Document: NUREG-1555
Document ID: 4539813b-f7f4-4dae-a8b5-d0be8df5b289
Document Type: esrp
Title: REACTOR POWER CONVERSION SYSTEM
Source: NUREG-1555
Source URL: https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1555/initial/
Revision Date: 2007-10
Chapter: 3
Section ID: 3.2
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Content:
ons (NRC 1976), with respect to the inclusion of information concerning the reactor-power conversion system. ` Generic determinations have been made that the environmental effects of transportation of spent fuel are bounded by those in Table S-4 for enrichment up to 5% uranium-235 by weight and fuel irradiation to 62,000 megawatt days per ton, provided that the fuel is shipped more than 5 years after discharge from the reactor (NRC 1996, NRC 1999a, 64 FR 48496). Technical Rationale The technical rationale for evaluation of the applicant’s reactor-power conversion system description is discussed in the following paragraph: A description of the overall nuclear energy generating system being proposed is crucial background information to the evaluation of any associated environmental impacts resulting from the proposed project. The reactor type, number of units, thermal-power level, and other factors influence the size and the performance of the facility and are required to assess the environmental impacts of the plant operation, transportation of fuel and waste, and the irreversible and irretrievable commitment of materials. III. REVIEW PROCEDURES These review procedures are used for applications for early site permits, construction permits, and com- bined licenses. Because the material to be reviewed is informational in nature, no specific analysis of the data is required. Ensure that adequate information is available to meet the purpose and scope of this ESRP. When reviewing the reactor-power conversion system, the reviewer should take the following steps: (1) Compare the proposed design parameters with those of similar operating plants and identify any fea- tures of the proposed system that represent a departure from previously reviewed plants. (2) Identify the reactor-power conversion and engineered safety feature systems and the basic design- performance data. As a rule, if the data listed under “Data and Information Needs” above are provided, this objective