Document: NUREG-0800
Document ID: a4ef36de-b662-41f6-9e66-96e4b7197298
Document Type: srp
Title: MASS AND ENERGY RELEASE ANALYSIS FOR POSTULATED
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0601/ML060150002.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1.3
CFR Part: 
CFR Title: 

Content:
his SRP section will be used by the staff when performing safety evaluations of design | certifications and license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR | 52. Except in those cases in which the applicant proposes an acceptable alternative method for | complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Rev. 2 - January 2006 6.2.1.3-8 The provisions of this SRP section apply to reviews of applications docketed six months or more | after the date of issuance of this SRP section. | VI. REFERENCES The references for this SRP section are listed in SRP Section 6.2.1. (As this is the first SRP section of 6.2.1 being updated, references, in sequence, are provided | here for completeness) | | 1. WCAP-7750, “SATAN-V, A Computer Space Time Dependent Analysis of Loss of | Coolant,” August 1971. | | 2. BAW-10092, “CRAFT-2 Fortran Program for Digital Simulation of a Multinode Reactor | Plant During a Loss-of-Coolant Accident,” Babcock and Wilcox Company, December | 1974. | | 3. CENPD-133 Supplement 5-A, “CEFLASH-4A — A Fortran77 Digital Computer Program | for Reactor Blowdown Analysis,” dated June 1985. | | 4. W. H. Retting, G. A. Jayne, K. Y. Moore, C. E. Slater, and M. L. Uptmor, “RELAP3 - A | Computer Program for Reactor Slowdown Analysts,” IN-1321, Idaho Nuclear | Corporation, June 1970. | | 5. F. C. Cadek, et al., “PWR FLECHT (Full Length Emergency Cooling Heat Transfer), | Final Report,” UCAP-7665, Westinghouse Electric Corporation, April 1971. | | 6. BAW-10030, “CRAFT - Description of Model for Equilibrium LOCA Analysis Program,” | Babcock and Wilcox, Lynchburg, VA, October 1971. | | 7. B&W-10164P, Revision 1, “RELAP5/MOD2-B&W - An Advanced Computer Program for | Light Water Reactor LOCA and Non-LOCA Transient Analysis,” Babcock and Wilcox, | October 1988. | | 8. BAW-10164P-A,