[en] The nuclear insurance pools, through American Nuclear Insurers (ANI) and the Mutual Atomic Energy Liability Underwriters (MAELU), have been providing the third-party liability insurance required of the nuclear industry by the Price-Anderson Act since 1957. Records of claims of radiation injury have been kept for twenty-five years, and a recent upsurge of the claim rate has been noted. An explanation for this new trend is postulated and some examples are discussed. The use of health physics records as evidence in litigation is described, and specific examples of the types of records required to defend against past and future claims are given

[en] The current status of internal dosimetry in the United States is a confused one. Federal regulations still use recommendations of the NCRP and ICRP which were prepared more than twenty years ago. More recently the ICRP has issued publications on a new philosophy of radiation protection and has adopted new recommendations of the ICRU on radiation quantities and units. These publications have been followed by a new set of recommendations from the ICRP on limits of intake of radionuclides for radiation workers. This manuscript reviews the current regulations in use in the United States, as well as the new ICRP recommendations. Calculational techniques used for each set of recommendations are explained and differences are highlighted. Also included is a short discussion of bioassay techniques used for internal exposure assessment in the industry

[en] The measurement of neutron exposures to personnel is an issue that has received increased attention in the last few years. It is important to consider key aspects of the whole dosimetry system when developing dose estimates. This begins with selection of proper dosimeters and survey instruments, and extends through the calibration methods. One must match the spectral response and sensitivity of the dosimeter to the spectral characteristics of the neutron fields. Threshold detectors that are insensitive to large fractions of neutrons in the lower energy portion of reactor spectra should be avoided. Use of two or more detectors with responses that complement each other will improve measurement quality. It is important to understand the spectral response of survey instruments, so that spectra which result in significant overresponse do not lead to overestimation of dose. Calibration sources that do not match operational field spectra can contribute to highly erroneous results. In those situations, in-field calibration techniques should be employed. Although some detection developments have been made in recent years, a lot can be done with existing technology until fully satisfactory, long term solutions are obtained

[en] Sources of Radiation in the US nuclear fuel cycle attend the various processes from mine to the generation of electric power. A light-water reactor fuel cycle consists of mining, ore concentration, purification, conversion to UF⁶, enrichment of ₂₃₅U, fuel fabrication, power generation, reprocessing and waste disposal. Some aspects of the physical and chemical nature of uranium are considered first, followed by some thoughts on the major fuel cycle steps and the potential radiological exposures that attend some of the processes

[en] Th essence of management is obtaining results through the efforts of other people. The efforts obtained, or performance, are enhanced by those who practice management with certain understandings of the work, role and behavior of management, who have the will to manage, and who have requisite skill and aptitude. Discussion of managerial work, role, and behavior comprises the major part of the following paper. The paper concludes with the suggestion that ineffective management is not the result of lack of knowledge about managing, rather ineffective management is more often the result of a lack of will to manage

[en] Control of radiation exposures in nuclear power stations to assure they are as low as reasonably achievable (ALARA) requires that the stations be designed and operated in accordance with certain generally accepted features and practices. This paper is a general survey of those design and operational practices with a concentration on the design aspect of ALARA. Generic design guidelines are developed as well as specific facility and design features. Since maintenance and inservice inspection activities account for over seventy percent of the annual collective exposures at most stations, emphasis is placed on design features that facilitate the accomplishment of these is placed on design features that facilitate the accomplishment of these tasks. Sources of corrosion product exposure and measures that have been and are being taken to reduce them are discussed. Domestic, Department of Energy, US Navy, and foreign reactor exposure experience is reviewed to enable a comparison of trends and to indicate the effectiveness of the different entities in controlling occupational exposures. A brief history of the ALARA concept, the ALARA regulatory guidance that has been issued, and the proposed changes in occupational radiation exposure guidance with its increased emphasis on ALARA are highlighted

[en] The need to control airborne and surface contamination cannot be overstressed. Failure or inability to effect this control increases radiation exposure and radioactive wastes, increases costs and manpower needs, and produces unnecessary administrative burdens. By approaching the problem in a systematic manner and applying various techniques, control is attainable. This paper presents methods which have been cost effective and successful in the control of radioactive contamination

[en] Major reactor accidents, such as that at the Stationary Low Power No. 1 Reactor in January 1961 and at the Three Mile Island, Unit 2, in March 1979 have shown the need for improvement in health physics programs to mitigate the consequences of such accidents. Salient needed improvements include: emergency response planning, facilities and training; plant management control over emergency operations; plant staffing levels; staff technical competence; system leakage control; additional plant shielding; higher range effluent monitors; higher range radiation monitors; higher range survey meters; and improved emergency communication. The described accidents and radiological incidents show the need for comprehensive radiological routine and emergency training in order to properly respond to changing circumstances in unusual occurrences

[en] Applications of modern computer network technology in the areas of nuclear power plant nuclear radiation monitoring and measurement are presented from the perspective of the analyst. A specific laboratory-based analytical instrumentation system network application in a multi-plant electric utility company is described. Brief mention is made of the inclusion of a mobile radioanalytical facility into the analytical instrumentation network. The concept of a plant-wide nuclear radiation monitoring system network is also presented. Throughout, emphasis is placed on the use of well-defined terminology and concepts. Definitions of terms and concepts are presented in the hope of eliminating some of the existing conflicting usage. The roles of the professional health physicist and the professional analyst in the implemenation of modern technology and in the assurance of technical integrity are discussed

[en] Each stage of the nuclear fuel cycle involves some release of waste radionuclides to the environment. The role of numerical modeling in assessing the environmental impact of these releases has increased in recent years due to the complexity of the issues involved: potential health effects, economics, and in some cases, the welfare of unborn generations. These issues require evaluation and examination in a systematic, reproducible manner. The objective of numerical modeling is to provide the decision maker with a synthesis of knowledge from many disciplines organized in a logical and coherent fashion. In a more limited application, radiological modeling is used to assess whether a proposed facility is designed in a manner to be operated within existing regulatory requirements or whether an operational facility is in compliance with regulatory requirements. This paper summarizes the present role of modeling for such decisions