (ORR) was placed on the National Priorities List by the US Environmental Protection Agency (EPA) on November 21, 1989, effective December 21, 1989. As a result of this listing, DOE, EPA, and the Tennessee Department of Environment and Conservation have signed a Federal Facility Agreement (FFA) for the environmental restoration of the ORR. Section XXI(F) of the FFA calls for the preparation of a draft listing of all ARARs as mandated by CERCLA {section}121. This report supplies a preliminary list of available federal and state ARARs that might be considered for remedial response at the ORR. A description of the terms ``applicable`` and ``relevant and appropriate`` is provided, as well as definitions of chemical-, location-, and action-specific ARARS. ARARs promulgated by the federal government and by the state of Tennessee are listed in tables. In addition, the major provisions of the Resource Conservation and Recovery Act, the Safe Drinking Water Act, the Clean Water Act, the Clean Air and other acts, as they apply to hazardous waste cleanup, are discussed. In the absence of ARARS, CERCLA {section}121 provides for the use of nonpromulgated federal criteria, guidelines, and advisories in evaluating the human risk associated with remedial action alternatives. Such nonpromulgated standards are classified as ``to-be-considered`` (TBC) guidance. A ion of available guidance is given; summary tables fist the available federal standards and guidance information. In addition, the substantive contents of the DOE orders as they apply to remediation of radioactively contaminated sites are discussed as TBC guidance.

Etnier, E.L.; McDonald, E.P.; Houlberg, L.M.

1993-07-01T23:59:59.000Z

276

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Tuba City, Arizona. Apendix D, Site characteriztion  

SciTech Connect (OSTI)

This appendix assesses the present conditions and data for the inactive uranium mill site near Tuba City, Arizona. It consolidates available engineering, radiological, geotechnical, hydrological, meterological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill and tailings site so that the Remedial Action Contractor (RAC) may complete final designs of the remedial actions.

Not Available

1987-05-01T23:59:59.000Z

277

Applicable or relevant and appropriate requirements (ARARs) for remedial actions at the Paducah Gaseous Diffusion Plant: A compendium of environmental laws and guidance. Environmental Restoration Program  

SciTech Connect (OSTI)

Section 121 of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 specifies that remedial actions for cleanup of hazardous substances found at sites placed on the National Priorities List (NPL) by the US Environmental Protection Agency (EPA) must comply with applicable or relevant and appropriate requirements (ARARs) or standards under federal and state environmental laws. To date, the US Department of Energy (DOE) Paducah Gaseous Diffusion Plant (PGDP) has not been on the NPL. Although DOE and EPA have entered into an Administrative Consent Order (ACO), the prime regulatory authority for cleanup at PGDP will be the Resource Conservation and Recovery Act (RCRA). This report supplies a preliminary list of available federal and state ARARs that might be considered for remedial response at PGDP in the event that the plant becomes included on the NPL or the ACO is modified to include CERCLA cleanup. A description of the terms ``applicable`` and ``relevant and appropriate`` is provided, as well as definitions of chemical-, location-, and action-specific ARARS. ARARs promulgated by the federal government and by the state of Kentucky are listed in tables. In addition, the major provisions of RCRA, the Safe Drinking Water Act, the Clean Water Act, the Clean Air Act, and other acts, as they apply to hazardous and radioactive waste cleanup, are discussed.

Etnier, E.L.; Eaton, L.A. [Oak Ridge National Lab., TN (United States)

1992-03-01T23:59:59.000Z

278

Community Service Block Grant Loan Program (Illinois)  

Broader source: Energy.gov [DOE]

Community Service Block Grant Loan Program is a partnership among the Department of Commerce and Economic Opportunity, community action agencies, and the Illinois Ventures for Community Action. The...

279

Energy Efficiency and Conservation Block Grant Program  

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

Action or Project Description 1) Community CFL program, 2) technical consultant for Energy and Climate Action Plan, 3) Civic Center light retrofit, 4) HVAC retrofit project, 5)...

280

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

SciTech Connect (OSTI)

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

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

1993-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

Northern Marshall Islands radiological survey: sampling and analysis summary  

SciTech Connect (OSTI)

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

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

1981-07-23T23:59:59.000Z

282

Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

G. N. Doyle

2002-02-01T23:59:59.000Z

283

Radiological Characterization and Final Facility Status Report Tritium Research Laboratory  

SciTech Connect (OSTI)

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

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

1996-08-01T23:59:59.000Z

284

Radiological Scoping Survey of the Scotia Depot, Scotia, NY  

SciTech Connect (OSTI)

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

Bailey, E. N.

2008-02-25T23:59:59.000Z

285

ASPECT Emergency Response Chemical and Radiological Mapping  

ScienceCinema (OSTI)

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

LANL

2009-09-01T23:59:59.000Z

286

GTRI's Nuclear and Radiological Material Removal | National Nuclear...  

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

and permanently disposing of excess, disused, unwanted, or abandoned radiological material overseas. This includes the recovery of Russian radioisotope thermoelectric...

287

E-Print Network 3.0 - arms aerial radiological Sample Search...  

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

General Diagnostic Radiology * Clinical Rotation Breast Imaging... * Clinical Rotation Pediatric Radiology * Clinical Rotation Nuclear Medicine Semester ... Source: VandeVord,...

288

E-Print Network 3.0 - anticipated radiological dose Sample Search...  

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

- thropomorphic models. II. Organ doses from computed tomographic examinations in pediatric radiology. Neuherberg... dose at CT in pediatric patients. Radiology...

289

Niagara Falls Storage Site environmental report for calendar year 1992, 1397 Pletcher Road, Lewiston, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

This report describes the environmental surveillance program at the Niagara Falls Storage Site (NFSS) and provides the results for 1992. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues produced as a by-product of uranium production. All onsite areas of residual radioactivity above guidelines have been remediated. Materials generated during remediation are stored onsite in the 4-ha (10-acre) waste containment structure (WCS). The WCS is a clay-lined, clay-capped, and grass-covered storage pile. The environmental surveillance program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Several chemical parameters, including seven metals, are also routinely measured in groundwater. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Results of environmental monitoring during 1992 indicate that levels of the parameters measured were in compliance with all but one requirement: Concentrations of iron and manganese in groundwater were above NYSDEC groundwater quality standards. However, these elements occur naturally in the soils and groundwater associated with this region. In 1992 there were no environmental occurrences or reportable quantity releases.

Not Available

1993-05-01T23:59:59.000Z

290

Environmental Health & Safety Office of Radiological Safety  

E-Print Network [OSTI]

Environmental Health & Safety Office of Radiological Safety Page 1 of 2 FORM LU-1 Revision 01 1 safety training and submit this registration to the LSO prior to use of Class 3B or 4 lasers. A copy will be returned to the Laser Supervisor to be filed in the Laboratory Laser Safety Notebook. Both the Laser

Houston, Paul L.

291

Nuclear Engineering Catalog 2013 Radiological Concentration  

E-Print Network [OSTI]

Nuclear Engineering Catalog 2013 Radiological Concentration Fall Math 141 or 147 (4) FA, SP, SU-approved by the department. Courses in Nuclear Engineering other than 500, 502 or 598 may also be used as technical electives on academic performance. Factors considered include overall grade point average, performance in selescted

Tennessee, University of

292

Nuclear Engineering Catalog 2014 Radiological Concentration  

E-Print Network [OSTI]

Nuclear Engineering Catalog 2014 Radiological Concentration Fall Math 141 or 147 (4) FA, SP, SU-approved by the department. Courses in Nuclear Engineering other than 500, 502 or 598 may also be used as technical electives. No more than four (4) credit hours of nuclear engineering courses in which a C- or lower is the highest

Grissino-Mayer, Henri D.

293

An aerial radiological survey of the Nevada Test Site  

SciTech Connect (OSTI)

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

Hendricks, T J; Riedhauser, S R

1999-12-01T23:59:59.000Z

294

MSU EMERGENCY ACTION TEAM  

E-Print Network [OSTI]

police/fire may use in emergencies for announcements HVAC system automated shut off with IPF and Hazardous Materials Emergencies (chemical, biological, radiological, nuclear, explosive) 3. Some other forms

Liu, Taosheng

295

Nuclear facility decommissioning and site remedial actions  

SciTech Connect (OSTI)

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

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

1989-09-01T23:59:59.000Z

296

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

SciTech Connect (OSTI)

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

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

2010-05-25T23:59:59.000Z

297

Determination of aerosol size distributions at uranium mill tailings remedial action project sites  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has an ongoing program, the Uranium Mill Tailings Remedial Action (UMTRA) Project, to stabilize piles of uranium mill tailings in order to reduce the potential radiological hazards to the public. Protection of workers and the general public against airborne radioactivity during remedial action is a top priority at the UMTRA Project. The primary occupational radionuclides of concern are {sup 230}Th, {sup 226}Ra, {sup 210}Pb, {sup 210}Po, and the short-lived decay products of {sup 222}Rn with {sup 230}Th causing the majority of the committed effective dose equivalent (CEDE) from inhaling uranium mill tailings. Prior to this study, a default particle size of 1.0 {mu}m activity median aerodynamic diameter (AMAD) was assumed for airborne radioactive tailings dust. Because of recent changes in DOE requirements, all DOE operations are now required to use the CEDE methodology, instead of the annual effective dose equivalent (AEDE) methodology, to evaluate internal radiation exposures. Under the transition from AEDE to CEDE, with a 1.0 {mu}m AMAD particle size, lower bioassay action levels would be required for the UMTRA Project. This translates into an expanded internal dosimetry program where significantly more bioassay monitoring would be required at the UMTRA Project sites. However, for situations where the particle size distribution is known to differ significantly from 1.0 {mu}m AMAD, the DOE allows for corrections to be made to both the estimated dose to workers and the derived air concentration (DAC) values. For particle sizes larger than 1.0 {mu}m AMAD, the calculated CEDE from inhaling tailings would be relatively lower.

Newton, G.J.; Reif, R.H. [CWM Federal Environmental Services, Inc., Albuquerque, NM (United States); Hoover, M.D.

1994-11-01T23:59:59.000Z

298

Paint for detection of radiological or chemical agents  

DOE Patents [OSTI]

A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, Sumner Daniel (Danville, CA)

2010-08-24T23:59:59.000Z

299

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

Broader source: Energy.gov [DOE]

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

300

Guam Energy Action Plan  

SciTech Connect (OSTI)

Describes the four near-term strategies selected by the Guam Energy Task Force during action planning workshops conducted in March 2013, and outlines the steps being taken to implement those strategies. Each strategy addresses one of the energy sectors identified in the earlier Guam strategic energy plan as being an essential component of diversifying Guam's fuel sources and reducing fossil energy consumption 20% by 2020. The four energy strategies selected are: (1) expanding public outreach on energy efficiency and conservation, (2) establishing a demand-side management revolving loan program, (3) exploring waste-to-energy options, and (4) influencing the transportation sector via anti-idling legislation, vehicle registration fees, and electric vehicles.

Conrad, M. D.; Ness, J. E.

