Document: NUREG-0800
Document ID: 54e3d49d-900d-4fe8-9297-2fc04501e4e0
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340664.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
ling Water Reactors, NEDO-10329, Appendix C, General Electric Company, April 1971. 11. J. Duncan and P. W. Marriott, "General Electric Company Analytical Model for Loss of Coolant Accident Analysis in Accordance with 10 CFR Part 50, Appendix K," NEDO-20566, General Electric Company, November 1975. 12. B. S. Mullanax, R. J. Walker and B. A. Karrasch, "Reactor Vessel Model Flow Tests," BAW-10037 (non-proprietary version of BAW-10012), Revision 2, Babcock and Wilcox Company, September 1968. 13. "Design and Performance of General Electric Boiling Water Reactor Jet Pumps," APED-5460, General Electric Company, September 1968. 14. H. T. Kim, "Core Flow Distribution in a Modern Boiling Water Reactor as Measured in Monticello," NEDO-10299, General Electric Company, January 1971. 15. Regulatory Guide No. 1.68, "Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors." 16. Regulatory Guide 1.133, "Loose Parts Detection Program for the Primary System of Light-Water-Cooled Reactors." 17. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits. 18. NUREG-0737, "Clarification of TMI Action Plan Requirements." 19. H. Chelemer, L. H. Boman, D. R. Sharp, "Improved Thermal Design Procedure," WCAP-8567(P)/8568(NP), Westinghouse Electric Corporation, July 1975. 4.4-9 Rev. 1 - July 1981 APPENDIX STANDARD REVIEW PLAN 4.4 INDEPENDENT AUDIT ANALYSIS to SRP Section 4.4 has been deleted) (Appendix I 4.4-10 Rev. 1 - July 1981