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
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CFR Title: 

Content:
nd generic letters) are performed under SRP Chapter 1, “Introduction and Interfaces,” Items 1.8 and 1.9. 3. The review of the exclusion area boundary and administrative controls in managing liquid effluent releases is performed using the guidance in SRP Sections 2.1.2, “Exclusion Area Authority and Control,” and 11.5, “Process and Effluent Radiological Monitoring Instrumentation and Sampling Systems.” 4. The review of the impacts of an accidental release of radioactive liquids in groundwater or surface water and effects on existing users or likely future users of groundwater or surface water resources is performed using the guidance in SRP Sections 2.4.1, “Hydrologic Description”; 2.4.12, “Groundwater”; and 2.4.13, “Accidental Releases of Radioactive Liquid Effluents in Ground and Surface Waters”; and information and guidance from Branch Technical Position (BTP) 11-6, “Postulated Radioactive Releases Due to Liquid-containing Tank Failures”; as referenced herein. 5. The review of independent source term calculations for the purpose of assessing the performance of the LWMS against NRC requirements of 10 CFR 20.1301 and 10 CFR 20.1302; Table 2, Column 2 and Note 4 of Appendix B to 10 CFR Part 20; and design objectives and ALARA provisions of Appendix I to 10 CFR Part 50, is performed under SRP Section 11.1, “Coolant Source Terms,” using the guidance in RG 1.112, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors,” NUREG-0016, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWRs),” or NUREG-0017, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWRs),” and American National Standards Institute/American Nuclear Society (ANSI/ANS) 18.1-1999, as modified to reflect specific design features. 6. The review of dose calculation methods