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

The Formerly Utilized Sites Remedial Action Program (FUSRAP) was initiated in 1974 to identify, investigate, and clean up or control sites throughout the United States that were part of the Nation's early atomic weapons and energy programs during the 1940  

E-Print Network [OSTI]

, investigate, and clean up or control sites throughout the United States that were part of the Nation's early atomic weapons and energy programs during the 1940s, 1950s, and 1960s. Activities at the sites were performed by the Manhattan Engineer District or under the Atomic Energy Commission. Both were predecessors

US Army Corps of Engineers

302

Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for the CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The site will be investigated based on the data quality objectives (DQOs) developed on July 6, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for the Baneberry site. The primary release associated with Corrective Action Unit 365 was radiological contamination from the Baneberry nuclear test. Baneberry was an underground weapons-related test that vented significant quantities of radioactive gases from a fissure located in close proximity to ground zero. A crater formed shortly after detonation, which stemmed part of the flow from the fissure. The scope of this investigation includes surface and shallow subsurface (less than 15 feet below ground surface) soils. Radionuclides from the Baneberry test with the potential to impact groundwater are included within the Underground Test Area Subproject. Investigations and corrective actions associated with the Underground Test Area Subproject include the radiological inventory resulting from the Baneberry test.

Patrick Matthews

2010-12-01T23:59:59.000Z

303

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

SciTech Connect (OSTI)

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

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

1994-02-01T23:59:59.000Z

304

Fixation of Radiological Contamination; International Collaborative Development  

SciTech Connect (OSTI)

A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdoms National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

Rick Demmer

2013-03-01T23:59:59.000Z

305

ORISE: Radiological Assessment and Monitoring System (RAMS)  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory |CHEMPACK MappingHistoryMedicalInternationalRadiological

306

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado  

SciTech Connect (OSTI)

This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

Not Available

1992-02-01T23:59:59.000Z

307

St. Louis airport site: Annual site environmental report, St. Louis, Missouri, Calendar Year 1988: Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

The monitoring program at St. Louis Airport Site (SLAPS) measures radon concentrations in air; external gamma dose rates; and uranium, thorium, and radium concentrations in surface water, groundwater, and sediment. To assess the potential effects of SLAPS on public health, the potential radiation dose was estimated for a hypothetical maximally exposed individual. Based on the scenario described in this report, this hypothetical individual would receive an external exposure approximately equivalent to 7.5 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is approximately the same as a person receives during two round-trip flights from New York to Los Angeles (because of greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of SLAPS that results from radioactive materials present at the site is indistinguishable from the dose the same population receives from naturally occurring radioactive sources. Results of 1988 monitoring show that SLAPS is in compliance with the DOE radiation protection standard. 18 refs., 13 figs., 13 tabs.

Not Available

1989-04-01T23:59:59.000Z

308

Niagara Falls Storage Site, Lewiston, New York: Annual site environmental report, Calendar year 1987: Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1987 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 13 refs., 10 figs., 20 tabs.

Not Available

1988-04-01T23:59:59.000Z

309

St. Louis Airport Site, St. Louis, Missouri: Annual site environmental report, Calendar year 1987: Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect (OSTI)

The monitoring program at the SLAPS measures radon gas concentrations in air; external gamma dose rates; and uranium, thorium, and radium concentrations in surface water, groundwater, and sediment. To assess the potential effect of the SLAPS on the public health, the radiation dose was calculated for the maximally exposed individual. Based on the scenario described in this report, the maximally exposed individual would receive an external exposure approximately equivalent to 5.5 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is approximately the same as a person would receive from increased cosmic radiation during six round-trip flights from New York to Los Angeles (due to greater amounts of cosmic radiation at higher altitudes). The dose to the population within an 80-km (50-mi) radius of the SLAPS that would result from radioactive materials present at the site would be indistinguishable from the dose the population would receive from naturally occurring radioactive sources. Results of 1987 monitoring show that the SLAPS is in compliance with the DOE radiation protection standard. 13 refs., 5 figs., 11 tabs.

Not Available

1988-04-01T23:59:59.000Z

310

Climate change action plan  

E-Print Network [OSTI]

Delivery Climate change action plan 2009-2011 #12;2 | Climate change action plan ©istockphoto.com #12;Climate Change Action Plan Climate change action plan | 3 Contents Overview 4 Preface and Introduction 5 Climate change predictions for Scotland 6 The role of forestry 7 Protecting and managing

311

Neighborhood Progress Through Organized Action.  

E-Print Network [OSTI]

[Blank Page in Original Bulletin] ~ei~ h borhood Progress Through Organized Action E. C. MARTIN, Administrative Assistant BONNIE COX, Organization Specialist MRS. EULA NEWMAN, Specialist in Home Management TEXAS A. & M. COLLEGE SYSTEM "The... coord: lent r peo plt 1. mmunity organization is successful when all families erested groups participate. Such an organization may inate interest in the community and provide an excel- neans for channeling most programs. The interest...

Newman, Eula; Cox, Bonnie; Martin, E. C.

1955-01-01T23:59:59.000Z

312

Final report of the UMTRA independent technical review of TAC audit programs  

SciTech Connect (OSTI)

This report details the findings of an Independent Technical Review (ITR) of practices and procedures for the Uranium Mill Tailings Remedial Action (UMTRA) Project audit program. The audit program is conducted by Jacobs Engineering Group Inc., the Technical Assistance Contractor (TAC) for the UMTRA Project. The purpose of the ITR was to ensure that the TAC audit program is effective and is conducted efficiently. The ITR was conducted from May 16-20, 1994. A review team observed audit practices in the field, reviewed the TAC audit program`s documentation, and discussed the program with TAC staff and management. The format of this report has been developed around EPA guidelines; they comprise most of the major section headings. Each section begins by identifying the criteria that the TAC program is measured against, then describing the approach used by the ITR team to measure each TAC audit program against the criteria. An assessment of each type of audit is then summarized for each component in the following order: Radiological audit summary; Health and safety audit summary; Environmental audit summary; Quality assurance audit summary.

Not Available

1994-10-01T23:59:59.000Z

313

Hanford Radiological Protection Support Services Annual Report for 1999  

SciTech Connect (OSTI)

During calendar year (CY) 1999, the Pacific Northwest National Laboratory (PNNL) performed its customary radiological protection support services in support of the U.S. Department of Energy (DOE) Richland Operations Office (RL) and the Hanford contractors. These services included: (1) external dosimetry, (2) internal dosimetry, (3) in vivo measurements, (4) radiological records, (5) instrument calibration and evaluation, and (6) calibration of radiation sources traceable to the National Institute of Standards and Technology (NIST). The services were provided under a number of programs as summarized here. Along with providing site-wide nuclear accident and environmental dosimetry capabilities, the Hanford External Dosimetry Program (HEDP) supports Hanford radiation protection programs by providing external radiation monitoring capabilities for all Hanford workers and visitors to help ensure their health and safety. Processing volumes decreased in CY 1999 relative to prior years for all types of dosimeters, with an overall decrease of 19%. During 1999, the HEDP passed the National Voluntary Laboratory Accreditation Program (NVLAP) performance testing criteria in 15 different categories. HEDP computers and processors were tested and upgraded to become Year 2000 (Y2K) compliant. Several changes and improvements were made to enhance the interpretation of dosimeter results. The Hanford Internal Dosimetry Program (HIDP) provides for the assessment and documentation of occupational dose from intakes of radionuclides at the Hanford Site. Performance problems carried over from CY 1998 continued to plague the in vitro bioassay contractor. A new contract was awarded for the in vitro bioassay program. A new computer system was put into routine operation by the in vivo bioassay program. Several changes to HIDP protocols were made that were related to bioassay grace periods, using field data to characterize the amount of alpha activity present and using a new default particle size. The number of incidents and high routine investigations that required follow-up were lower compared with 1998. Also, the number of excreta analyses performed decreased compared with CY 1998. The In Vivo Monitoring Program for Hanford (formerly the Hanford Whole Body Counting Project) provides the in vivo counting services for Hanford Site radiation workers. New computer hardware and software were put into routine operation to acquire, analyze, and store the measurement data. The technical procedures were revamped to reflect operational changes implemented with the new computer system. The U.S. Department of Energy Laboratory Accreditation Program (DOELAP) accreditation was extended to include two additional categories. New detectors were purchased for wound counting applications. The 8,085 in vivo measurements performed in 1999 represent a 2% decrease from 1998. Several high-purity germanium detectors were repaired at the In Vivo Radioassay and Research Facility, thereby saving out-of-service time and money compared with returning the detectors to the vendor. There were 11 phantom loans made through the DOE Phantom Library in 1999, including 2 international loans.

TP Lynch; DE Bihl; ML Johnson; MA MacLellan; RK Piper

2000-05-19T23:59:59.000Z

314

Uranium Mill Tailings Remedial Action Project 1993 Environmental Report  

SciTech Connect (OSTI)

This annual report documents the Uranium Mill Tailing Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1993, surface remedial action was complete at 10 of the 24 designated UMTRA Project processing sites. In 1993 the UMTRA Project office revised the UMTRA Project Environmental Protection Implementation Plan, as required by the US DOE. Because the UMTRA Project sites are in different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.

Not Available

1994-10-01T23:59:59.000Z

315

Corrective Action Investigation Plan for Corrective Action Unit 405: Area 3 Septic Systems, Tonopah Test Range, Nevada(April 2001, Rev. 0) with Record of Technical Change No. 1  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's (DOE/NV's) approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 405, Area 3 Septic Systems, Tonopah Test Range (TTR), under the Federal Facility Agreement and Consent Order. Corrective Action Unit 405 consists of Corrective Action Sites 03-05-002-SW03, 03-05-002-SW04, and 03-05-002-SW07 (also collectively known as: Septic Waste Systems [SWSs] 3, 4, and 7). Located in Area 3 in the northwest section of the TTR, approximately 140 miles northwest of Las Vegas, this location was historically (between 1960 and 1990) used as a research facility with the mission to perform defense-related projects, and whose operations generated sanitary and industrial wastewaters potentially contaminated with COPCs and disposed of in septic tanks and leachfields. Though Septic Waste Systems 3, 4, and 7 were origin ally constructed to receive sanitary sewage, they may have inadvertently received effluent containing potentially hazardous and radiological constituents containing acetone, benzene, ethylbenzene, 4-methyl-2-pentanone, toluene, xylenes, volatile organic compound constituents, phenols, arsenic, barium, lead, mercury, hydrocarbons of oil and grease, and uranium-234, -235, and -238. The Area 3 septic systems were documented in a DOE/NV 1996 report as being included in the septic tank abandonment program conducted by Sandia National Laboratories in 1993; however, this program was not completed and the possibility exists that some of the Area 3 septic tanks may not have been abandoned. Even though all of the SWSs addressed in this CAIP are inactive, geophysical surveys conducted in 1993 were generally inconclusive and did not provide useful data for the purposes of this investigation. The scope of this current investigation, therefore, will be to determine the existence of the identified CO PCs and excavation will be the primary investigation method employed for these leachfield systems, but this effort may be limited by existing facilities and utilities. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the subsequent corrective action decision document.

DOE /NV

2001-04-26T23:59:59.000Z

316

Final audit report of remedial action construction at the UMTRA Project Mexican Hat, Utah -- Monument Valley, Arizona, sites  

SciTech Connect (OSTI)

The final audit report for remedial action at the Mexican Hat, Utah, Monument Valley, Arizona, Uranium Mill Tailings Remedial Action (UMTRA) Project sites consists of a summary of the radiological surveillances/audits, quality assurance (QA) in-process surveillances, and QA remedial action close-out inspections performed by the US Department of Energy (DOE) and the Technical Assistance Contractor (TAC); on-site construction reviews (OSCR) performed by the US Nuclear Regulatory Commission (NRC); and a surveillance performed by the Navajo Nation. This report refers to remedial action activities performed at the Mexican Hat, Utah--Monument Valley, Arizona, Uranium Mill Tailings Remedial Action (UMTRA) Project sites.

