Document: NUREG-0800
Document ID: ba7b8f31-872f-4ab8-bdf8-7be885afd4b6
Document Type: srp
Title: LIQUID WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A032.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.2
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Content:
cession ML081710264. 8. Clarification in developing design basis reactor coolant and reactor steam source terms when considering technical specification limits for halogens (I-131 dose equivalent) and noble gases (Xe-133 dose equivalent), as applied in analyses conducted in SRP Sections 11.1 and 11.3. 9. DC/COL-ISG-013, “Assessing the Radiological Consequences of Accidental Releases of Radioactive Materials from Liquid Waste Tanks for Combined License Applications,” as it relates to guidance on reviewing the analysis of the radiological consequences of accidental releases of radioactive materials to groundwater and surface water. 10. Clarification on the application of RG 1.143 acceptance criteria related to seismic, safety, and quality group classifications and quality assurance provisions for structures, systems, and components of the LWMS produced during normal operation and AOOs. RG 1.143 provides guidance in assigning safety classifications to structures and liquid waste management systems in protecting SSCs against natural phenomena and man- induced hazards. The acceptance criteria are revised to conform with 10 CFR Part 20 dose limits for members of the public and plant workers and their assumed locations in restricted areas for workers and unrestricted areas for members of the public. Also, the revised guidance refers to RG 1.206, Part I, C.I.3, Sections 3.2.1 and 3.2.2 and SRP Section 3.8.4 in identifying applicable acceptance criteria in evaluating SSCs requiring seismic design considerations and differences from the recommendations of RG 1.143. 11. Additional clarification is provided on the use of automatic control features and placement of isolation valves and radiation detectors on process piping and effluent discharge lines to ensure the timely closure of such valves upon the detection of elevated radioactivity levels, and, if part of the design, controls in monitoring deviations of in-plant dilution flow rates in terminating releases or isolating