Document: NUREG-0800
Document ID: b486e8d3-c8b0-4990-b7ec-211a3aae25c3
Document Type: srp
Title: CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070456.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1
CFR Part: 
CFR Title: 

Content:
Lead Plant Program Load Evaluation and Acceptance Criteria," USNRC Report NUREG-0487, Supplement 1, October 1980. 3813. U.S. Nuclear Regulatory Commission, "Mark II Containment Lead Plant Program Load Evaluation and Acceptance Criteria," USNRC Report NUREG-0487, Supplement 2, February 1981. 3514. NUREG-0588, "Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment." 3215. NUREG-0609, "Asymmetric Blowdown Loads on PWR Primary Systems," January 1981. 1416. "COMPARE: A Computer Program for the Transient Calculation of a System of Volumes Connected by Flowing Vents," LA-NUREG-6488-MS, September 1976. 24 3917. U.S. Nuclear Regulatory Commission, "Safety Evaluation Report Mark I Containment Long-Term Program," USNRC Report NUREG-0661, July 1980. 3018. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License," March 1981. 2719. NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980. 20. U.S. Nuclear Regulatory Commission, "Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor," USNRC Report NUREG-1503, July 1994.25 421. Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors." 3422. Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following An Accident." 26 23. Regulatory Guide 1.157, "Best-Estimate Calculations of Emergency Core Cooling System Performance."27 3124. NRC Safety Evaluation Report, Babcock and Wilcox Company, Reference Safety Analysis Report, B-SAR-205, May 1978. 28 6.2.1-7 DRAFT Rev. 3 - April 1996 1925. "NRC Safety Evaluation Report - Standard Reference System, CESSAR System 80," Combustion Engineering Inc., December 1975. 29 2126. Final Safety Analysis Report for Donald C. Cook Nuclear Plant, Units 1 and 2, Appendices M and