NONE

1995-10-01T23:59:59.000Z

317

2013 Environmental/Radiological Assistance Directory (ERAD) Presentations  

Broader source: Energy.gov [DOE]

November 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site May 2013 THE MARSAME METHODOLOGY Fundamentals, Benefits, and Applications March 2013 Working to Keep our Shipments Safe, Secure and Economical ANL Facility Decommissioning Training Program January 2013 DOE Corporate Operating Experience Program Radiological Reporting Annual Site Environmental Reports (ASERs) & HSS Environmental and Radiation Protection Performance Dashboards November 2012 Environmental Measurements in an Emergency: This is not a Drill! BGRR D&D Presentation for the DOE ERAD Working Group September 2012 Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Clearance of Real and Personal Property Under DOE Radiation Protection Directive DOE Order 458.1 June 2012 RESRAD Codes for ERAD June 27, 2012 Florida International University (FIU) D&D Knowledge Management Information Tool, June 27, 2012 May 2012 Integrated Cloud Based Environmental Data Management System DOE Order 458.1, Radiation Protection of the Public and the Environment

318

Radiological and Nuclear Security in A Global Context  

E-Print Network [OSTI]

This paper considers the state of nuclear and radiological security in the UK and abroad and reports on the methods that could be employed by terrorists with radiological or nuclear material to cause destruction. It is shown that despite current safeguards that problems arise due to materials that are unaccounted for and poor implementation of detection regimes in some geographical regions. The prospect of a future terrorist event that involves nuclear or radiological materials seems likely despite best efforts of prevention.

Jones, Nick

2010-01-01T23:59:59.000Z

319

ACTIONS AND PARTIAL ACTIONS OF INDUCTIVE CONSTELLATIONS  

E-Print Network [OSTI]

ACTIONS AND PARTIAL ACTIONS OF INDUCTIVE CONSTELLATIONS VICTORIA GOULD AND CHRISTOPHER HOLLINGS structure of a semigroup can be recovered from a partial order it possesses. Date: August 13, 2009. 2000 and FEDER, and also FCT post-doctoral grant SFRH/BPD/34698/2007. 1 #12;2 VICTORIA GOULD AND CHRISTOPHER

Gould, Victoria

320

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

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

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C...

Note: This page contains sample records for the topic "action program radiological" 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

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

Office of Environmental Management (EM)

Response to Radiological Transportation Incidents.docx More Documents & Publications TEPP Model Needs Assessment Document First Responder Initial Response Procedure Hazardous...

322

Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 98: Frenchman Flat, Nevada National Security Site, Nevada, Revision 1  

SciTech Connect (OSTI)

This CADD/CAP follows the Corrective Action Investigation (CAI) stage, which results in development of a set of contaminant boundary forecasts produced from groundwater flow and contaminant transport modeling of the Frenchman Flat CAU. The Frenchman Flat CAU is located in the southeastern portion of the NNSS and comprises 10 underground nuclear tests. The tests were conducted between 1965 and 1971 and resulted in the release of radionuclides in the subsurface in the vicinity of the test cavities. Two important aspects of the corrective action process are presented within this CADD/CAP. The CADD portion describes the results of the Frenchman Flat CAU data-collection and modeling activities completed during the CAI stage. The corrective action objectives and the actions recommended to meet the objectives are also described. The CAP portion describes the corrective action implementation plan. The CAP begins with the presentation of CAU regulatory boundary objectives and initial use restriction boundaries that are identified and negotiated by NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The CAP also presents the model evaluation process designed to build confidence that the flow and contaminant transport modeling results can be used for the regulatory decisions required for CAU closure. The first two stages of the strategy have been completed for the Frenchman Flat CAU. A value of information analysis and a CAIP were developed during the CAIP stage. During the CAI stage, a CAIP addendum was developed, and the activities proposed in the CAIP and addendum were completed. These activities included hydrogeologic investigation of the underground testing areas, aquifer testing, isotopic and geochemistry-based investigations, and integrated geophysical investigations. After these investigations, a groundwater flow and contaminant transport model was developed to forecast contaminant boundaries that enclose areas potentially exceeding the Safe Drinking Water Act radiological standards at any time within 1,000 years. An external peer review of the groundwater flow and contaminant transport model was completed, and the model was accepted by NDEP to allow advancement to the CADD/CAP stage. The CADD/CAP stage focuses on model evaluation to ensure that existing models provide adequate guidance for the regulatory decisions regarding monitoring and institutional controls. Data-collection activities are identified and implemented to address key uncertainties in the flow and contaminant transport models. During the CR stage, final use restriction boundaries and CAU regulatory boundaries are negotiated and established; a long-term closure monitoring program is developed and implemented; and the approaches and policies for institutional controls are initiated. The model evaluation process described in this plan consists of an iterative series of five steps designed to build confidence in the site conceptual model and model forecasts. These steps are designed to identify data-collection activities (Step 1), document the data-collection activities in the 0CADD/CAP (Step 2), and perform the activities (Step 3). The new data are then assessed; the model is refined, if necessary; the modeling results are evaluated; and a model evaluation report is prepared (Step 4). The assessments are made by the modeling team and presented to the pre-emptive review committee. The decision is made by the modeling team with the assistance of the pre-emptive review committee and concurrence of NNSA/NSO to continue data and model assessment/refinement, recommend additional data collection, or recommend advancing to the CR stage. A recommendation to advance to the CR stage is based on whether the model is considered to be sufficiently reliable for designing a monitoring system and developing effective institutional controls. The decision to advance to the CR stage or to return to step 1 of the process is then made by NDEP (Step 5).

Irene Farnham and Sam Marutzky

2011-07-01T23:59:59.000Z

323

Remedial Action Plan for the codisposal and stabilization of the Monument Valley and Mexican Hat uranium mill tailings at Mexican Hat, Utah: Appendices C--E. Final report  

SciTech Connect (OSTI)

This document provides appendices C, D, and E this Remedial Action Plan (RAP) which is a revision of the original Mexican Hat Remedial Action Plan and RAP Modification submitted in July 1988 and January 1989, respectively, along with updated design documents. Appendix C provide the Radiological Support Plan, Appendix D provides the Site Characterization, and Appendix E provides the Water Resources Protection Strategy.

NONE

1993-02-01T23:59:59.000Z

324

Radiological hazards of alpha-contaminated waste  

SciTech Connect (OSTI)

The radiological hazards of alpha-contaminated wastes are discussed in this overview in terms of two components of hazard: radiobiological hazard, and radioecological hazard. Radiobiological hazard refers to human uptake of alpha-emitters by inhalation and ingestion, and the resultant dose to critical organs of the body. Radioecological hazard refers to the processes of release from buried wastes, transport in the environment, and translocation to man through the food chain. Besides detailing the sources and magnitude of hazards, this brief review identifies the uncertainties in their estimation, and implications for the regulatory process.

Rodgers, J.C.

1982-01-01T23:59:59.000Z

325

Fourth report on the Oak Ridge National Laboratory Biological Monitoring and Abatement Program for White Oak Creek Watershed and the Clinch River  

SciTech Connect (OSTI)

In response to a condition of the National Pollutant Discharge Elimination System (NPDES) permit issued to Oak Ridge National Laboratory (ORNL) on April 1, 1986, a Biological Monitoring and Abatement Program (BMAP) was developed for White Oak Creek (WOC) and selected tributaries. BMAP currently consists of six major tasks that address both radiological and nonradiological contaminants in the aquatic and terrestrial environs on-site and the aquatic environs off-site. These tasks are (1) toxicity monitoring, (2) bioaccumulation monitoring of nonradiological contaminants in aquatic biota, (3) biological indicator studies, (4) instream ecological monitoring, (5) assessment of contaminants in the terrestrial environment, and (6) radioecology of WOC and White Oak Lake. The ecological characterization of the WOC watershed will provide baseline data that can be used to document the ecological effects of the water pollution control program and the remedial action program. The long-term nature of BMAP ensures that the effectiveness of remedial measures will be properly evaluated.

Loar, J.M. [ed.] [ed.

1994-04-01T23:59:59.000Z

326

Corrective Action Investigation Plan for Corrective Action Unit 565: Stored Samples, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 565 is located in Area 26 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 565 is comprised of one corrective action site (CAS) listed--CAS 26-99-04, Ground Zero Soil Samples. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend closure of CAU 565. Additional information will be obtained by conducting a corrective action investigation before evaluating closure objectives and selecting the appropriate corrective action. The results of the field investigation will support closure and waste management decisions that will be presented in the Corrective Action Decision Document/Closure Report. The site will be investigated based on the data quality objectives (DQOs) developed on June 1, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was utilized to identify and define the type, amount, and quality of data needed to develop and evaluate closure for CAU 565. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to this CAS. The scope of the corrective action investigation for CAU 565 includes the following activities: (1) Remove stored samples, shelves, and debris from the interior of Building 26-2106. (2) Perform field screening on stored samples, shelves, and debris. (3) Dispose of stored samples, shelves, and debris. (4) Collect samples of investigation-derived waste, as needed, for waste management purposes. (5) Conduct radiological surveys of Building 26-2106 in accordance with the requirements in the ''NV/YMP Radiological Control Manual'' to determine if there is residual radiological contamination that would prevent the release of the building for unrestricted use. This Corrective Action Investigation has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

Wickline, Alfred; McCall, Robert

2006-08-01T23:59:59.000Z

327

October 2006 Standards Actions  

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

Project No. SAFT-0109 Continued on next page Standards Actions Page 2 October 2006 2.0 NON-GOVERNMENT STANDARDS ACTIONS 2.1 American National Standards Institute American...

328

July 2006 Standards Actions  

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

were received in June 2006. Continued on next page Standards Actions Page 2 July 2005 2.0 Non-Government Standards Actions 2.1 American National Standards Institute (ANSI)...

329

Derivative actions in China  

E-Print Network [OSTI]

The enactment of derivative action was expected to be actively used by shareholders to protect their interests. In fact, it turned out that this reform effort seemed futile as the right to engage in such actions was ...

Lin, Shaowei

2014-07-02T23:59:59.000Z

330

Phase II Documentation Overview of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Subproject to assess and evaluate radiologic groundwater contamination resulting from underground nuclear testing at the NTS. These activities are overseen by the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended March 2010). For Frenchman Flat, the UGTA Subproject addresses media contaminated by the underground nuclear tests, which is limited to geologic formations within the saturated zone or 100 meters (m) or less above the water table. Transport in groundwater is judged to be the primary mechanism of migration for the subsurface contamination away from the Frenchman Flat underground nuclear tests. The intent of the UGTA Subproject is to assess the risk to the public from the groundwater contamination produced as a result of nuclear testing. The primary method used to assess this risk is the development of models of flow and contaminant transport to forecast the extent of potentially contaminated groundwater for the next 1,000 years, establish restrictions to groundwater usage, and implement a monitoring program to verify protectiveness. For the UGTA Subproject, contaminated groundwater is that which exceeds the radiological standards of the Safe Drinking Water Act (CFR, 2009) the State of Nevadas groundwater quality standard to protect human health and the environment. Contaminant forecasts are expected to be uncertain, and groundwater monitoring will be used in combination with land-use control to build confidence in model results and reduce risk to the public. Modeling forecasts of contaminant transport will provide the basis for negotiating a compliance boundary for the Frenchman Flat Corrective Action Unit (CAU). This compliance boundary represents a regulatory-based distinction between groundwater contaminated or not contaminated by underground testing. Transport modeling simulations are used to compute radionuclide concentrations in time and space within the CAU for the 1,000-year contaminant boundary. These three-dimensional (3-D) concentration simulations are integrated into probabilistic forecasts of the likelihood of groundwater exceeding or remaining below the radiological standards of the Safe Drinking Water Act (CFR, 2009) defined as the contaminant boundary. Contaminant boundaries are not discrete predictions of the location or concentration of contaminants, but instead are spatial representations of the probability of exceeding Safe Drinking Water Act radiological standards. The forecasts provide planning tools to facilitate regulatory decisions designed to protect the health and safety of the public.

