Document: NUREG-0800
Document ID: ecb92ac6-97df-4e4b-a20a-81638c2d573b
Document Type: srp
Title: - 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350157.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
parts of the method discussed herein are contained in the rpfprenced NUREGs. 15.3.3-6 Rev. 2 - July 1981 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 27, "Combined Reactivity Control Systems Capability.". 2. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactivity Limits." 3. ASME Boilure and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 4. "Staff Discussion of Fifteen Technical Issues Listed in Attachment to November 3, 1976 Memorandum from the Director, NRR, to NRR Staff" (Issue No. 1), U.S. Nuclear Regulatory Commission, NUREG-0318, November 1976. 5. "Staff Discussion of Twelve Additional Technical Issues Raised by Responses to November 3, 1976 Memorandum from the Director, NRR, to NRR Staff" (Issue No. 22), U.S. Nuclear Regulatory Commission, NUREG-0158, December 1976. 6. F. M. Bordelon, "Calculation of Flow Coastdown after Loss of Reactor Coolant Pump," WCAP-7973, Westinghouse Electric Corporation, August 1970. 7. C. D. Morgan, H. C. Cheatwood, and J. R. Glandermans, "RADAR - Reactor Thermal and Hydraulic Analysis During Reactor Flow Coastdown," BAW-10069, Babcock and Wilcox Company, July 1973. 8. R. H. Stoudt and J. E. Busby, "CADD - Computer Applications to Direct Simulation of Transient Events on Water Reactors," BAW-10080 (nonpro- prietary) and BAW-10076 (proprietary), Babcock and Wilcox Company, July 1973. 9. "System 80 Standard Safety Analysis Report (CESSAR)," Combustion Engineering, Inc., August 1973. 10. R. Linford, "Analytical Methods of Transient Evaluations in the General Electric Boiling Water Reactor," NEDP-10802, General Electric Company, April 1973. 11. Standard Review Plan Section 4.4, "Thermal and Hydraulic Safety." 12. Standard Review Plan Section 4.2, "Fuel System Design." 13. Standard Review Plan Section 7.2, "Reactor Trip System." 14. Standard Review Plan Section 7.3, "Engineered Safety