[en] A survey is presented of the discussion on location sites for nuclear power plants in the Netherlands and the USA. It consists of two parts (A and B). This part (A) presents a summary of the discussion in the Netherlands. The name and contents of the reports which have been published are indicated briefly. Many of the Dutch reports refer to American studies on reactor safety. In order to obtain a good survey of these a description is presented of the development of the discussion in the USA after the publication of the well-known reactor safety study WASH-1400. After this survey of five important reports, an introduction is presented dealing with the background of the authors, the purposes, the main conclusions and the most salient points of criticism formulated by others. Under discussion are the reports of the IDCOR (nuclear power industry), ANS (American Nuclear Society), APS (American Physical Society), NRC (Nuclear Regulatory Commission) and UCS (Union of Concerned Scientists). 38 refs.; 5 figs.; 5 tabs

[en] Requirements put on the preliminary and pre-operation safety reports on radioactive waste depositories, as following from Czechoslovak regulations No. 85/1976 and 67/1987, are commented on. Basic approaches to the compilation of the required documentation are described, and practical experience gained during its writing is discussed. (author). 18 refs

[en] A survey is presented of the discussion on location sites for nuclear power plants in the Netherlands and the USA. It consists of two parts (A and B). This part (B) goes farther into the American reports already introduced briefly in part A. They are the reports of the IDCOR (nuclear power industry), ANS (American Nuclear Society), APS (American Physical Society), NRC (Nuclear Regulatory Commission) and UCS (Union of Concerned Scientists). Of each report a summary in English and an extended summary in Dutch is presented. Parts of the text of chapter 3 of the report 'Reactor accidents: the source term discussion' of the Technical University Twente (BC8501, 1985) are presented. 65 refs.; 15 figs.; 32 tabs

[en] Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

[en] A report of a seminar on The Review of Safety at Magnox Nuclear Installations is presented. Main theme was the long term safety review (LTSR) which comes into operation once the plant life is extended to beyond 20 years. Calder Hall and Chapelcross, pressure vessels, post-trip cooling, probabilistic safety analysis, steel pressure circuits, modern standards and the biological shield integrity are discussed. (U.K.)

[en] The safety of a nuclear power plant is guaranteed for by its design, the maintenance and management operations, by refurbishing and periodical overhauling. The conditions for the operation permission are discussed, as are the safety report and the probabilistic safety analysis. It can be shown that the nuclear power plant meets today's safety requirements and therefore can be operated safely

[en] Risk can best be understood in terms of its converse, safety, which is freedom from the totality of risk. Safety can be expressed quantitatively as life expectancy. The rapid rate of increase of safety in Canada during the last century and in today's world is reviewed. It is proposed that the vector combination of the rate of improvement of wealth and the rate of increase of life expectancy should be used as a quantitative safety goal. Proposals are made for research, policies and action to manage and improve safety. A prospect for the next century is outlined

[en] A survey and comparison has been made of 10 widely disseminated safety goal proposals originating in Canada, the U.K. and the U.S. When the proposals are placed in a directly comparable numerical context, they are remarkably similar in the inferred levels of safety. The development of quantitative safety goals by the U.S. Nuclear Regulatory Commission is also reviewed. While progress has been made in structuring technically and politically defensible goals, because of the way the regulatory philosophy has evolved in the U.S., the implementation of such goals could well turn out to be more difficult than defining the goals themselves. The safety goals are useful in providing guidance to the designers, operators and regulators of nuclear power plants with regard to public safety concerns as well as plant reliability and engineering considerations. (author)

[en] Guidelines have been developed for improving 10CFR50.59 safety evaluation. The guidelines were prepared by an industry committee and extensively reviewed by industry and the NRC. An important and difficult function of the guidelines is to define the thresholds for unreviewed safety questions. The guidelines also cover the applicability of 10CFR50.59 and the process of performing 10CFR50.59 safety reviews for facility changes, tests or experiments at nuclear power plants. (author)

[en] Published in summary form only