Greg Ruskauff

2010-04-01T23:59:59.000Z

331

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*. . : '* FEB1f\l p :.; . I,F8FISKThirdFOR

332

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*. . : '* FEB1f\l p :.; . I,F8FISKThirdFOR

333

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$ EGcG ENERGY MEASUREMENTS;/:4,4 (; .369sy ((-'"

334

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$ EGcG ENERGY MEASUREMENTS;/:4,4 (; .369sy

335

THE RABIT: A RAPID AUTOMATED BIODOSIMETRY TOOL FOR RADIOLOGICAL TRIAGE  

E-Print Network [OSTI]

. Health Phys. 98(2):209­217; 2010 Key words: biological indicators; dosimetry; blood; cytogenetics-priority need in an environment of heightened concern over possible radiological or nuclear terrorist attacks of radiological injuries. A small improvised nuclear device (IND) would produce a major health emergency

336

Current Trends in Gamma Ray Detection for Radiological Emergency Response  

SciTech Connect (OSTI)

Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies.

Mukhopadhyay, S., Guss, P., Maurer, R.

2011-08-18T23:59:59.000Z

337

FRMAC Interactions During a Radiological or Nuclear Event  

SciTech Connect (OSTI)

During a radiological or nuclear event of national significance the Federal Radiological Emergency Monitoring and Assessment Center (FRMAC) assists federal, state, tribal, and local authorities by providing timely, high-quality predictions, measurements, analyses and assessments to promote efficient and effective emergency response for protection of the public and the environment from the consequences of such an event.

Wong, C T

2011-01-27T23:59:59.000Z

338

Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering  

E-Print Network [OSTI]

Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering University of Illinois at Urbana-Champaign The Department of Nuclear, Plasma, and Radiological Engineering-qualified candidates with background in areas related to reactor power engineering and other nuclear applications

Ma, Yi

339

healthcare.utah.edu/radiology What is Nuclear Medicine?  

E-Print Network [OSTI]

expensive diagnostic tests or surgery. Tissues such as intestines, muscles, and blood vessels are difficulthealthcare.utah.edu/radiology Radiology What is Nuclear Medicine? Nuclear Medicine is a specialized to visualize on a standard X-ray. In Nuclear Medicine, a radioactive tracer is used so the tissue is seen more

Feschotte, Cedric

340

Reinforcement Control via Heuristic Dynamic Programming K. Wendy Tang and Govardhan Srikant  

E-Print Network [OSTI]

Dynamic Programing (HDP) system involves two subnetworks, the Action net- work and the Critic network

Tang, Wendy

Note: This page contains sample records for the topic "action program radiological" 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

Radioanalytical Data Quality Objectives and Measurement Quality Objectives during a Federal Radiological Monitoring and Assessment Center Response  

SciTech Connect (OSTI)

During the early and intermediate phases of a nuclear or radiological incident, the Federal Radiological Monitoring and Assessment Center (FRMAC) collects environmental samples that are analyzed by organizations with radioanalytical capability. Resources dedicated to quality assurance (QA) activities must be sufficient to assure that appropriate radioanalytical measurement quality objectives (MQOs) and assessment data quality objectives (DQOs) are met. As the emergency stabilizes, QA activities will evolve commensurate with the need to reach appropriate DQOs. The MQOs represent a compromise between precise analytical determinations and the timeliness necessary for emergency response activities. Minimum detectable concentration (MDC), lower limit of detection, and critical level tests can all serve as measurements reflecting the MQOs. The relationship among protective action guides (PAGs), derived response levels (DRLs), and laboratory detection limits is described. The rationale used to determine the appropriate laboratory detection limit is described.

E. C. Nielsen

2006-01-01T23:59:59.000Z

342

Recovery from chemical, biological, and radiological incidents :  

SciTech Connect (OSTI)

To restore regional lifeline services and economic activity as quickly as possible after a chemical, biological or radiological incident, emergency planners and managers will need to prioritize critical infrastructure across many sectors for restoration. In parallel, state and local governments will need to identify and implement measures to promote reoccupation and economy recovery in the region. This document provides guidance on predisaster planning for two of the National Disaster Recovery Framework Recovery Support Functions: Infrastructure Systems and Economic Recovery. It identifies key considerations for infrastructure restoration, outlines a process for prioritizing critical infrastructure for restoration, and identifies critical considerations for promoting regional economic recovery following a widearea disaster. Its goal is to equip members of the emergency preparedness community to systematically prioritize critical infrastructure for restoration, and to develop effective economic recovery plans in preparation for a widearea CBR disaster.

Franco, David Oliver; Yang, Lynn I.; Hammer, Ann E.

2012-06-01T23:59:59.000Z

343

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Mexican Hat, Utah: Appendix D. Final report  

SciTech Connect (OSTI)

This appendix is an assessment of the present conditions of the inactive uranium mill site near Mexican Hat, Utah. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan. Plan is to characterize the conditions at the mill and tailings site so that the Remedial Action Contractor may complete final designs of the remedial action.

NONE

1988-07-01T23:59:59.000Z

344

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 2, Appendices D and E: Final report  

SciTech Connect (OSTI)

This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

Not Available

1992-02-01T23:59:59.000Z

345

Corrective Action Investigation Plan for Corrective Action Unit 551: Area 12 Muckpiles, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 551, Area 12 muckpiles, Nevada Test Site (NTS), Nevada. 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 551 is located in Area 12 of the NTS, which is approximately 110 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Area 12 is approximately 40 miles beyond the main gate to the NTS. Corrective Action Unit 551 is comprised of the four Corrective Action Sites (CASs) shown on Figure 1-1 and listed below: (1) 12-01-09, Aboveground Storage Tank and Stain; (2) 12-06-05, Muckpile; (3) 12-06-07, Muckpile; and (4) 12-06-08, Muckpile. Corrective Action Site 12-01-09 is located in Area 12 and consists of an above ground storage tank (AST) and associated stain. Corrective Action Site 12-06-05 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. Corrective Action Site 12-06-07 is located in Area 12 and consists of a muckpile associated with the U12 C-, D-, and F-Tunnels. Corrective Action Site 12-06-08 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. In keeping with common convention, the U12B-, C-, D-, and F-Tunnels will be referred to as the B-, C-, D-, and F-Tunnels. The corrective action investigation (CAI) will include field inspections, radiological surveys, and sampling of media, where appropriate. Data will also be obtained to support waste management decisions.

David A. Strand

2004-06-01T23:59:59.000Z

346

Corrective Action Investigation Plan for Corrective Action Unit 551: Area 12 Muckpiles, Nevada Test Site, Nevada, Rev. No. 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 551, Area 12 muckpiles, Nevada Test Site (NTS), Nevada. 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 551 is located in Area 12 of the NTS, which is approximately 110 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Area 12 is approximately 40 miles beyond the main gate to the NTS. Corrective Action Unit 551 is comprised of the four Corrective Action Sites (CASs) shown on Figure 1-1 and listed below: (1) 12-01-09, Aboveground Storage Tank and Stain; (2) 12-06-05, Muckpile; (3) 12-06-07, Muckpile; and (4) 12-06-08, Muckpile. Corrective Action Site 12-01-09 is located in Area 12 and consists of an above ground storage tank (AST) and associated stain. Corrective Action Site 12-06-05 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. Corrective Action Site 12-06-07 is located in Area 12 and consists of a muckpile associated with the U12 C-, D-, and F-Tunnels. Corrective Action Site 12-06-08 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. In keeping with common convention, the U12B-, C-, D-, and F-Tunnels will be referred to as the B-, C-, D-, and F-Tunnels. The corrective action investigation (CAI) will include field inspections, radiological surveys, and sampling of media, where appropriate. Data will also be obtained to support waste management decisions.

Robert F. Boehlecke

2004-06-01T23:59:59.000Z

347

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

SciTech Connect (OSTI)

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

Alfred Wickline

2008-07-01T23:59:59.000Z

348

May 2008 Standards Actions  

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

Standards Actions 2 American National Standards Institute (ANSI) 2 American Society of Mechanical Engineers (ASME) 2 ASTM International 2 American Nuclear Society...

349

May 2006 Standards Actions  

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

Standards Actions 1 American National Standards Institute (ANSI) 1 American Society of Mechanical Engineers (ASME) 2 ASTM International 2 American Nuclear Society...

350

November 2006 Standards Actions  

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

Actions 2 American National Standards Institute (ANSI) 2 American Society of Mechanical Engineers (ASME) 2 ASTM International 2 American Nuclear Society (ANS) 2 National...

351

October 2007 Standards Actions  

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

Actions 1 American National Standards Institute (ANSI) 1 American Society of Mechanical Engineers (ASME) 2 ASTM International 2 American Nuclear Society (ANS) 2 National...

352

Protective Actions and Reentry  

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

This volume defines appropriate protective actions and reentry of a site following an emergency. Canceled by DOE G 151.1-4.

1997-08-21T23:59:59.000Z

353

Climate Action Plan (Kentucky)  

Broader source: Energy.gov [DOE]

The Commonwealth of Kentucky established the Kentucky Climate Action Plan Council (KCAPC) process to identify opportunities for Kentucky to respond to the challenge of global climate change while...

354

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

SciTech Connect (OSTI)

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

J. R. Morton

2000-09-01T23:59:59.000Z

355

Office of radiation and indoor air: Program description  

SciTech Connect (OSTI)

The goal of the Environmental Protection Agency`s (EPA) Office of Radiation and Indoor Air is to protect the public and the environment from exposures to radiation and indoor air pollutants. The Office develops protection criteria, standards, and policies and works with other programs within EPA and other agencies to control radiation and indoor air pollution exposures; provides technical assistance to states through EPA`s regional offices and other agencies having radiation and indoor air protection programs; directs an environmental radiation monitoring program; responds to radiological emergencies; and evaluates and assesses the overall risk and impact of radiation and indoor air pollution. The Office is EPA`s lead office for intra- and interagency activities coordinated through the Committee for Indoor Air Quality. It coordinates with and assists the Office of Enforcement in enforcement activities where EPA has jurisdiction. The Office disseminates information and works with state and local governments, industry and professional groups, and citizens to promote actions to reduce exposures to harmful levels of radiation and indoor air pollutants.

Not Available

1993-06-01T23:59:59.000Z

356

FIRE Project Action Plan in Response to  

E-Print Network [OSTI]

. The project should review other mission statements from the Office of Science in order to understand better, the Next Generation Space Telescope, etc. The project will also solicit input from the science community1 FIRE Project Action Plan in Response to Next Step Options Program Advisory Committee Report (PAC1

357

Draft Action Plan for the Comprehensive  

E-Print Network [OSTI]

benchmarking tools, upgrades to small and medium commercial buildings, upgrades to public buildings, inclusion CA| Draft Action Plan for the Comprehensive Energy Efficiency Program for Existing Buildings Buildings of 2009 (Assembly Bill 758, Skinner, Chapter 470, Statutes of 2009) anticipates the evolution

358

On-the-Fly Model Checking of Program Runs for Automated Debugging M. Frey B.-H. Schlingloff  

E-Print Network [OSTI]

debugging of parallel programs. Dur- ing the monitoring of a program run, a state action net is constructed

Schlingloff, Holger

359

OntheFly Model Checking of Program Runs for Automated Debugging M. Frey B.H. Schlingloff  

E-Print Network [OSTI]

debugging of parallel programs. Dur­ ing the monitoring of a program run, a state action net is constructed

Schlingloff, Holger

360

Posting and Labeling for Radiological Control Guide for use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection  

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

This Guide provides an acceptable methodology for establishing and operating a radiological hazard posting and labeling program that will comply with U.S. Department of Energy (DOE) requirements specified in Title 10 of the Code of Federal Regulations (CFR), Part 835, Occupational Radiation Protection Canceled by DOE G 441.1-1B.

