[en] This paper is a high-level overview of managing risks to workers, public, and the environment. It discusses the difference between a model and a hypothesis. The need for models in risk assessment is justified, and then it is shown that radiation risk models that are useable in risk management are highly simplistic. The weight of evidence is considered for and against the linear non-threshold (LNT) model for carcinogenesis and heritable ill-health that is currently the basis for radiation risk management. Finally, uses and misuses of this model are considered. It is concluded that the LNT model continues to be suitable for use as the basis for radiation protection

[en] This paper reports that HEPA-filtered wet vacuum systems are used at many nuclear stations for decontamination and spill cleanup. One problem with a wet vacuum, however, in that the operator must periodically stop the unit and move it to a floor drain to empty the water that has been collected. Interrupting the job in this manner decreases productivity, increases personnel exposures, and increases the chances for the spread of contamination. Recognizing this, Indian Point Station personnel have modified some wet vacuum systems to allow the continuous direct pump-down of the units to a floor drain

[en] This paper reports that Wolf Creek has developed a method for efficiently training contract health physics technicians. The time allotted for training contractors prior to a refueling and maintenance outage is normally limited to a few days. Therefore, it was necessary to develop a systematic method to evaluate prior experience as well as practical skills and knowledge. In addition, instruction in the particular methodologies used at Wolf Creek hadto be included with methods for evaluating technician comprehension

[en] The Universal Radiation Spectrum Analyzer (URSA-II), developed by Radiation Safety Associates, and manufactured by SE International (Figure 1) is an interface between a radiation detector and a personal computer. Originally, the URSA-II was developed for use with detectors that measure the energy of gamma rays. At the Idaho National Laboratory, the URSA-II is an integral part of standard measurement techniques to measure characteristics of neutron radiation fields. Those techniques are discussed briefly and spectra using the URSA-II are presented

[en] In this paper a dosimeter is proposed for the purpose of detecting noble gas releases (principally Xe-133) from nuclear power plants. The dosimeter consists of two Li₂B₄O₇:Cu (LiBO) elements and one CaSO₄:Tm (CaSO) element. One LiBO element is enclosed only in plastic and is used to determine shallow dose, while the LiBO and CaSO pair, which are used to determine deep dose, are enclosed in a 1070 mg/cm² aluminum sphere and plastic. The dosimeter is designed to overcome the three major problems involved in monitoring for Xe-133: the effect of angular response, differences in irradiation geometry (overhead plume vs. submersion), and interference from naturally occurring high-energy gamma rays. Laboratory test data are presented to demonstrate the proposed dosimeter's response characteristics

[en] In this paper an approach to developing realistic radiological data for incorporation in emergency plan scenarios is discussed. The methodology mimics the progression of a plant radiological event from the creation of a source term, to the radiological conditions that result within the plant, to the effect of an environmental release. Important considerations in the development of data at each step are discussed

[en] In this paper a scheme for determining which protective measures should be implemented as facilities that process radioactive material is presented. The recommendations re based on the quantity of material being processed and on the relative toxicity of those materials. The proposed scheme is compared to others that have appeared in the literature

[en] Carolina Power and Light Company's Shearon Harris Nuclear Power Plant will enter commercial operation in 19987. During its design and construction a number of reviews were performed to ensure that personnel exposures in the completed plant would be ALARA. The final review in this process consisted of a comprehensive walk-down of plant radiation controlled areas by health physics, operations, maintenance, and engineering personnel. The walk-down project was conducted over a 12-month period using detailed criteria and checklists. This article describes the project, presents examples of the criteria that were used, and list the problems that were identified for resolution as well as the good ALARA design features that were incorporated into the plant

[en] This paper reports that on December 18, 1988, a worker at the Duane Arnold Energy Center was found to have a hot particle lodged in his nasal passage. A mild steam inhalation technique was used to expel the particle which proved to be 0.206 Ci of Co-60. This activity, along with the appropriate distance and shielding data, was used with the VARSKIN dose calculation program. A dose of 0.6 rad was calculated. The most interesting aspect of this case was determining which organ the dose should be assigned to. With the concurrence of the Nuclear Regulatory Commission, the dose was assigned to the skin of the whole body

[en] An integrated system of data management is a necessity for the variety and volume of data encountered in many health physics programs. A Personal Computer (PC) Database Management System (DBMS) can fill these data management needs if it is designed and constructed properly. This article presents a suggested approach to PC database design and outlines the specific features that should be examined when choosing DBMS software. This approach was used to set up a health physics database system at the National Bureau of Standards in 1985. The NBS system is described, and an example of dosimetry data entry is used to illustrate how the system works