Document: NUREG-0800
Document ID: ccdd2795-5741-481a-9873-fd92f6379656
Document Type: srp
Title: CONDENSATE STORAGE FACILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550046.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.6
CFR Part: 
CFR Title: 

Content:
transfer heat from SSCs important to safety to an ultimate heat sink is provided. In addition, the CSF can transfer the combined heat load of these SSCs under normal operating and accident conditions, assuming loss of offsite power and a single failure, and that system portions can be isolated so the safety function of the system is not compromised. 4. Condensate Storage Facility Inspection. Information that addresses the requirements of GDC 45 regarding the inspection of cooling water systems will be considered acceptable if the design of the CSF permits inservice inspection of safety-related components and equipment and operational functional testing of the system and its components. 5. Condensate Storage Facility Testing. Information that addresses the requirements of GDC 46 regarding the testing of cooling water systems will be considered acceptable if the CSF is designed for testing to detect degradation in performance or in the system pressure boundary so that the CSF will function reliably to provide decay heat removal and essential cooling for safety-related equipment. 6. Control of Radioactive Releases to the Environment. Acceptance for meeting the relevant aspects of GDC 60 is based on meeting the guidance of Regulatory Guide 1.143. 7. Loss of All Alternating Current Power. Acceptance for meeting the relevant aspects of 10 CFR 50.63 is based on meeting the guidance of Regulatory Guide 1.155. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 9.2.6-6 Revision 3 - March 2007 1. GDC 2 requires that nuclear power plant SSCs important to safety be designed to withstand the effects of seismic events and other natural phenomena without losing the capability to perform their safety functions. The subject SSCs are those necessary to ensure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shut down the