1999-05-24T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

Radiological Threat Reduction | ornl.gov  

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

to participate in the US Department of Energy's program that focuses on three areas: Conversion of highly enriched uranium reactors to low enriched uranium as their fuel...

362

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS).

J. L. Smith

2001-01-01T23:59:59.000Z

363

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

364

Program Development  

SciTech Connect (OSTI)

This presentation covers how to go about developing a human reliability program. In particular, it touches on conceptual thinking, raising awareness in an organization, the actions that go into developing a plan. It emphasizes evaluating all positions, eliminating positions from the pool due to mitigating factors, and keeping the process transparent. It lists components of the process and objectives in process development. It also touches on the role of leadership and the necessity for audit.

Atencio, Julian J.

2014-05-01T23:59:59.000Z

365

February 2001 Standards Actions  

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

Technical Standards Program Document Status Visit the Technical Standards Program Web Site: http:tis.eh.doe.govtechstds Activity Summary In Conversion - 4 In Preparation...

366

Corrective Action Investigation Plan for Corrective Action Unit 550: Smoky Contamination Area Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 550 is located in Areas 7, 8, and 10 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 550, Smoky Contamination Area, comprises 19 corrective action sites (CASs). Based on process knowledge of the releases associated with the nuclear tests and radiological survey information about the location and shape of the resulting contamination plumes, it was determined that some of the CAS releases are co-located and will be investigated as study groups. This document describes the planned investigation of the following CASs (by study group): (1) Study Group 1, Atmospheric Test - CAS 08-23-04, Atmospheric Test Site T-2C; (2) Study Group 2, Safety Experiments - CAS 08-23-03, Atmospheric Test Site T-8B - CAS 08-23-06, Atmospheric Test Site T-8A - CAS 08-23-07, Atmospheric Test Site T-8C; (3) Study Group 3, Washes - Potential stormwater migration of contaminants from CASs; (4) Study Group 4, Debris - CAS 08-01-01, Storage Tank - CAS 08-22-05, Drum - CAS 08-22-07, Drum - CAS 08-22-08, Drums (3) - CAS 08-22-09, Drum - CAS 08-24-03, Battery - CAS 08-24-04, Battery - CAS 08-24-07, Batteries (3) - CAS 08-24-08, Batteries (3) - CAS 08-26-01, Lead Bricks (200) - CAS 10-22-17, Buckets (3) - CAS 10-22-18, Gas Block/Drum - CAS 10-22-19, Drum; Stains - CAS 10-22-20, Drum - CAS 10-24-10, Battery. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each study group. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 31, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 550. The potential contamination sources associated with the study groups are from nuclear testing activities conducted at CAU 550. The DQO process resulted in an assumption that the total effective dose (TED) within the default contamination boundary of CAU 550 exceeds the final action level and requires corrective action. The presence and nature of contamination outside the default contamination boundary at CAU 550 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based final action level. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each group of CASs.

Grant Evenson

2012-05-01T23:59:59.000Z

367

SEE Action Webinar on Community-Based Social Marketing  

Broader source: Energy.gov [DOE]

Hosted by the State and Local Energy Efficiency Action Network, this webinar will describe community-based social marketing as a behavior-based approach for developing energy efficiency programs.

368

2011 SIMON FRASER UNIVERSITY carbon neutral action report  

E-Print Network [OSTI]

and 6 more buildings were recommissioned through the BC Hydro Continuous Optimization Program. SFU: IT Services Virtual Technology & Power Management 6.4 #12;CARBON NEUTRAL ACTION REPORT 2011 EXECUTIVE SUMMARY1

369

Visioning 2050 BNL's Contribution to the NYS Climate Action Plan  

E-Print Network [OSTI]

and Energy Climate change: motivations for NYS action Some energy facts New York State Climate Action Plan, and storage Energy Strategy Focus: Discovery to Deployment CFN/Nanoscience NSLS II New York Blue Core Programs improvements of heating systems, biofuels - Building controls, energy management , etc. #12;#12;The New York

Homes, Christopher C.

370

Uranium Mill Tailings Remedial Action Project 1994 environmental report  

SciTech Connect (OSTI)

This annual report documents the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1994, surface remedial action was complete at 14 of the 24 designated UMTRA Project processing sites: Canonsburg, Pennsylvania; Durango, Colorado; Grand Junction, Colorado; Green River Utah, Lakeview, Oregon; Lowman, Idaho; Mexican Hat, Utah; Riverton, Wyoming; Salt Lake City, Utah; Falls City, Texas; Shiprock, New Mexico; Spook, Wyoming, Tuba City, Arizona; and Monument Valley, Arizona. Surface remedial action was ongoing at 5 sites: Ambrosia Lake, New Mexico; Naturita, Colorado; Gunnison, Colorado; and Rifle, Colorado (2 sites). Remedial action has not begun at the 5 remaining UMTRA Project sites that are in the planning stage. Belfield and Bowman, North Dakota; Maybell, Colorado; and Slick Rock, Colorado (2 sites). The ground water compliance phase of the UMTRA Project started in 1991. Because the UMTRA Project sites are.` different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.

NONE

1995-08-01T23:59:59.000Z

371

Bayesian Network Analysis of Radiological Dispersal Device Acquisitions  

E-Print Network [OSTI]

It remains unlikely that a terrorist organization could produce or procure an actual nuclear weapon. However, the construction of a radiological dispersal device (RDD) from commercially produced radioactive sources and conventional explosives could...

Hundley, Grant Richard

2012-02-14T23:59:59.000Z

372

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

SciTech Connect (OSTI)

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

Wickline, Alfred

2005-12-01T23:59:59.000Z

373

Development of an auditable safety analysis in support of a radiological facility classification  

SciTech Connect (OSTI)

In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23.

Kinney, M.D. [Roy F. Weston, Inc., Rockville, MD (United States); Young, B. [Dept. of Energy, Albuquerque, NM (United States)

1995-03-01T23:59:59.000Z

374

Comments received on proposed rule on radiological criteria for decommissioning and related documents  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As a part of this action, the Commission published in the Federal Register (59 FR 43200), on August 22, 1994, a proposed rule on radiological criteria for decommissioning, soliciting comments both on the rule as proposed and on certain specific items as identified in its supplementary statement of considerations. A draft Generic Environmental Impact Statement (GEIS) in support of the rule, also published in August 1994 as NUREG-1496, along with its Appendix A (NUREG-1501), were also made available for comment. A staff working draft on regulatory guidance (NUREG-1500)was also made available. This report summarizes the 1,309 comments on the proposed rule and supplementary items and the 311 comments on the GEIS as excerpted from 101 docketed letters received associated in the Federal/Register notice. Comments from two NRC/Agreement-States meetings are also summarized.

Page, G.; Caplin, J.; Smith, D. [and others

1996-03-01T23:59:59.000Z

375

A review of the radiological treatment  

SciTech Connect (OSTI)

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

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

1996-07-01T23:59:59.000Z

376

Corrective Action Decision Document/Closure Report for Corrective Action Unit 371: Johnnie Boy Crater and Pin Stripe Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit 371, Johnnie Boy Crater and Pin Stripe, located within Areas 11 and 18 at the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit (CAU) 371 comprises two corrective action sites (CASs): 11-23-05, Pin Stripe Contamination Area 18-45-01, U-18j-2 Crater (Johnnie Boy) The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 371 based on the implementation of corrective actions. The corrective action of closure in place with administrative controls was implemented at both CASs. Corrective action investigation (CAI) activities were performed from January 8, 2009, through February 16, 2010, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 371: Johnnie Boy Crater and Pin Stripe. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides and investigation of other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 371 dataset of investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels (FALs) established in this document. Radiological doses exceeding the FAL of 25 millirem per year were not found to be present in the surface soil. However, it was assumed that radionuclides are present in subsurface media within the Johnnie Boy crater and the fissure at Pin Stripe. Due to the assumption of radiological dose exceeding the FAL, corrective actions were undertaken that consist of implementing a use restriction and posting warning signs at each site. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: No further corrective actions are necessary for CAU 371. A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 371. Corrective Action Unit 371 should be moved from Appendix III to Appendix IV of the FFACO.

Patrick Matthews

2010-07-01T23:59:59.000Z

377

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 2005  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the Department of Energy (DOE) Radiological Control Manual (RCM) in January 1993. This program is to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a)(1)-(4) and Article 511.1 of the PNNL Radiological Control Program Description, personnel dosimetry shall be provided to (1) radiological workers who are likely to receive at least 100 mrem annually, and (2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-2005 confirm that personnel dosimetry is not needed for individuals located in areas monitored by the program

Bivins, Steven R.; Stoetzel, Gregory A.

2006-06-21T23:59:59.000Z

378

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 2006  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the Department of Energy (DOE) Radiological Control Manual (RCM) in January 1993. This program is to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a)(1)-(4) and Article 511.1 of the PNNL Radiological Control Program Description, personnel dosimetry shall be provided to 1) radiological workers who are likely to receive at least 100 mrem annually, and 2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-2005 confirm that personnel dosimetry is not needed for individuals located in areas monitored by the program.

Bivins, Steven R.; Stoetzel, Gregory A.

2007-07-19T23:59:59.000Z

379

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 2001  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the U.S. Department of Energy (DOE) Radiological Control Manual (RCM) in January 1993. This program is to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a) (1)-(4) and Article 511.1 of the PNNL Radiological Control Program Description, personnel dosimetry shall be provided to 1) radiological workers who are likely to receive at least 100 mrem annually, and 2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-2001 confirm that personnel dosimetry is not needed for individuals located in areas monitored by the program.

Bivins, Steven R.; Stoetzel, Gregory A.

2002-07-08T23:59:59.000Z

380

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

SciTech Connect (OSTI)

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

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

1994-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

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

SciTech Connect (OSTI)

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

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

1994-10-01T23:59:59.000Z

382

Radiological assessment of residues from uranium and other ore mining and processing - A precondition for decisions on remedial measures  

SciTech Connect (OSTI)

In certain parts of Eastern Germany relics of uranium mining and milling as well as of traditional ore mining and processing may contribute to the environmental contamination and the radiation exposure of the public. Systematic investigations of the situation are the indispensable prerequisite for decisions upon the radiological relevance and remedial actions. In view of the large number and scattering of relics under consideration, a stepwise procedure with increasing intensity of investigation was developed to solve the task effectively and in an appropriate time. For the radiological evaluation following the steps of investigation generic criteria were derived. They are based on a primary reference dose of level (1 mSv/year) and on measureable radioactivity quantities recommend by the German Commission on Radiological Protection for unrestricted/restricted release of contaminated grounds. Applying the criteria established for the verification (gamma dose rate, volume of disposed material, area affected by waste materials) the investigations led to the result that no more than 30% of the objects of former mining have to be classified as {open_quotes}possibly relevant{close_quotes} and have to be investigated further on.

