Annual ReportThe Commission, 1979 |
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Page 6
... core melt , and containment integrity . Also , a new study has begun into simulators , control rooms , and human factors in nuclear power plant operations . The accident has also underscored the need to apply the fault - tree / event ...
... core melt , and containment integrity . Also , a new study has begun into simulators , control rooms , and human factors in nuclear power plant operations . The accident has also underscored the need to apply the fault - tree / event ...
Page 13
... core and removing its decay heat ( about 7 percent of its normal operating heat production ) . The relief valve did not close . At this same time , several pumps came on automatically on the secondary side to restore feedwater flow and ...
... core and removing its decay heat ( about 7 percent of its normal operating heat production ) . The relief valve did not close . At this same time , several pumps came on automatically on the secondary side to restore feedwater flow and ...
Page 14
... core to boil , and steam voids or bubbles had formed within the primary system between the reactor core and the coolant in the pressurizer . Under such conditions , the level of coolant in the pressurizer would not disclose the amount ...
... core to boil , and steam voids or bubbles had formed within the primary system between the reactor core and the coolant in the pressurizer . Under such conditions , the level of coolant in the pressurizer would not disclose the amount ...
Page 15
... ( core and control rods ) and through which the reactor coolant flows , carrying heat away from the core to the steam generators . The TMI - 2 reactor contains 177 fuel assemblies with 208 fuel rods in each assembly . ( B ) REACTOR ...
... ( core and control rods ) and through which the reactor coolant flows , carrying heat away from the core to the steam generators . The TMI - 2 reactor contains 177 fuel assemblies with 208 fuel rods in each assembly . ( B ) REACTOR ...
Page 16
... core , indicating inadequate flow of coolant through the core . As a result of fuel damage , the con- centration of radioactivity in the reactor coolant in- creased by several orders of magnitude . A flow of this highly contaminated ...
... core , indicating inadequate flow of coolant through the core . As a result of fuel damage , the con- centration of radioactivity in the reactor coolant in- creased by several orders of magnitude . A flow of this highly contaminated ...
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Expressions et termes fréquents
actions activities agencies analysis application areas assessment assurance Commission Commissioner Committee construction permit containment control room core cracking criteria decay heat effects Electric emergency planning emergency response Energy environmental impact equipment evaluation Federal feedwater fiscal year 1979 fuel cycle health and safety IAEA identified implementation improve investigation Laboratory low-level waste ment NRC staff NRC's nuclear facilities Nuclear Plant nuclear power plants Nuclear Reactor Nuclear Regulatory Commission operating license personnel piping potential power reactor pressure pressurized water reactor procedures proposed protection radiation radioactive materials radioactive waste radiological reactor coolant recommendations regulations requirements result revised safeguards safety-related scram seismic shipments shutdown special nuclear material specific spent fuel standards Station steam Task Force technical Three Mile Island tion TMI accident transportation Unit uranium mills utility valve waste management water hammer water reactor
Fréquemment cités
Page 284 - ... the Atomic Energy Act of 1954, as amended; the Energy Reorganization Act of 1974. as amended; and the...
Page 82 - Design bases for protection against natural phenomena. Structures, systems, and components important to safety shall be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions.
Page 30 - NRC that the state of onsite and off site emergency preparedness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
Page 64 - A public hearing is not mandatory at this stage, but one may be held if requested by affected members of the public or at the initiative of the Commission. Each license for operation of a nuclear reactor contains technical specifications which set forth the particular safety and environmental protection measures to be imposed upon the facility and the conditions that must be met for the facility to operate.
Page 184 - ... to assure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded.
Page 286 - Commission deems appropriate to the issues to be decided, to conduct such hearings as the Commission may direct and make such intermediate or final decisions as the Commission may authorize with respect to the granting, suspending, revoking or amending of any license or authorization under the provisions of this Act, any other provision of law, or any regulation of the Commission issued thereunder.
Page 35 - To prevent nuclear accidents as serious as Three Mile Island, fundamental changes will be necessary in the organization, procedures, and practices — and above all — in the attitudes of the Nuclear Regulatory Commission and, to the extent that the institutions we investigated are typical, of the nuclear industry.
Page 65 - SEC. 210. The Commission shall develop a plan providing for specification and analysis of unresolved safety issues relating to nuclear reactors and shall take such action as may be necessary to implement corrective measures with respect to such issues. Such plan shall be submitted to the Congress on or before January 1, 1978 and progress reports shall be included in the annual report of the Commission thereafter.
Page 73 - Anticipated operational occurrences. Anticipated operational occurrences mean those conditions of normal operation which are expected to occur one or more times during the life of the nuclear power unit...
Page 299 - Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation...