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NUREG 0933
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Displaying 76 - 100 of 147
DESCRIPTION This issue was identified in NUREG-0471 [1] and addressed the concerns that the validity of the mathematical models used to predict the performance of dedicated ponds, spray ponds, and cooling towers had not been confirmed, and that better …
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DESCRIPTION This NUREG-0471 [1] task involved the preparation of a paper detailing the bases for design basis flood events utilized by the staff in case reviews, including probable maximum floods, hurricanes, tsunamis, seiches, seismically-induced dam …
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DESCRIPTION Historical Background This issue, as originally stated in 1978, [1] addressed the unavailability (at that time) of a suitable model to predict the erosion rates and, therefore, the flood hydrographs at nuclear power plant sites resulting from …
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DESCRIPTION Historical Background This issue was identified in NUREG-0471 [1] and addressed the concern that additional information was needed on the potential effects of extreme cold weather and ice buildup on the reliability of various plant water …
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DESCRIPTION This NUREG-0471 [1] task involves the maintenance and improvement of calculational capabilities for assessing doses to individuals from radiation and radioactive effluents from normal operation and from radioactive releases from postulated …
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DESCRIPTION Compilation of occupational radiation exposure reports from operating reactors has shown that exposures to station and contractor personnel have generally been increasing over the past 7 years for both PWRs and BWRs. The overriding problem at …
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DESCRIPTION This NUREG-0471 [1] task involves evaluating information from semiannual operating reports, inplant measurements program and topical reports, and revisions to models for calculating releases of radioactive materials in effluents from PWRs and …
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DESCRIPTION This NUREG-0471 [1] item involves developing revisions to current guidance and staff technical positions regarding ESF and normal ventilation system air filtration and adsorption units. This involves developing revisions to Regulatory Guide …
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DESCRIPTION In accordance with licensing responsibilities under the National Environmental Policy Act (NEPA), the NRC is responsible for assessing the impact of licensee's discharges into surface waters. The objective of this assessment is to afford a …
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DESCRIPTION NRC environmental information needs for licensing fall into the categories of: (1) detailed site-specific investigations at a preferred site, and (2) reconnaissance level information to support alternative site assessment and selection, …
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DESCRIPTION This NUREG-0471 [1] task involves two activities: (1) The United States Department of Interior (DOI) is preparing a handbook which will set forth practices for siting and managing transmission line corridors for the betterment of …
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DESCRIPTION The effects of entrainment on phytoplankton and zooplankton populations are often minimal and occasionally beneficial. Numerous studies of the effects of entrainment on plankton organisms, phytoplankton, and zooplankton have shown impacts to …
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DESCRIPTION This NUREG-0471 [1] task involves studies related to the impacts of power plant operation on fishery resources. Possible studies to be undertaken are described below: (1) In recent years, an attempt has been made at a number of …
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DESCRIPTION As part of the cost-benefit analysis of nuclear power plant licensing applications, the NRC is required to assess likely socioeconomic impacts of power plant construction and operation on local communities and the surrounding region. This …
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DESCRIPTION The technique of aerial photography has a long established and proven utility for earth resource inventory and evaluation. Applicants for nuclear construction permits are becoming aware of this and are making increasing use of aerial …
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DESCRIPTION In the performance of NEPA obligations to evaluate alternatives to the proposed action, the staff must reach a conclusion as to the comparative costs of generating power among the feasible alternatives. While alternatives other than coal are …
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DESCRIPTION This NUREG-0471 [1] task is included in Item B-2. CONCLUSION This Environmental issue is covered in Item B-2. [1] NUREG-0471, "Generic Task Problem Descriptions (Categories B, C, and D)," U.S. Nuclear Regulatory Commission, June …
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DESCRIPTION Frequently, regulatory changes are made in the applicant's proposal for design and/or operation of systems or subsystems based on perceived needs to mitigate impacts on the environment. Also, differences in design and/or operation are an …
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DESCRIPTION According to NUREG-0471, [1] the safety concern in this issue relates to results from inspections of various structural components in the torus support systems of operating BWRs. These inspections have revealed several inconsistencies between …
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DESCRIPTION Surface cracks have been discovered in control rod drive internal parts at some operating BWR plants. Although only observed to be localized in nature, this cracking, if propagated, could potentially affect the capability of the control rod …
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DESCRIPTION GDC-53, "Provisions for Containment Testing and Inspection," requires in part that the reactor containment be designed to permit: (1) periodic inspection of all important areas, and (2) an appropriate surveillance program. 10 CFR 50, Appendix …
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DESCRIPTION Historical Background Appendix A of CFR 10 Part 100 specifies that the operating basis earthquake (OBE) shall be defined by response spectra and that the maximum vibratory ground acceleration of the OBE shall be at least one-half of the …
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DESCRIPTION In the design of nuclear power plants, inelastic response of equipment and components due to severe transients from low probability events is permitted in the ASME Boiler and Pressure Vessel Code, Section III, Subsection NA, Appendix F. Local …
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DESCRIPTION The fuel assembly is a highly nonlinear structure which can be subjected to substantial loadings during seismic excitations and LOCA transients. The integrity of this assembly is critical for plant safety. Extensive work has been completed by …
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DESCRIPTION Historical Background This NUREG-0471 [1] item arose in the course of the NRC review of the McGuire application, where the applicant proposed relying on the generator load break switch for isolating the generator from the stepup transformer …
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Page Last Reviewed/Updated 3/1/2026
Disclaimer: Some of the formatting in NUREG-0933 may not be correct. We are currently working on fixing the formatting.