Ettenhuber, E; Roehnsch, W. [Bundesamt fuer Strahlenschutz, Berlin (Germany); Biesold, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Colonge (Germany)

1994-12-31T23:59:59.000Z

383

Radiological dose assessments in the northern Marshall Islands (1989--1991)  

SciTech Connect (OSTI)

The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure {gamma}-emitters, such as {sup 40}K, {sup 60}Co and {sup 137}Cs, present in individuals. Urine samples are used to measure {alpha} and {beta}-emitting nuclides, such as {sup 239}Pu and {sup 90}Sr, that are undetectable by WBC routine methods.

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1992-01-01T23:59:59.000Z

384

August 2007 Standards Actions  

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

August 2007 1.5 DOE Technical Standards Published No entries were received in August 2007 2.0 Non-Government Standards Actions 2.1 American National Standards Institute (ANSI)...

385

July 2007 Standards Actions  

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

in June 2007 1.5 DOE Technical Standards Published No entries were received in June 2007 2.0 Non-Government Standards Actions 2.1 American National Standards Institute (ANSI)...

386

Climate Action Plan (Maine)  

Broader source: Energy.gov [DOE]

In June 2003, the Maine State Legislature passed a bill charging the Department of Environmental Protection (DEP) with developing an action plan with the goal of reducing greenhouse gas (GHG)...

387

USING RISK-BASED CORRECTIVE ACTION (RBCA) TO ASSESS (THEORETICAL) CANCER DEATHS AVERTED COMPARED TO THE (REAL) COST OF ENVIRONMENTAL REMEDIATION  

SciTech Connect (OSTI)

In 1978, on the basis of existing health studies at the time, the Uranium Mill Tailings Remedial Action (UMTRA) Project legislation was proposed that would authorize remedial action at inactive uranium processing sites and vicinity properties. The cost of the program to the Federal Government was expected to be $180 million. With the completion of this project, approximately 1300 theoretical cancer deaths were prevented in the next 100 years at a cost of $1.45 billion, based on the Fiscal Year 1998 Federal UMTRA budget. The individual site costs ranged from $0.2 million up to $18 billion spent per theoretical cancer death averted over the next 100 years. Resources required to sustain remediation activities such as this are subject to reduction over time, and are originally based on conservative assumptions that tend to overestimate risks to the general public. This evaluation used a process incorporating risk-based corrective action (RBCA); a three-tiered, decision-making process tailoring corrective action activities according to site-specific conditions and risks. If RBCA had been applied at the start of the UMTRA Project, and using a criterion of >1 excess cancer death prevented as justification to remediate the site, only 50% of the existing sites would have been remediated, yielding a cost savings of $303.6 million to the Federal Government and affected States, which share 10% of the cost. This cost savings equates to 21% of the overall project budget. In addition, only 22% of the vicinity properties had structural contamination contributing to elevated interior gamma exposure and radon levels. Focusing only on these particular properties could have saved an additional $269.3 million, yielding a total savings of $573 million; 40% of the overall project budget. As operational experience is acquired, including greater understanding of the radiological and nonradiological risks, decisions should be based on the RBCA process, rather than relying on conservative assumptions that tend to overestimate risks to the general public.

Miller, M. L.; Hylko, J. M.

2002-02-25T23:59:59.000Z

388

Corrective Action Investigation Plan for Corrective Action Unit 562: Waste Systems Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 562 is located in Areas 2, 23, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 562 is comprised of the 13 corrective action sites (CASs) listed below: 02-26-11, Lead Shot 02-44-02, Paint Spills and French Drain 02-59-01, Septic System 02-60-01, Concrete Drain 02-60-02, French Drain 02-60-03, Steam Cleaning Drain 02-60-04, French Drain 02-60-05, French Drain 02-60-06, French Drain 02-60-07, French Drain 23-60-01, Mud Trap Drain and Outfall 23-99-06, Grease Trap 25-60-04, Building 3123 Outfalls These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on December 11, 2008, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 562. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 562 includes the following activities: Move surface debris and/or materials, as needed, to facilitate sampling. Conduct radiological surveys. Perform field screening. Collect and submit environmental samples for laboratory analysis to determine the nature and extent of any contamination released by each CAS. Collect samples of source material to determine the potential for a release. Collect samples of potential remediation wastes. Collect quality control samples. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; DOE, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996; as amended February 2008). Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval of the plan.

Alfred Wickline

2009-04-01T23:59:59.000Z

389

How to deal with radiologically contaminated vegetation  

SciTech Connect (OSTI)

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

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

1996-12-31T23:59:59.000Z

390

Corrective Action Investigation Plan for Corrective Action Unit 555: Septic Systems Nevada Test Site, Nevada, Rev. No.: 0 with Errata  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 555: Septic Systems, Nevada Test Site (NTS), Nevada. 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 555 is located in Areas 1, 3 and 6 of the NTS, which is approximately 65 miles (mi) northwest of Las Vegas, Nevada, and is comprised of the five corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-59-01, Area 1 Camp Septic System; (2) CAS 03-59-03, Core Handling Building Septic System; (3) CAS 06-20-05, Birdwell Dry Well; (4) CAS 06-59-01, Birdwell Septic System; and (5) CAS 06-59-02, National Cementers Septic System. An FFACO modification was approved on December 14, 2005, to include CAS 06-20-05, Birdwell Dry Well, as part of the scope of CAU 555. The work scope was expanded in this document to include the investigation of CAS 06-20-05. 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 555 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 the evaluation and selection of corrective action alternatives.

Pastor, Laura

2005-12-01T23:59:59.000Z

391

Insider Threat Program  

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

To establish responsibilities and requirements for the Department of Energy (DOE) Insider Threat Program (ITP) to deter, detect, and mitigate insider threat actions by Federal and contractor employees in accordance with the requirements of Executive Order 13587, the National Insider Threat Policy and Minimum Standards for Executive Branch Insider Threat Programs and other government-wide and DOE requirements. Does not cancel other directives.

2014-06-02T23:59:59.000Z

392

Radiological assessment. A textbook on environmental dose analysis  

SciTech Connect (OSTI)

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

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

1983-09-01T23:59:59.000Z

393

Water Quality Program, Volume 2 (Alabama)  

Broader source: Energy.gov [DOE]

This volume of the water quality program mainly deals with Technical Standards, Corrective Action Requirements and Financial Responsibility for Owners and Operators of Underground Storage Tanks....

394

Energy Efficiency and Conservation Block Grant Program  

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

Recovery and Reinvestment Act: Proposed Action or Project Description: 1) Energy efficiency financial sub-grant program, 2) re-roof design of City Hall and energy...

395

Energy Efficiency and Conservation Block Grant Program  

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

Reinvestment Act: Proposed Action or Project Description: 1) Reimbursement for energy efficiency and conservation strategy; 2) financial incentive program to promote residential...

396

Energy Efficiency and Conservation Block Grant Program  

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

OK-TRIBE-COMANCHE NATION Energy Efficiency and Conservation Block Grant Program Location: Tribe OK-TRIBE- COMANCHE NATION OK American Recovery and Reinvestment Act: Proposed Action...

397

Energy Efficiency and Conservation Block Grant Program  

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

Action or Project Description 1) Sustainability Manager position, 2) emissions inventory consultant, 3) energy efficiency program for town buildingsfacilities, 4) ball...

398

GRADUATE PROGRAM UNDERGRADUATE PROGRAMS  

E-Print Network [OSTI]

SELF STUDY GRADUATE PROGRAM UNDERGRADUATE PROGRAMS DEPARTMENT OF POLITICAL SCIENCE COLLEGE OF LIBERALARTS TEXAS A&M UNIVERSITY March 2007 #12;SELF STUDY GRADUATE PROGRAM UNDERGRADUATE PROGRAMS DEPARTMENT........................................................................................ 4 Brief History of Degree Programs and the Department

399

Corrective Action Decision Document/Closure Report for Corrective Action Unit 106: Area 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 106 comprises four corrective action sites (CASs): (1) 05-20-02, Evaporation Pond; (2) 05-23-05, Atmospheric Test Site - Able; (3) 05-45-04, 306 GZ Rad Contaminated Area; (4) 05-45-05, 307 GZ Rad Contaminated Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 106 based on the implementation of corrective actions. The corrective action of clean closure was implemented at CASs 05-45-04 and 05-45-05, while no corrective action was necessary at CASs 05-20-02 and 05-23-05. Corrective action investigation (CAI) activities were performed from October 20, 2010, through June 1, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of other releases (mechanical displacement and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 106 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Industrial Area exposure scenario (2,250 hours of annual exposure). The only radiological dose exceeding the FAL was at CAS 05-45-05 and was associated with potential source material (PSM). It is also assumed that additional PSM in the form of depleted uranium (DU) and DU-contaminated debris at CASs 05-45-04 and 05-45-05 exceed the FAL. Therefore, corrective actions were undertaken at these CASs that consisted of removing PSM and collecting verification samples. Results of verification samples show that remaining soil does not contain contamination exceeding the FALs. Therefore, the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) provides the following recommendations: (1) No further corrective actions are necessary for CAU 106. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 106. (3) Corrective Action Unit 106 should be moved from Appendix III to Appendix IV of the FFACO.

Patrick Matthews and Dawn Peterson

2011-09-01T23:59:59.000Z

400

Corrective Action Decision Document/Closure Report for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 367 comprises four corrective action sites (CASs): 10-09-03, Mud Pit 10-45-01, U-10h Crater (Sedan) 10-45-02, Ess Crater Site 10-45-03, Uncle Crater Site The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation of the corrective actions and site closure activities implemented at CAU 367. A corrective action of closure in place with use restrictions was completed at each of the three crater CASs (10-45-01, 10-45-02, and 10-45-03); corrective actions were not required at CAS 10-09-03. In addition, a limited soil removal corrective action was conducted at the location of a potential source material release. Based on completion of these correction actions, no additional corrective action is required at CAU 367, and site closure is considered complete. Corrective action investigation (CAI) activities were performed from February 2010 through March 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters, Nevada Test Site, Nevada. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of non-test or other releases (e.g., migration in washes and potential source material). Based on the proximity of the Uncle, Ess, and Sedan craters, the impact of the Sedan test on the fallout deposited from the two earlier tests, and aerial radiological surveys, the CAU 367 investigation was designed to study the releases from the three crater CASs as one combined release (primary release). Corrective Action Site 10-09-03, Mud Pit, consists of two mud pits identified at CAU 367. The mud pits are considered non-test releases or other releases and were investigated independent of the three crater CASs. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 367 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels (FALs) established in this document. For the primary release, radiological doses exceeding the FAL of 25 millirem per year were not found to be present in the surface or shallow subsurface soil outside the default contamination boundary. However, it was assumed that radionuclides are present in subsurface media within each of the three craters (Sedan, Ess, and Uncle) due to prompt injection of radionuclides from the tests. Based on the assumption of radiological dose exceeding the FAL, corrective actions were undertaken that consisted of implementing a use restriction and posting warning signs at each crater CAS. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. With regard to other releases, no contaminants of concern were identified at the mud pits or any of the other release locations, with one exception. Potential source material in the form of lead was found at one location. A corrective action of clean closure was implemented at this location, and verification samples indicated that no further action is necessary. Therefore, NNSA/NSO provides the following recommendations: A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 367. Corrective Action Unit 367 should be promoted from Appendix III to Appendix IV of the FFACO.

