Document: NUREG-0800
Document ID: 3ab8ae04-e11b-4993-a907-f644301c5af2
Document Type: srp
Title: MAIN STEAM SUPPLY SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070577.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.3
CFR Part: 
CFR Title: 

Content:
shutdown can be achieved with dependence upon safety-grade components only. f. The system design capability can withstand adverse dynamic loads, such as water (steam) hammer resulting from rapid valve closure and relief valve fluid 10 discharge loads. 2. The SPLBASB reviews the MSSS with regard to measures provided to limit blowdown 11 of the system in the event of a steam line break. 3. For plants in which the design relies on the MSSS in response to a station blackout (SBO), SPLB reviews the MSSS to assure conformance with 10 CFR 50.63. 12 10.3-3 DRAFT Rev. 4 - April 1996 34. The SPLBASB and PSB also reviews the design of the MSSS with respect to the 13 14 following: a. The functional capability of the system to transport steam from the nuclear steam supply system as required during all operating conditions. b. The capability to detect and control system leakage, and to isolate portions of the system in case of excessive leakage or component malfunctions. c. The capability to preclude accidental releases to the environment. d. Provisions for functional testing for safety-related portions of the system. Review Interfaces:15 4. The SPLBASB also performs the following reviews under the SRP sections indicated: 16 1a. Review for flood protection is performed under SRP Section 3.4.1. 2b. Review of the protection against internally generated missiles outside containment is 17 performed under SRP Section 3.5.1.1. 3. Review of the protection against internally generated missiles inside containment is performed under SRP Section 3.5.1.2.18 4c. Review of the structures, systems, and components to be protected against externally generated missiles is performed under SRP Section 3.5.2. 5d. Review of high- and moderate-energy pipe breaks is performed under SRP Section 3.6.1. 6. Review of the environmental qualification of components is performed under SRP Section 3.11.19 7. Review of the Main Steam Isolation Valve Leakage Control System is performed under SRP Section 6.7. 20 8.