Document: NUREG-0800
Document ID: 0dcda381-7ccf-499e-b926-b844f97fc4cf
Document Type: srp
Title: MAIN CONDENSERS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070586.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.1
CFR Part: 
CFR Title: 

Content:
t (CP) review to determine that the design criteria and bases and the preliminary design meet the acceptance criteria given in subsection II. For the review of operating license (OL) applications, the procedures are used to verify that the initial design criteria and bases have been appropriately implemented in the final design as set forth in the final safety analysis report. The reviewer will select and emphasize material from this SRP section as may be appropriate for a particular case. The primary reviewer will coordinate this review with other branches' areas of review as stated in subsection I. The primary reviewer obtains and uses such input as required to assure that this review procedure is complete. 1. The SAR is reviewed to determine that the system description delineates the main condenser system capabilities including the minimum system heat transfer and system flow requirements for normal plant and turbine bypass operation. Measures provided to prevent loss of vacuum, corrosion and/or erosion of MC tubes and components, and hydrogen buildup in the MC are reviewed, with particular emphasis on these measures for direct cycle (boiling water reactor) plants. System performance requirements are reviewed to determine that they satisfactorily limit possible system degradation conditions (e.g., leakage, partial loss of vacuum) and describe the procedures that are followed to detect and correct these conditions. The SAR is also reviewed to determine 25 that any allowed MC system degraded operation does not have an adverse effect on the reactor primary system or secondary system in the case of pressurized water reactors. The SAR is also reviewed to determine if the MC will be relied upon for plateout of fission products following core damage (applicable only to new BWRs with no main steam isolation valve leakage control system). If this is the case, a seismic analysis should be performed to ensure that the condenser anchorages and the piping inlet nozzle to the