Document: NUREG-0800
Document ID: 8da52d2b-9980-4076-8056-2cafebb25ed6
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550060.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
PWRs (Generic Letter No. 86–09),” March 31, 1986. 12. NRC Letter to All Holders of Operating Licenses and Construction Permits for Pressurized Water Reactors (PWRs), “Loss of Decay Heat Removal (Generic Letter 88–17),” October 17, 1988. 4.4-15 Revision 2 - March 2007 13. NRC Letter to All Boiling Water Reactor (BWR) Licensees of Operating Reactors, “Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f) (Generic Letter No. 92–04),” August 19, 1992. 14. B.S. Mullanax, R.J. Walker, and B.A. Karrasch, “Reactor Vessel Model Flow Tests,” BAW-10037 (nonproprietary version of BAW-10012), Rev. 2, Babcock and Wilcox Company, September 1968. 15. “Design and Performance of General Electric Boiling Water Reactor Jet Pumps,” APED-5460, General Electric Company, September 1968. 16. H.T. Kim, “Core Flow Distribution in a Modern Boiling Water Reactor as Measured in Monticello,” NEDO-10299, General Electric Company, January 1971. DRAFT Rev. 2, April 1996, 4.4-16. 17. H. Chelemer, L.H. Boman, and D.R. Sharp, “Revised Thermal Design Procedure,” WCAP-11397-P-A, Westinghouse Electric Corporation, July 1975. 18. Review Standard RS-001, “Review Standard for Extended Power Uprates,” RS-001, Revision 0, December 2003. 19. NRC Inspection Manual Chapter IMC-2504, “Construction Inspection Program - Non-ITAAC Inspections,” April 25, 2006. 20. “TEMP - Thermal Enthalpy Mixing Program,” BAW-10021, Babcock and Wilcox Company, April 1970. 21. H. Chelemer, P.T. Chu, and L.E. Hochreiter, “THINC-IV - An Improved Program for Thermal-Hydraulic Analysis of Rod Bundle Cores,” WCAP-7956, Westinghouse Electric Corporation, June 1973. (See also WCAP-7359-L and WCAP-7838.) 22. B.C. Slifer and J.E. Hench, “Loss of Coolant Accident and Emergency Core Cooling Models for General Electric Boiling Water Reactors,” NEDO-10329, Appendix C, General Electric Company, April 1971. 23. J. Duncan and P.W.