Document: NRC Regulatory Guide
Document ID: 5f799693-27fd-4e13-a5e1-4c02f393d90a
Document Type: regulatory_guide
Title: Best-Estimate Calculations of Emergency Core Cooling System Performance + HISTORY –HISTORY 04/2013 – Periodic Review of Revision 0 – Reviewed with issues identified for future consideration 03/1987 – Draft RS 701-4, Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003739584.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.157
CFR Part: 
CFR Title: 

Content:
erature predictions for best-estimate thermal-hydraulic transient codes that the NRC has developed. D. IMPLEMENTATION The purpose of this section is to provide informa tion to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. Licensees and applicants may propose means other than those specified by the provisions of the Regulatory Position of this guide for meeting applica ble regulations. This guide has been approved for use by the NRC staff as an acceptable means of 1.157-14 complying with the Commission's regulations and for evaluating submittals in the following categories: 1. Construction permit applicants that choose to make use of the provisions of § 50.46 that allow the use of realistic models as an alter native to the features of Appendix K of 10 CFR Part 50. 2. Operating license applicants that choose to make use of the provisions of § 50.46 that allow the use of realistic models as an alter native to the features of Appendix K of 10 CFR Part 50. 3. Operating reactor licensees will not be evaluated against the provisions of this guide except for new submittals that make use of the provisions of § 50.46 that allow the use of realistic models as an alternative to the features of Appendix K of 10 CFR Part 50. 1.157-15 REFERENCES 1. Los Alamos National Laboratory, "TRAC PF1/MOD1: An Advanced Best-Estimate Com puter Program for Pressurized Water Reactor Thermal-Hydraulic Analysis," NUREG/ CR-3858 (LA-10157-MS), July 1986. 2. Idaho National Engineering Laboratory, "TRAC-BD1/MOD1: An Advanced Best Esti mate Computer Program for Boiling Water Re actor Transient Analysis," NUREG/CR-3633, 4 Vols. (EGG-2294), April 1984. 3. Idaho National Engineering Laboratory, "RELAP5/MOD2 Code Manual," Vols. 1 & 2, NUREG/CR-4312, August 1985. (Available in the NRC Public Document Room.) 4. Pacific Northwest Laboratory, "COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Pri mary Coolant Systems,"