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:
ce 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 coolant pressure boundary (primary reviewer), and the organization responsible for component integrity issues related to reactor vessels (secondary reviewer), assess the inservice inspection of the steam generator shells under SRP Section 5.2.4. D. The organization responsible for the review of transient and accident analyses for PWRs/BWRs reviews the steam generator configuration and process design parameters and the response to various anticipated operational occurrences under SRP Sections 15.1.1 - 15.1.4, “Decrease in Feedwater Temperature, Increase in Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve,” and various other SRP Sections of Chapter 15. E. The organization responsible for the review of transient and accident analyses for PWRs/BWRS (primary reviewer), and the organization responsible for transient and accident analyses (secondary reviewer), assess the steam generator response to various anticipated operational occurrences and postulated accidents under SRP 15.1.5, “Steam System Piping Failures Inside and Outside of Containment (PWR),” and various other SRP Sections of Chapter 15. 5.4-5 Revision 2 - March 2007 F. The organization responsible for the review of transient and accident analyses for PWRs/BWRs evaluates the effects of a postulated feedwater-line break under SRP 15.2.8, “Feedwater System Pipe Break Inside and Outside Containment (PWR),” and various other SRP Sections of Chapter 15. G. The organization responsible for the review of transient and accident analysis for PWRs/BWRs (primary reviewer), and the organization responsible for the review of atmospheric dispersion estimates (secondary reviewer), assess the steam generator response to various postulated accidents under SRP