Document: NUREG-0800
Document ID: 9e3f4564-4ddf-4369-b699-a42709a80b66
Document Type: srp
Title: CONTAINMENT SPRAY AS A FISSION PRODUCT CLEANUP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0701/ML070190178.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.2
CFR Part: 
CFR Title: 

Content:
ditives, and any metering pumps or mixing devices. B. Tests. Preoperational testing of the system, including the additive storage tanks, pumps (if any), piping, and valves, is required. In particular, the preoperational testing should verify that the system, as installed, is capable of delivering a well-mixed solution containing all additives in concentrations that are within the design margins assumed in the dose analyses of SAR Chapter 15. Periodic testing and exercising of all active components should include the spray pumps, metering pumps (if any), and valves. Confirmation should be made periodically that passive components, such as all essential spray and spray additive piping, and any passive mixing devices are free of obstructions. The contents of the spray additive storage tanks should be sampled and analyzed periodically to verify that the concentrations are within the established limits, that no concentration gradients exist, and that no precipitates have formed. 4. Fission Product Removal Effectiveness (primary reviewer). The fission product removal effectiveness of the system is calculated to establish the degree of dose mitigation by the containment spray system following the postulated accident. The mathematical model used for this calculation should reflect the preceding steps of the review. The analysis and assumptions are as follows: A. The amounts of fission products assumed to be released to the containment space are obtained from Regulatory Guide 1.3, Regulatory Guide 1.4, or Regulatory Guide 1.183, as appropriate1. The amounts of airborne fission 6.5.2-11 Revision 4 - March 2007 product inside the containment building depend on plateout on interior surfaces, removal by the spray system and other engineered safety features present, radioactive decay, and outleakage from the containment building. If the value in Position C.1.a of Regulatory Guides 1.3 and 1.4 is used in the calculation of fission product removal, then deposition by plateout, as