Document: NUREG-0800
Document ID: 74415b71-98a0-4109-9ba7-8a72a89a3d18
Document Type: srp
Title: ULTIMATE HEAT SINK
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070520.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.5
CFR Part: 
CFR Title: 

Content:
e availability of the source water. The UHS is also reviewed to assure ensure that 5 adverse environmental conditions including freezing will not preclude the safety function of the UHS. e. Sharing of cooling water sources in multi-unit stations. f. Applicable design requirements such as the high- and low-water levels of the source to determine their compatibility with the service water system. 2. ASBSPLB reviews the station heat input provided in the safety analysis report (SAR) 6 7 for the design of the UHS with respect to reactor system heat, sensible heat, and pump work, and station auxiliary system individual and total heat loads. Portions of this review may be beyond the scope of the standard design certification application. The conceptual design and interface requirements will be reviewed for standard design certification. Detailed review will be performed for each site-specific application.8 Review Interfaces9 3. ASBSPLB also performs the following reviews under the SRP sections indicated: 10 a. Review of flood protection is performed under SRP Section 3.4.1, b. Review of the protection against internally generated missiles is performed under SRP Section 3.5.1.1, c. Review of the structures, system, and components to be protected against externally generated missiles is performed under SRP Section 3.5.2, and d. Review of high- and moderate-energy pipe breaks is performed under SRP Section 3.6.1., e. Review of the program of surveillance and control techniques to detect and control the incidence of flow blockage problems due to aquatic bivalves and other fouling due to mud, silt, or corrosion products under SRP Section 9.2.1, and 11 f. Coordination and review of fire protection is performed under SRP Section 9.5.1.12 9.2.5-3 DRAFT Rev. 3 - April 1996 In addition, ASBSPLB will coordinate other branch evaluations that interface with the overall 13 review of the system as follows: A. The Reactor Systems Branch (RSBSRXB ) will confirm the heat loads transmitted