Document: NUREG-0800
Document ID: a416cfea-d766-4e80-9d15-6ac4918475fa
Document Type: srp
Title: REACTOR COOLANT SYSTEM COMPONENT AND SUBSYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070610167.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4
CFR Part: 
CFR Title: 

Content:
of materials engineering issues related to flaw evaluation and welding evaluates RCP flywheel integrity under SRP Section 5.4.1.1, “Pump Flywheel Integrity (PWR).” 5.4-4 Revision 2 - March 2007 L. The organization responsible for the review of instrumentation and controls assesses the instrumentation and control aspects to confirm that reactor and plant protection and safeguard controls and instrumentation systems will function as assumed in the safety analysis under SRP Sections 7.2 through 7.5. M. The organization responsible for review of transient and accident analysis for PWRs/BWRs reviews expected transients under SRP Sections 15.3.1-15.3.2, “Loss of Forced Reactor Coolant Flow Including Trip of Pump Motor and Flow Controller Malfunctions.” N. The organization responsible for the review of transient and accident analysis for PWRs/BWRs evaluates RCP rotor seizure or shaft break under SRP Sections 15.3.3 - 15.3.4, “Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break.” 2. Steam Generators A. The organization responsible for mechanical engineering reviews assesses methods of analysis (e.g., seismic and vibratory loadings [including those due to fluid flow and adverse flow conditions], and dynamic analyses), and the structural and functional integrity of steam generators under SRP Sections 3.9.1, 3.9.2, and 3.9.3. B. The organization responsible for the review of component integrity issues related to steam generator tubes evaluates the materials used to fabricate the steam generator, and the steam generator tube inservice inspection operational program. This evaluation of materials and design provisions is performed under SRP Section 5.4.2.1, “Steam Generator Materials,” while the evaluation of the steam generator tube inservice inspection operational program is performed under SRP Section 5.4.2.2, “Steam Generator Program.” C. The organization responsible for the review of component integrity issues related to reactor