Document: NUREG-0800
Document ID: 8536691d-4254-4c01-a5ec-aa9dee960958
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740509.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
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Content:
ents. 4. Appendix I to 10 CFR Part 50 provides numerical guides for the ALARA criterion for radioactive materials released by light-water-cooled nuclear power reactors. 10 CFR 50.34a and 10 CFR 50.36a contain provisions designed to ensure that releases of radioactive materials, as liquid and gaseous effluents, from nuclear power reactors to unrestricted areas during normal operation, including AOOs, are ALARA. Appendix I provides specific numerical criteria and guidance for meeting this requirement. Meeting the requirements of the ALARA criterion provides reasonable assurance that offsite doses to any individual from normal operation and from AOOs will not result in exposures in excess of the numerical guides specified in Section II of Appendix I to 10 CFR Part 50. The review conducted in this SRP section, with supporting information drawn from SRP Sections 11.2, 11.3, and 11.4, evaluates the method used to demonstrate compliance with these requirements. 5. Compliance with GDC 60 requires that the nuclear power plant design include mechanisms to control the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid wastes produced during normal reactor operation, including AOOs. GDC 60 applies to SRP Section 11.5 because mechanisms to control the release of radioactive effluents must include, among other components, equipment and related operating procedures to provide monitoring, sampling, and surveillance of effluent streams that may contain radioactive materials. RG 1.143 includes guidance on the design of radioactive waste management SSCs. Meeting the requirements of GDC 60 provides reasonable assurance that releases of radioactive materials during normal operation and AOOs will not result in offsite radiation doses that exceed the limits and design objectives specified in the regulations. The review conducted in this SRP section, with supporting information drawn from SRP Sections 11.2, 11.3, and 11.4, evaluates the method