Document: NUREG-0800
Document ID: 25e52c07-8f43-4a33-a908-01ec9eb02d06
Document Type: srp
Title: LIQUID WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1304/ML13044A644.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.2
CFR Part: 
CFR Title: 

Content:
f the requirements of 10 CFR 20.1406. Specific guidance to meet 10 CFR 20.1406 is identified in RG 4.21, Regulatory Positions C.1 through C.4. DC/COL-ISG-06 is incorporated in SRP Section 12.3-2.4. 3. Meeting the requirements of 10 CFR 50.34a, as they relate to the LWMS, provides assurance that each nuclear power reactor will meet the criterion that controlled releases of radioactive materials in effluents to unrestricted areas in its vicinity will be kept ALARA and that the LWMS will have the necessary design features and equipment to control releases of radioactive liquid effluents to the environment in accordance with the requirements of 10 CFR 20.1301 and 20.1302, Appendix I to 10 CFR Part 50, and GDC 60 and 61. See separate discussion below, on the requirements of 10 CFR Part 20.1301(e). 4. Appendix I to 10 CFR Part 50 provides numerical guides on design objectives to meet the requirements that radiation doses caused by radioactive materials in effluents released to unrestricted areas be kept ALARA. Sections II.A and II.D of Appendix I relate to the numerical guides for dose design objectives, limiting conditions for operation, and controls to meet the ALARA criterion for liquid effluents. RGs 1.109 and 1.113 provide acceptable methods for performing dose analyses to demonstrate that the LWMS design and its operation result in doses, due to releases of radioactive materials from each reactor, that comply with 10 CFR Part 50, Appendix I design objectives. 11.2-17 Draft Revision 5 – August 2014 RG 1.110 provides an acceptable method of performing cost-benefit analysis to demonstrate that the LWMS design includes all items of reasonably demonstrated technology for reducing cumulative population doses from releases of radioactive materials from each reactor to ALARA levels within an 80 km (50 mi) radius of the reactor and to comply with the cost-benefit ratio of Section II.D of Appendix I. Meeting the requirements of Section II.A of Appendix I to 10 CFR Part 50