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At least 19 records

Nevada National Security Site Radiological Control Manual

Please have this STIP assigned, documented, and recorded in OSTI as Report Number DOE/NV/03624--0257 Revision 1 and Author as Radiological Control Managers' Council. 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 Field Office (NNSA/NFO). (Activities conducted under the purview of the U.S. Department of Energy, Office of Environmental Management Nevada[(EM Nevada] may require additional approval authorities as described in the EM Nevada Prime Contractor’s implementation plan.) Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, “Occupational Radiation Protection.” This manual represents policies, guidelines, and best practices for implementing the DOE/NV/03624--0082, “Nevada National Security Site Radiation Protection Program,” (NNSS RPP) according to the requirements of 10 CFR 835.

61 RADIATION PROTECTION AND DOSIMETRY↗

Nevada National Security Site Radiological Control Manual

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 Field Office (NNSA/NFO). (Activities conducted under the purview of the U.S. Department of Energy, Office of Environmental Management Nevada[(EM Nevada] may require additional approval authorities as described in the EM Nevada Prime Contractor’s implementation plan.) Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, “Occupational Radiation Protection.” This manual represents policies, guidelines, and best practices for implementing the DOE/NV/03624--0082, “Nevada National Security Site Radiation Protection Program,” (NNSS RPP) according to the requirements of 10 CFR 835.

61 RADIATION PROTECTION AND DOSIMETRY↗

Nevada National Security Site Radiological Control Manual (Rev. 2)

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.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Weld Repair of a Stamped Pressure Vessel in a Radiologically Controlled Zone

In September 2012 an ASME B&PVC Section VIII stamped pressure vessel located at the DOE Hanford Site Effluent Treatment Facility (ETF) developed a through-wall leak. The vessel, a steam/brine heat exchanger, operated in a radiologically controlled zone (by the CH2MHill PRC or CHPRC), had been in service for approximately 17 years. The heat exchanger is part of a single train evaporator process and its failure caused the entire system to be shut down, significantly impacting facility operations. This paper describes the activities associated with failure characterization, technical decision making/planning for repair by welding, logistical challenges associated with performing work in a radiologically controlled zone, performing the repair, and administrative considerations related to ASME code requirements.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Radiological Control Manual

Objectives of the manual are to (1) ensure compliance with requirements of AEC and governmental health agencies, (2) ensure against excessive and unnecessary exposure of personnel to harmful radiation, and (3) prevent contamination of equipment, materials, and environment with radioactive materials.

Noblin, J. W.↗

Controlling radiological and chemical hazards of uranium in the workplace: Applications of biokinetic modeling and occupational monitoring data

This paper describes methods of interpreting and applying occupational uranium (U) monitoring data to avoid chemical damage to the kidneys and limit radiological risk to an acceptable level. The methods are based on current international radiation protection guidance, current information on the chemical toxicity of U, and best available biokinetic models for U. The methods apply to air monitoring data and bioassay (U in urine and faeces and externally measured U in lungs). Reference primary guidance levels for prevention of chemical effects and limitation of radiation effects are selected on the basis of a review of current scientific data and regulatory principles for setting standards. Generic investigation levels (ILs) and immediate action levels (IALs) are defined in terms of the primary guidance levels. The ILs and IALs are stated in terms of generic levels of radiation dose and concentration of U in the kidneys that are not directly measurable quantities. Models are used to relate the generic levels to measured levels of U in air or bioassay. Methods are prescribed for deriving ILs and IALs of U in air and bioassay for known and unknown solubility levels of airborne U. This paper focuses on interpretation of air monitoring to illustrate the general approach.

bioassay↗

Radiological Control of Water in Reactor Pond of MR Reactor in NRC 'Kurchatov Institute', During Dismantling Work - 13462

