Document: NUREG-0800
Document ID: 3e34268a-a6f4-4ce5-ba4d-7f2cec5a192e
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070481.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
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NUREG-0800 (Formerly NUREG-75/087) U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION DRAFT Rev. 3 - April 1996 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new information and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, D.C. 20555. 6.2.1.1.A PWR DRY CONTAINMENTS, INCLUDING SUBATMOSPHERIC CONTAINMENTS REVIEW RESPONSIBILITIES Primary - Containment Systems and Severe Accident Branch (SCSB) 1 Secondary - None I. AREAS OF REVIEW For pressurized water reactor (PWR) plants with dry containments, the SCSB review covers the 2 following areas: 1. The temperature and pressure conditions in the containment due to a spectrum (including break size and location) of postulated loss-of-coolant accidents (i.e., reactor coolant system pipe breaks) and secondary system steam and feedwater line breaks. 2. The maximum expected external pressure to which the containment may be subjected. 3. The minimum containment pressure that is used in analyses of emergency core cooling system capability. 4. The effectiveness