Oversight--the Nuclear Regulatory Commission Research Program: Hearings Before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, U.S. House of Representatives, Ninety-seventh Congress, Second Session, May 18, 19; June 15, 1982 |
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Common terms and phrases
ACRS analysis ANSWER application behavior BOUQUARD budget computer codes confirmatory research conservatism containment coolant cooperation coordination core cooling criteria decay heat degraded core effects effort emergency engineering EPRI evaluation facility failure fission product fuel funding impact important improve reactor safety industry INPO LIBRARY OF CONGRESS licensing light water reactor LOCA loss-of-coolant accident LUJAN MINOGUE models needed NRC program NRC research program NRC staff NRC's nuclear power plants Nuclear Regulatory Commission Nuclear Regulatory Research nuclear safety Office of Nuclear operating PALLADINO performance piping potential priorities probabilistic risk assessment problems projects questions radioactive radionuclides reactor safety research recommended regulations release reliability requirements Research Plan response Review Group safety research program seismic severe accident SIESS source term specific subcommittee technical tests tion transients utilities waste management water hammer water reactor
Popular passages
Page 9 - Commission. (b) Subject to the provisions of this Act, the Director of Nuclear Regulatory Research shall perform such functions as the Commission shall delegate including: (1) Developing recommendations for research deemed necessary for performance by the Commission of its licensing and related regulatory functions.
Page 47 - Siess has been a member or chairman of numerous committees of the American Concrete Institute, the American Society of Civil Engineers, and other societies, and has been active in the preparation of structural design specifications and codes for both reinforced and prestressed concrete structures. He is a member of the National Academy of Engineering.
Page 21 - III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.
Page 17 - The Conference Report stated that "the basic purpose of this research is the improvement of reactor safety and not the enhancement of the economic attractiveness of nuclear power versus alternative energy sources.
Page 361 - NRC with regard to interagency relationships in the conduct of research programs and related activities.
Page 80 - Without objection, your prepared statement will be. included in the record and you may proceed in any manner you desire.
Page 6 - I and my colleagues will be glad to respond to any questions the Committee may have. The CHAIRMAN. I have an initial question.
Page 191 - ... other occupations recognized as having high standards of safety, which are generally considered to be those in which the average annual mortality due to occupational hazards does not exceed lO-4.
Page 206 - Regulation, the Office of Nuclear Material Safety and Safeguards, and the Office of Inspection and Enforcement primarily focus— the offices exist to examine these issues.
Page 168 - Therefore, the industry must also set and police its own standards of excellence to ensure the effective management and safe operation of nuclear power plants.