% , U.S NUCLEAR REGULATORY COMMISSION,it STANDARD REVIEW PLAN OFRICE OF NUCLEAR REACTOR REGULATION 6.2.1.1.A PWR DRY CONTAINMENTS, INCLUDING SUBATMOSPHERIC CONTAINMENTS REVIEW RESPONSIBILITIES Primary- Containment Systems Branch (CSB) Secondary- None

For pressurized water reactor (PWR) plants with dry containments, the CSB review covers the 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 feed-water 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 of static and active heat removal mechanisms. 5. The pressure conditions within subcompartmenits that act on system components and supports due to high energy line breaks. 6. The range and accuracy of instrumentation that is provided to monitor and record containment conditions during and following an accident. CSB will coordinate the primary review responsibilities of other branches that interface with the CSB evaluation of the containment functional design. Thes