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:
t to regulation being discussed): a. meeting the regulatory positions in Regulatory Guide ________ or Guides; b. providing and meeting an alternative method to regulatory positions in Regulatory Guide ________, that the staff has reviewed and found to be acceptable; c. meeting the regulatory position in BTP; d. using calculational methods for (state what was evaluated) that has been have previously been reviewed by the staff and found acceptable; the staff has 16 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 6.2.1-5 DRAFT Rev. 3 - April 1996 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. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.17 V. IMPLEMENTATION The implementation schedules are given in the "Implementation" sections of the seven SRP sections listed above. VI. REFERENCES 18 21. 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