Patrick Matthews

2011-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "action program radiological" 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

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 2000  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the Department of Energy (DOE) Radiological Control Manual (RCM) in January 1993. This program is to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a) (1)-(4) and Article 511.1 of the DOE Standard Radiological Control, personnel dosimetry shall be provided to 1) radiological workers who are likely to receive at least 100 mrem annually, and 2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-2000 confirm that personnel dosimetry is not needed for individuals located in areas monitored by the program.

Bivins, Steven R.; Stoetzel, Gregory A.

2001-07-05T23:59:59.000Z

402

Mitigation Action Plan  

SciTech Connect (OSTI)

This Mitigation Action Plan (MAP) focuses on mitigation commitments stated in the Supplemental Environmental Impact Statement (SEIS) and the Record of Decision (ROD) for the Naval Petroleum Reserve No. 1 (NPR-1). Specific commitments and mitigation implementation actions are listed in Appendix A-Mitigation Actions, and form the central focus of this MAP. They will be updated as needed to allow for organizational, regulatory, or policy changes. It is the intent of DOE to comply with all applicable federal, state, and local environmental, safety, and health laws and regulations. Eighty-six specific commitments were identified in the SEIS and associated ROD which pertain to continued operation of NPR-1 with petroleum production at the Maximum Efficient Rate (MER). The mitigation measures proposed are expected to reduce impacts as much as feasible, however, as experience is gained in actual implementation of these measures, some changes may be warranted.

Not Available

1994-02-01T23:59:59.000Z

403

New Degree Program in BIOMEDICAL PHYSICS  

E-Print Network [OSTI]

New Degree Program in BIOMEDICAL PHYSICS JUNIOR YEAR Fall Physics 5340/41: Optics Chemistry 2220: Biomedical Physics Seminar Science Elective College Group Req. General Education Req. Winter Physics/Radiology 6710: Physics in Medicine Physics 6780: Biomedical Physics Research College Group Req. General

Cinabro, David

404

Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada: Revision 0  

SciTech Connect (OSTI)

The general purpose of this Corrective Action Investigation Plan is to ensure that adequate data are collected to provide sufficient and reliable information to identify, evaluate, and select technically viable corrective action alternatives (CAAs) for Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. Located in Areas 6 and 15 on the NTS, CAU 543 is comprised of a total of seven corrective action sites (CASs), one in Area 6 and six in Area 15. The CAS in Area 6 consists of a Decontamination Facility and its components which are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency Farm and are related to waste disposal activities at the farm. Sources of possible contamination at Area 6 include potentially contaminated process waste effluent discharged through a process waste system, a sanitary waste stream generated within buildings of the Decon Facility, and radiologically contaminated materials stored within a portion of the facility yard. At Area 15, sources of potential contamination are associated with the dairy operations and the animal tests and experiments involving radionuclide uptake. Identified contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, petroleum hydrocarbons, pesticides, herbicides, polychlorinated biphenyls, metals, and radionuclides. Three corrective action closure alternatives - No Further Action, Close in Place, or Clean Closure - will be recommended for CAU 543 based on an evaluation of all the data quality objective-related data. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2004-05-03T23:59:59.000Z

405

Corrective Action Investigation Plan for Corrective Action Unit 190: Contaminated Waste Sites Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 190 is located in Areas 11 and 14 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 190 is comprised of the four Corrective Action Sites (CASs) listed below: (1) 11-02-01, Underground Centrifuge; (2) 11-02-02, Drain Lines and Outfall; (3) 11-59-01, Tweezer Facility Septic System; and (4) 14-23-01, LTU-6 Test Area. These sites are being investigated because existing information is insufficient on the nature and extent of potential contamination to evaluate and recommend corrective action alternatives. Additional information will be obtained before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS by conducting a corrective action investigation (CAI). The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on August 24, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture, and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 190. The scope of the CAU 190 CAI includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling; (2) Conduct radiological and geophysical surveys; (3) Perform field screening; (4) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present; (5) If COCs are present, collect additional step-out samples to define the lateral and vertical extent of the contamination; (6) Collect samples of source material, if present, to determine the potential for a release; (7) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes; and (8) Collect quality control samples. This Corrective Action Investigation Document (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada, U.S. Department of Energy, and U.S. Department of Defense. Under the FFACO, this CAIP will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval.

Wickline, Alfred

2006-12-01T23:59:59.000Z

406

Corrective Action Investigation Plan for Corrective Action Unit 309: Area 12 Muckpiles, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 309, Area 12 Muckpiles, Nevada Test Site (NTS), Nevada. 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 (DoD). Corrective Action Unit 309 is located in Area 12 of the NTS, which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Area 12 is approximately 40 mi beyond the main gate to the NTS. Corrective Action Unit 309 is comprised of the three Corrective Action Sites (CASs) shown on Figure 1-1 and listed below: CAS 12-06-09, Muckpile; CAS 12-08-02, Contaminated Waste Dump (CWD); and CAS 12-28-01, I, J, and K-Tunnel Debris. Corrective Action Sites 12-06-09 and 12-08-02 will be collectively referred to as muckpiles in this document. Corrective Action Site 12-28-01 will be referred to as the fallout plume because of the extensive lateral area of debris and fallout contamination resulting from the containment failures of the J-and K-Tunnels. The corrective action investigation (CAI) will include field inspections, radiological surveys, and media sampling, where appropriate. Data will also be obtained to support waste management decisions. The CASs in CAU 309 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and/or the environment. Existing information on the nature and extent of potential contamination at these sites are insufficient to evaluate and recommend corrective action alternatives for the CASs. Therefore, additional information will be obtained by conducting a CAI prior to evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS.

David A. Strand

2004-12-01T23:59:59.000Z

407

Method for warning of radiological and chemical substances using detection paints on a vehicle surface  

DOE Patents [OSTI]

A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

Farmer, Joseph C. (Tracy, CA)

2012-03-13T23:59:59.000Z

408

Surface with two paint strips for detection and warning of chemical warfare and radiological agents  

DOE Patents [OSTI]

A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

Farmer, Joseph C.

2013-04-02T23:59:59.000Z

409

Paint for detection of corrosion and warning of chemical and radiological attack  

DOE Patents [OSTI]

A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

Farmer, Joseph C. (Tracy, CA)

2010-08-24T23:59:59.000Z

410

POSITION MANAGEMENT ACTION FORM  

E-Print Network [OSTI]

POSITION MANAGEMENT ACTION FORM Workforce Planning | 408-924-2250 classcomp@sjsu.edu SJSU Human FOR POSITION MANAGEMENT FORM Workforce Planning | 408-924-2250| classcomp@sjsu.edu SJSU Human Resources Revised contact your Workforce Planning Analyst. List the name of the position this position reports to

Eirinaki, Magdalini

411

Action Plan Materials Science  

E-Print Network [OSTI]

sense, including all strata) has available to it a wide range of con- venient products which improve, improving companies' pros- pects and generating wealth without harming the environment. And allAction Plan 2010-2013 Materials Science Area EXECUTIVE SUMMARY #12;N.B.: If you require any further

Fitze, Patrick

412

Corrective Action Investigation Plan for Corrective Action Unit 567: Miscellaneous Soil Sites, Nevada National Security Site, Nevada, with ROTC 1 Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 567 is located in Areas 1, 3, 5, 20, and 25 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 567 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 567, which comprises the following corrective action sites (CASs): 01-23-03, Atmospheric Test Site T-1 03-23-25, Seaweed E Contamination Area 05-23-07, A5b RMA 20-23-08, Colby Mud Spill 25-23-23, J-11 Soil RMA These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on May 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 567. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 567 releases are nuclear test operations and other NNSS operations. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary at Atmospheric Test Site T-1 exceeds the final action level (FAL) and requires corrective action. The presence and nature of contamination outside the default contamination boundary at Atmospheric Test Site T-1 and all other CAU 567 CASs will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based FAL. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Matthews, Patrick K.

2013-07-01T23:59:59.000Z

413

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

SciTech Connect (OSTI)

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

NSTec Environmental Restoration

2012-07-17T23:59:59.000Z

414

E-Print Network 3.0 - aspects radiological aspects Sample Search...  

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

in Radiological Health Sciences (1994) from Colorado State University. Her fields... , dosimetry, radiation protection, radiochemistry, societal aspects of nuclear technology,...

415

Corrective Action Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility Nevada Test Site, Nevada  

SciTech Connect (OSTI)

The Area 25 Reactor Maintenance, Assembly, and Disassembly Decontamination Facility is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Unit (CAU) 254. CAU 254 is located in Area 25 of the Nevada Test Site and consists of a single Corrective Action Site CAS 25-23-06. CAU 254 will be closed, in accordance with the FFACO of 1996. CAU 254 was used primarily to perform radiological decontamination and consists of Building 3126, two outdoor decontamination pads, and surrounding soil within an existing perimeter fence. The site was used to decontaminate nuclear rocket test-car hardware and tooling from the early 1960s through the early 1970s, and to decontaminate a military tank in the early 1980s. The site characterization results indicate that, in places, the surficial soil and building materials exceed clean-up criteria for organic compounds, metals, and radionuclides. Closure activities are expected to generate waste streams consisting of nonhazardous construction waste. petroleum hydrocarbon waste, hazardous waste, low-level radioactive waste, and mixed waste. Some of the wastes exceed land disposal restriction limits and will require off-site treatment before disposal. The recommended corrective action was revised to Alternative 3- ''Unrestricted Release Decontamination, Verification Survey, and Dismantle Building 3126,'' in an addendum to the Correction Action Decision Document.

C. M. Obi

2000-12-01T23:59:59.000Z

416

Final audit report of remedial action construction at the UMTRA Project Falls City, Texas, site  

SciTech Connect (OSTI)

This final audit report for the Falls City, Texas, Uranium Mill Tailings Remedial Action Project site summarizes the radiological audits and the quality assurance (QA) in-process surveillances, audits, and final close-out inspection performed by the U.S. Department of Energy (DOE) and Technical Assistance Contractor (TAC). It also summarizes U.S. Nuclear Regulatory Commission (NRC) surveillances. One radiological audit and three radiological surveillances were performed at the Falls City site. These surveillances and audit, which resulted in 31 observations, focused primarily on processing site activities and were performed on the following dates: 3-6 August 1992, 29-30 October 1992, 22-26 March 1993, and 1-3 November 1993. All outstanding radiological issues were closed out at the completion of the construction activities. Six QA in-process surveillances, which resulted in 71 observations, were performed at the Falls City site on the following dates: 22-24 July 1992, 23-25 November 1992, 17-19 May 1993, 16-18 August 1993, 13-15 October 1993, and 2-4 February 1994. All outstanding issues were closed out with the February surveillance on 3 March 1994. The DOE/TAC remedial action close-out inspections of the Falls City site, which resulted in 56 observations, were conducted 9-10 June 1994 and 26 July 1994. The inspections were closed out on 26 January 1995. The NRC performed three on-site construction reviews (OSCR), resulting in seven observations of remedial action construction activities that occurred during site visits. The OSCRs were performed 9 December 1992, 12 May 1993, and 25 October 1993. Since all audit and surveillance observations and recommendations have been closed out, this final audit report segment of the site certification process is complete.

