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:
he staff concludes that the proposed design of reactor water cleanup system (RWCS) is acceptable and meets the relevant requirements of General Design Criteria 1, 2, 14, 60, and 61. This conclusion is based on the following: 1. The applicant has met the requirements of General Design Criterion 1 by designing, in accordance with the guidelines of Regulatory Guide 1.26, the portion of the RWCS extending from the reactor vessel and recirculation loops to the outermost primary containment isolation valves to Quality Group A and by designing, in accordance with position C.2.c of Regulatory Guide 1.26, the remainder of the RWCS outside the primary containment (excluding the precoating unit) to Quality Group C. 2. The applicant has met the requirements of General Design Criterion 2 by designing in accordance with positions C.1, C.2, C.3, and C.4 of Regulatory Guide 1.29, the portion of the RWCS extending from the reactor vessel and recirculation loops to the outermost primary containment isolation valves to seismic Category I. 3. The applicant has met the requirements of General Design Criterion 14 by meeting the positions of Regulatory Guide 1.56 in maintaining reactor water purity and material compatibility to reduce corrosion probabilities, and thus 73 reducing the probability of reactor coolant pressure boundary failure. 4. The applicant has met the requirements of General Design Criteria 60 and 61 by designing a system containing radioactivity with confinement and by venting and collecting drainage from the RWCS components through closed systems. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.74 V. IMPLEMENTATION The following