Document: NUREG-0800
Document ID: 577b52cf-90e2-467e-8165-a1ce02957947
Document Type: srp
Title: REACTOR WATER CLEANUP SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070438.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.8
CFR Part: 
CFR Title: 

Content:
ross rupture. GDC 14 applies because the materials used in the reactor coolant system require careful control. Thus, reactor cooling water chemistry and levels of impurities must be monitored to avoid deterioration of the reactor coolant pressure boundary by general corrosion or by intergranular stress corrosion cracking (IGSCC). IGSCC results from the simultaneous occurrence of aggressive water environment, susceptible material, and tensile stress conditions. Should general corrosion or IGSCC occur, leakage, failure, or gross rupture could result. The RWCS provides a means of controlling reactor cooling water chemistry and levels of impurities. In addition, parts of the RWCS connected directly to the reactor coolant system must be fabricated to the same standards as the reactor coolant system. Meeting the requirements of GDC 14 provides assurance that failure of the reactor coolant pressure boundary because of general corrosion or IGSCC will not occur, thus decreasing the potential for a loss-of-coolant accident. 58 D. Compliance with GDC 60 requires that the nuclear 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. 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 provides assurance that releases of radioactive materials during normal operation and during anticipated operational occurrences will not result in onsite radiation doses exceeding the limits specified in 10 CFR Part 50,