NONE

1995-05-01T23:59:59.000Z

417

Nuclear facility decommissioning and site remedial actions: a selected bibliography  

SciTech Connect (OSTI)

This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

1982-09-01T23:59:59.000Z

418

24.01.01.M5 Radiological Safety Page 1 of 3 UNIVERSITY RULE  

E-Print Network [OSTI]

Radiological Safety Page 3 of 3 1.5 Employees, visitors and students shall only work with radiation sources24.01.01.M5 Radiological Safety Page 1 of 3 UNIVERSITY RULE 24.01.01.M5 Radiological Safety 25, 2011 Next scheduled review: March 25, 2014 Rule Statement Environmental Health and Safety (EHS

419

Environmental Radiological Effluent Monitoring and Environmental Surveillance  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.Program -DepartmentNovember 1, 2010December 1, 1996GuidanceDepartment

420

Radiological Control - DOE Directives, Delegations, and Requirements  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, and 323Program AccomplishmentsScience

Note: This page contains sample records for the topic "action program radiological" 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

Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU)106 is located in Area 5 of the Nevada Test Site, which is approximately 65miles northwest of Las Vegas, Nevada. Corrective Action Unit 106 comprises the five corrective action sites (CASs) listed below: 05-23-02, GMX Alpha Contaminated Area 05-23-05, Atmospheric Test Site - Able 05-45-01, Atmospheric Test Site - Hamilton 05-45-04, 306 GZ Rad Contaminated Area 05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S.Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from a weapons-effect tower test (CAS 05-45-01), a weapons-related airdrop test (CAS05-23-05), equation of state experiments (CAS 05-23-02), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). Surface-deposited radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample plot locations to the dose-based final action level. The TED will be calculated as the total of separate estimates of internal and external doses. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample plot will be used to measure external radiological dose. The presence and nature of contamination from other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) will be evaluated using soil samples collected from the locations most likely containing contamination, if present. AppendixA provides a detailed discussion of the DQO methodology and the DQOs specific to eachCAS. The scope of the corrective action investigation for CAU 106 includes the following activities: Conduct radiological surveys. Collect and submit environmental samples for laboratory analysis to determine internal doserates and the presence of contaminants of concern. If contaminants of concern are present, collect additional samples to define the extent of thecontamination and determine the area where TED at the site exceeds final action levels (i.e., corrective action boundary). Collect samples of investigation-derived waste, as needed, for waste management purposes.

Patrick Matthews

2010-04-01T23:59:59.000Z

422

COMMENTARY/COMMENTAIRE The radiological consequences of the Chernobyl  

E-Print Network [OSTI]

COMMENTARY/COMMENTAIRE The radiological consequences of the Chernobyl accident The First­22 March 1996 Eric Voice Abstract: The human health consequences of the Chernobyl accident in 1986 have are discussed with particular focus on thyroid cancers and exposures to iodine-131. Key words: Chernobyl

Shlyakhter, Ilya

423

Radiology utilizing a gas multiwire detector with resolution enhancement  

DOE Patents [OSTI]

This invention relates to a process and apparatus for obtaining filmless, radiological, digital images utilizing a gas multiwire detector. Resolution is enhanced through projection geometry. This invention further relates to imaging systems for X-ray examination of patients or objects, and is particularly suited for mammography.

Majewski, Stanislaw (Grafton, VA); Majewski, Lucasz A. (Grafton, VA)

1999-09-28T23:59:59.000Z

424

Radiological Habits Survey: Chapelcross Liquid Effluent Pipeline, 2002  

E-Print Network [OSTI]

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

425

Radiological Modeling for Determination of Derived Concentration Levels of an Area with Uranium Residual Material - 13533  

SciTech Connect (OSTI)

As a result of a pilot project developed at the old Spanish 'Junta de Energia Nuclear' to extract uranium from ores, tailings materials were generated. Most of these residual materials were sent back to different uranium mines, but a small amount of it was mixed with conventional building materials and deposited near the old plant until the surrounding ground was flattened. The affected land is included in an area under institutional control and used as recreational area. At the time of processing, uranium isotopes were separated but other radionuclides of the uranium decay series as Th-230, Ra-226 and daughters remain in the residue. Recently, the analyses of samples taken at different ground's depths confirmed their presence. This paper presents the methodology used to calculate the derived concentration level to ensure that the reference dose level of 0.1 mSv y-1 used as radiological criteria. In this study, a radiological impact assessment was performed modeling the area as recreational scenario. The modelization study was carried out with the code RESRAD considering as exposure pathways, external irradiation, inadvertent ingestion of soil, inhalation of resuspended particles, and inhalation of radon (Rn-222). As result was concluded that, if the concentration of Ra-226 in the first 15 cm of soil is lower than, 0.34 Bq g{sup -1}, the dose would not exceed the reference dose. Applying this value as a derived concentration level and comparing with the results of measurements on the ground, some areas with a concentration of activity slightly higher than latter were found. In these zones the remediation proposal has been to cover with a layer of 15 cm of clean material. This action represents a reduction of 85% of the dose and ensures compliance with the reference dose. (authors)

Perez-Sanchez, Danyl [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)] [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)

2013-07-01T23:59:59.000Z

426

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

SciTech Connect (OSTI)

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

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

1994-10-01T23:59:59.000Z

427

Corrective Action Decision Document/Closure Report for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 365 based on the implementation of the corrective action of closure in place with a use restriction (UR). Corrective action investigation (CAI) activities were performed from January 18, 2011, through August 2, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 365 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in supporting the DQO decisions. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present to the southwest of the Baneberry crater. It was also assumed that radionuclide levels present within the crater and fissure exceed the FAL. Corrective actions were undertaken that consisted of establishing a UR and posting warning signs for the crater, fissure, and the area located to the southwest of the crater where soil concentrations exceeded the FAL. These URs were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions beyond what are described in this document are necessary for CAU 365. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 365. (3) Corrective Action Unit 365 should be moved from Appendix III to Appendix IV of the FFACO.

Patrick Matthews

2011-09-01T23:59:59.000Z

428

Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01T23:59:59.000Z

429

Corrective Action Investigation Plan for Corrective Action Unit...  

Office of Scientific and Technical Information (OSTI)

Plan for Corrective Action Unit 541: Small Boy Nevada National Security Site and Nevada Test and Training Range, Nevada Re-direct Destination: Corrective Action Unit (CAU) 541 is...

430

Corrective Action Decision Document/Closure Report for Corrective Action Unit 504: 16a-Tunnel Muckpile, Nevada Test Site  

SciTech Connect (OSTI)

This Corrective Action Decision Document (CADD)/Closure Report (CR) was prepared by the Defense Threat Reduction Agency (DTRA) for Corrective Action Unit (CAU) 504, 16a-Tunnel Muckpile. This CADD/CR is consistent with the requirements of the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Corrective Action Unit 504 is comprised of four Corrective Action Sites (CASs): 16-06-01, Muckpile 16-23-01, Contaminated Burial Pit 16-23-02, Contaminated Area 16-99-01, Concrete Construction Waste Corrective Action Site 16-23-01 is not a burial pit; it is part of CAS 16-06-01. Therefore, there is not a separate data analysis and assessment for CAS 16-23-01; it is included as part of the assessment for CAS 16-06-01. In addition to these CASs, the channel between CAS 16-23-02 (Contaminated Area) and Mid Valley Road was investigated with walk-over radiological surveys and soil sampling using hand tools. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation for closure in place with use restrictions for CAU 504. A CADD was originally submitted for CAU 504 and approved by the Nevada Division of Environmental Protection (NDEP). However, following an agreement between NDEP, DTRA, and the DOE, National Nuclear Security Administration Nevada Site Office to change to a risk-based approach for assessing the corrective action investigation (CAI) data, NDEP agreed that the CAU could be re-evaluated using the risk-based approach and a CADD/CR prepared to close the site.

NSTec Environmental Restoration

2010-03-15T23:59:59.000Z

431

Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography  

SciTech Connect (OSTI)

This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1985-09-01T23:59:59.000Z

432

Radiological dose assessments in the northern Marshall Islands (1989--1991)  

SciTech Connect (OSTI)

The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southwest of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral islands, having a total land area of about 180 km{sup 2}, distributed over more than 2.5 {times} 10{sup 6} of ocean. Between 1946 and 1958 the United states conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planning to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure {gamma}-emitters, such as {sup 40}K, {sup 60}Co and {sup 137}Cs, present in individuals. Urine samples are used to measure {alpha} and {beta}-emitting nuclides such as {sup 239}Pu and {sup 90}Sr, that are undetectable by WBC routine methods.

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1991-11-01T23:59:59.000Z

433

Radiological dose assessments in the northern Marshall Islands (1989--1991). Revision  

SciTech Connect (OSTI)

The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southwest of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral islands, having a total land area of about 180 km{sup 2}, distributed over more than 2.5 {times} 10{sup 6} of ocean. Between 1946 and 1958 the United states conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planning to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure {gamma}-emitters, such as {sup 40}K, {sup 60}Co and {sup 137}Cs, present in individuals. Urine samples are used to measure {alpha} and {beta}-emitting nuclides such as {sup 239}Pu and {sup 90}Sr, that are undetectable by WBC routine methods.

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1991-11-01T23:59:59.000Z

434

Radiological dose assessments in the northern Marshall Islands (1989--1991)  

SciTech Connect (OSTI)

The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southeast of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral island, having a total land area of about 180 km{sup 2}, distributed over more than 2.5 {times} 10{sup 6} km{sup 2} of ocean. Between 1946 and 1958 the United States conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planing to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure {gamma}-emitters, such as {sup 40}K, {sup 60}Co and {sup 137}Cs, present in individuals. Urine samples are used to measure {alpha} and {beta}-emitting nuclides, such as {sup 239}Pu and {sup 90}Sr, that are undetectable by WBC routine methods. 6 refs.

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1991-12-01T23:59:59.000Z

435

Radiological dose assessments in the northern Marshall Islands (1989--1991). Revision  

SciTech Connect (OSTI)

The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southeast of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral island, having a total land area of about 180 km{sup 2}, distributed over more than 2.5 {times} 10{sup 6} km{sup 2} of ocean. Between 1946 and 1958 the United States conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planing to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure {gamma}-emitters, such as {sup 40}K, {sup 60}Co and {sup 137}Cs, present in individuals. Urine samples are used to measure {alpha} and {beta}-emitting nuclides, such as {sup 239}Pu and {sup 90}Sr, that are undetectable by WBC routine methods. 6 refs.

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1991-12-01T23:59:59.000Z

436

Corrective Action Investigation Plan for Corrective Action Unit 370: T-4 Atmospheric Test Site, Nevada Test Site, Nevada with ROTC-1, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 370 is located in Area 4 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 370 is comprised of Corrective Action Site (CAS) 04-23-01, Atmospheric Test Site T-4. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and/or implement a corrective action. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for this CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The investigation results may also be used to evaluate improvements in the Soils Project strategy to be implemented. The site will be investigated based on the data quality objectives (DQOs) developed on December 10, 2007, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Desert Research Institute; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 370. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to the CAS. The scope of the CAI for CAU 370 includes the following activities: Move surface debris and/or materials, as needed, to facilitate sampling. Conduct radiological surveys. Perform field screening. Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern are present. If contaminants of concern are present, collect samples to define the extent of the contamination. Collect samples of investigation-derived waste including debris deemed to be potential source material, as needed, for waste management purposes.

Pat Matthews

2008-04-01T23:59:59.000Z

437

Aerial vehicle with paint for detection of radiological and chemical warfare agents  

DOE Patents [OSTI]

A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

Farmer, Joseph C.; Brunk, James L.; Day, S. Daniel

2013-04-02T23:59:59.000Z

438

Method for warning of radiological and chemical agents using detection paints on a vehicle surface  

DOE Patents [OSTI]

A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, S. Daniel (Danville, CA)