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NUREG 0933
Displaying 151 - 175 of 458
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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DESCRIPTION Historical Background This NUREG-0471 [1] item deals with two concerns regarding the ice condenser containment design. The first concern arises from an ACRS comment on the D. C. Cook Unit 1 review. The normal procedure used by the staff (CSB) …
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DESCRIPTION The BWR pressure relief system is designed to prevent overpressurization of the reactor coolant pressure boundary (RCPB) under the most severe abnormal operational transient: closure of the main steam line isolation valves (MSIVs) with failure …
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DESCRIPTION Historical Background This issue was documented in NUREG-0471 [1] and resulted from a review of LERs which indicated that onsite emergency diesel generators (EDGs) at operating plants were demonstrating an average starting reliability of about …
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DESCRIPTION This NUREG-0471 [1] task will make a determination as to whether plants should be designed to accommodate a total loss of all AC power for a limited period of time. CONCLUSION This issue is covered in USI A-44, "Station Blackout." [1] …
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DESCRIPTION Historical Background This NUREG-0471 [1] task involves a review of valve failure data in a systematic manner to verify the staff's present judgment regarding the likelihood of passive mechanical valve failures, to categorize these and other …
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DESCRIPTION Historical Background The majority of the presently operating BWRs and PWRs are designed to operate with less than full reactor coolant flow. If a PWR RCP or a BWR recirculation pump becomes inoperative, the flow provided by the remaining …
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DESCRIPTION The presence of a loose (i.e., disengaged and/or drifting) object in the primary coolant system can be indicative of degraded reactor safety resulting from failure or weakening of a safety-related component. A loose part, whether it be from a …
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DESCRIPTION Historical Background This issue was identified in NUREG-0471 [1] and addressed the establishment of surveillance test intervals and allowable equipment outage periods, using analytically-based TS criteria and methods. At the time the issue …
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DESCRIPTION The methods used to establish safe operating limits for reactor cores were developed about 10 years ago. At present, safety margins are reviewed utilizing previous staff judgments based on individual plant reviews. A uniform staff position …
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DESCRIPTION There are several systems connected to the reactor coolant pressure boundary that have design pressures that are considerably below the reactor coolant system operating pressure. The NRC has required that valves forming the interface between …
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Page Last Reviewed/Updated 3/1/2026
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