Document: NUREG-0800
Document ID: 73148264-0cb4-4b1b-8586-3105a0a46c78
Document Type: srp
Title: REACTOR WATER CLEANUP SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190009.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.8
CFR Part: 
CFR Title: 

Content:
r power unit design shall include a suitable means 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. 5.4.8-8 Revision 3 - March 2007 GDC 60 applies because the RWCS is used to purify the reactor coolant. As such, gaseous, liquid, and solid radioactive materials will be accumulated within the system and will have the potential for discharge to the environment unless gaseous effluents, spent demineralizer resins, and liquid effluents are collected in closed systems and discharged to the radwaste system for processing and disposal. Meeting the requirements of GDC 60 minimizes the probability that releases of radioactive materials during normal operation or anticipated operational occurrences would result in onsite radiation doses exceeding the limits specified in 10 CFR Part 50, Appendix I, or offsite radiation doses exceeding those specified in 10 CFR Part 20. 5. Compliance with GDC 61 requires that the fuel storage and handling, radioactive waste, and other systems that may contain radioactivity shall be designed to ensure adequate safety under normal and postulated accident conditions. GDC 61 applies because the RWCS is used to purify the reactor coolant. As such, gaseous, liquid, and solid radioactive materials will be accumulated within the system and will have the potential for discharge to the environment. Meeting the requirements of GDC 61 minimizes the probability that releases of radioactive materials during normal operation or anticipated operational occurrences would result in radiation doses exceeding the limits specified in 10 CFR Part 20. In addition, meeting the GDC 61 requirements minimizes the probability that the system would fail under postulated accident conditions. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a