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:
nd found to be acceptable; c. meeting the regulatory position in BTP; d. using calculational methods for (state what was evaluated) that has been previously reviewed by the staff and found acceptable; the staff has reviewed the impact parameters in this case and. found them to be suitably conservative or performed independent calculations to verify acceptability of their analysis; and/or e. meeting the provisions-of (industry standard number and title) that has been reviewed by the staff and determined to be appropriate for this application. 2. Repeat discussion for each regulation cited above. 3. The temperature/pressure profiles provided in the Final Safety Analysis Report for the spectrum of LOCA and main steam line break accidents are acceptable for use in equipment qualification, i.e., there is reasonable assurance that the actual temperatures and pressures for the postulated accidents will not exceed these profiles anywhere within the specified environmental zones, except in the break zone. V. IMPLEMENTATION The implementation schedules are given in the "Implementation" sections of the seven SRP sections listed above. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases"; Criterion 13, "Instrumentation and Control"; Criterion 16, "Containment Design"; Criterion 38, "Containment Heat Removal"; Criterion 39, "Inspection of Containment Heat Removal System"; Criterion 40, "Testing of Containment Heat Removal System"; Criterion 50, "Containment Design Basis"; Criterion 52, "Capability for Containment Leakage Rate Testing"; Criterion 53, "Provisions for Containment Testing and Inspection"; Criterion 54, "Systems Penetrating Containment"; Criterion 55, "Reactor Coolant Pressure Boundary Penetrating Containment"; 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