Document: NUREG-1555
Document ID: 9b3af5e8-9e20-4e8d-a5b0-6ef244d48fb6
Document Type: esrp
Title: RADIOACTIVE WASTE MANAGEMENT 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: 3.5
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actors (NRC 1977), with respect to determining the releases of radioactive effluents from power reactors ` NUREG-0016, Calculations of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-water reactors (NRC 1976a), with respect to determining the releases of radioactive effluents from a boiling-water reactor (BWR) ` NUREG-0017, Calculations of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized-water reactors (NRC 1976b), with respect to determining the releases of radioactive effluents from a pressurized-water reactor (PWR) NUREG-1555 3.5-4 October 1999 ` Regulatory Guide 4.2, Preparation of Environmental Reports for Nuclear Power Stations (NRC 1976c), with respect to determining the benefit-cost of waste-management systems. Technical Rationale The technical rationale for evaluating the applicant’s radioactive waste management system is discussed in the following paragraph: All light-water-cooled reactors release small quantities of radioactive materials to the environment. The criteria for these releases are addressed in 10 CFR 50, Appendix I, and additional requirements are in 10 CFR 20, Subpart K, and the values are in 10 CFR 20, Appendix B, Table 2 or 3 (as appropriate). Radioactive waste management and effluent control systems are to be designed to minimize the radioactive material releases from reactors to be ALARA. Evaluation of the releases against the requirements in 10 CFR 50, Appendix I, and 10 CFR 20 provide validation that radioactive waste management systems are adequate to protect the environment and minimize the effects of radiation to the public. III. REVIEW PROCEDURES The detailed analysis and evaluation of the radioactive waste management and effluent control systems and the capability of these systems to meet the requirements of 10 CFR 20, Subparts D and K; 10 CFR 50, Appendix I; and 10 CFR 20.1301(d) should be presented in the staff’s safety evaluation report (SER). The SER should be