Document: NUREG-0800
Document ID: 13fda301-b942-4542-a493-fc1e4c60019b
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710438.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
controls, as stated in Generic Letter 89-01 and NUREG-1301 for PWRs and NUREG-1302 for BWRs. Meeting the requirements of 10 CFR 50.36a provides reasonable assurance that the levels of radioactivity in effluents from nuclear power plants will meet the ALARA criterion and result in doses to members of the public that are a small fraction of the 10 CFR 20.1301 limits. The review conducted in this SRP section, with supporting information from SRP Sections 11.2, 11.3, and 11.4, evaluates the method used to demonstrate compliance with these requirements. 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 anticipated operational occurrences, are ALARA. Appendix I provides specific numerical criteria and guidance for meeting this requirement. 11.5-11 Revision 4 - March 2007 Meeting the requirements of the ALARA criterion provides reasonable assurance that offsite doses to any individual from normal operation and from anticipated operational occurrences 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 anticipated operational occurrences. GDC 60 applies to SRP Section 11.5 because mechanisms to control the release of