Document: NUREG-0800
Document ID: 070a558a-dd64-4d4c-b104-780f0d1c49a3
Document Type: srp
Title: CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340652.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1
CFR Part: 
CFR Title: 

Content:
nment"; Criterion 56, "Primary Containment Isolation"; Criterion 57, "Closed System Isolation Valves"; and Criterion 64, "Monitoring Radioactivity Release." 2. 10 CFR §50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors," and 10 CFR Part 50, Appendix K, "ECCS Evaluation Models." 3. ASME Boiler and Pressure Vessel Code, Section II, Division 1, Subsection NE, "Class MC Components," American Society of Mechanical Engineers. 4. Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radio- logical Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors." 6.2.1-4 Rev. 2 - July 1981 5. Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors." 6. C. F. Carmichael and S. A. Marks, "CONTEMPT-PS, A Digital Computer Code for Predicting the Pressure-Temperature History Within a Pressure- Suppression Containment Vessel in Response to a Loss-of-Coolant Accident," IDO-17252, Phillips Petroleum Company, April 1969. 7. L. C. Richardson, L. J. Finnegan, R. J. Wagner, and J. M. Waage, "CONTEMPT, A Computer Program for Predicting the Containment Pressure- Temperature Response to a Loss-of-Coolant Accident," IDO-17220, Phillips Petroleum Company, June 1967. 8. R. J. Wagner and L. L. West, "CONTEMPT-LT Users Manual," Interim Report 1-214-74-12.1, Aerojet Nuclear Company, August 1973. 9. R. I. Miller, "Evaluation of the Predictive Capabilities of the CONTEMPT-PS Computer Code by Comparison of Calculated Results with the Humboldt Bay and Bodega Bay Pressure Suppression Tests," Interim Report 4.2.1.1, Idaho Nuclear Corporation, September 1970. 10. T. Tagami, "Interim Report on Safety Assessments and Facilities Establishment Project in Japan for Period Ending June 1965 (No. 1)," prepared for the National Reactor Testing Station, February 28, 1966 (unpublished work). 11. H. Uchida, A. Oyama, and Y. Toga, "Evaluation