The analysis of the activity and radionuclide composition of water from the MR reactor pond for α,β,γ-ray radionuclides was made. To solve this problem we use a wide range of laboratory equipment: gamma spectrometric complex, beta spectrometric complex, vacuum alpha spectrometer, and spectrometric complex with liquid scintillator. The water from MR reactor pond contains: Cs-137 (2,6*10{sup 2} Bq/g), Co-60(1,8 Bq/g), Sr-90 (1,0*10{sup 2} Bq/g), H-3 (7,0*10{sup 3} Bq/g), and components of nuclear fuel (U-232,U-234,U-235,U-236,U-238). Therefore the cleaning water from radioactivity waste occurs to be quite a complicated radiochemical task. (authors)

07 ISOTOPE AND RADIATION SOURCES↗

The control room radiological habitability assessment of high temperature reactor pebble bed module (HTR-PM) - 18465

The control room radiological habitability is important for staff safety in nuclear power plant accident, which is also a licensing requirement of the High Temperature Reactor Pebble Bed Module (HTR-PM) in China. In this study, a comprehensive evaluation of the control room radiological habitability is performed for three design basis accident scenario of HTR-PM. For each scenario, three exposure pathways are taken into account, which includes the immersion external exposure, the inhalation exposure and the direct exposure from radioactive cloud in the environment. The atmospheric concentration is calculated using the NRC-recommended ARCON96 code, based on the two-year meteorological observation data at HTR-PM s site and the final building layout. The evaluation result demonstrates that the individual dose level of staffs in the control room is far below the requirement of the regulatory, which guarantees the radiological habitability of control room of HTR-PM. The contribution of each radionuclide has been analyzed, which suggests that iodine and metal radionuclides such as Cs-137 and Co-60 are primary contributor of the total dose, which are worthy of particular attention in the control room habitability design. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room

Human factors researchers at Idaho National Laboratory are collaborating with a utility partner to address human factors in the modernization of their radiological waste control room. The collaborating utility, Palo Verde, plans to remove all control boards associated with the liquid radiological waste system, which include controls, indicators, and alarm systems, and replace them with modernized digital instrumentation and controls and displays. To be sure the new system either supports current operational performance or enhances it, researchers have carried out three planning and analysis activities: expert operator review, function allocation analysis, and human factor principles and design applications. Researchers utilized access to expert operators to gain information about the system. Operators were asked to detail a procedure exemplifying typical interactions with the liquid radiological waste system and provide it to Idaho National Laboratory with a list of functionalities to incorporate (Section 4.1). Later, operators were asked to provide additional feedback to inform a prototype with adequate realism to support sound analysis of the system design (Section 4.2). Other operators not associated with the utility partner were also involved in experiment design and prototype evaluation (Section 4.2). Due to the extent of the upgrade, care was given to measure the change in the operator’s role (Section 7). As part of the modernization, some plant systems are expected to be equipped with automation or sensors that send information directly to the control where previously operators were required to enter controlled areas to find the information. Such updates made slight changes to operator role requirements, but the impact was negligible. The way the system is operated will remain largely the same, but operator convenience and safety is expected to increase. Additionally, to map operator tasks during the selected procedure, an Operational Sequence Diagram was created (Section 7.1). The diagram helped to account for every interaction and piece of equipment needed to create the prototype design. Alternatively, the diagram can be created following the final design to identify any function reallocations due to redesign. Human factors principles were also applied to the design. An ergonomic assessment was performed on the workspace resulting in various recommendations for placing and designing the new workstation (Section 6). A 3 D mockup of the control room was created to depict the options available with in-depth descriptions of each. Furthermore the prototype design incorporates well known human factors principles. However, to be sure the principles are sound in the control room context, the researches have designed an experiment to measure the impact design decision has on operator performance. The experiment is described in detail in Section 5. Lastly, a tool emerged as this effort began called the NUREG 0711 Crosswalk (Section 8). The tool has multiple uses, but it was primarily intended to communicate how the researcher’s action directly mapped to specific results suggested in the Nuclear Regulatory Commission review guideline. The tool also maps how current results impact future decisions in the modernization process.

47 OTHER INSTRUMENTATION↗