Document: NUREG-0800
Document ID: 919b8fa0-8b11-41bd-9694-2c62120b843b
Document Type: srp
Title: Revision 7 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600403.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
nce of this SRP section, unless superseded by a later revision. The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. 1. LOCA-related pool dynamic loads criteria are implemented on all plants with Mark I containments in accordance with section 5 of NUREG-0661 and Supplement 1 to it; for all Mark II containments in accordance with section 3.1 of NUREG-0808 and/or Appendix B of this SRP section; and for all Mark III containment designs in accordance with Section 4 of NUREG-0978. 2. Reactor coolant system safety/relief valve(s)-related pool dynamic loads criteria are implemented on all plants with Mark I containments in accordance with section 5 of 6.2.1.1.C-13 Revision 7 - March 2007 NUREG-0661 and supplement 1 to it, and for all Mark II and III containments in accordance with section 4.1 of NUREG-0802. VI. REFERENCES References for this SRP section as those listed in SRP Section 6.2.1. 6.2.1.1.C-14 Revision 7 - March 2007 Appendix A to SRP Section 6.2.1.1.C Steam Bypass for Mark I, II, and III Containments A. Background This appendix pertains to steam bypass from the drywell to the suppression pool air volume in the Mark I, II, and III containment design. In a pressure suppression-type containment, steam released from the primary system following a postulated LOCA is collected in the containment drywell volume and directed through connecting vents to the suppression pool in the containment wetwell volume and steam is condensed as it enters into the suppression pool. Thus, no steam enters the wetwell air volume. The potential exists for steam to bypass the suppression pool by leakage through the vacuum breakers or directly from leak paths in the drywell-to-suppression chamber vent pipes, the diaphragm-wall seal around diaphragm penetrations, or cracks in the concrete diaphragm. The capability for steam bypass for small primary system breaks in the Mark I, II, and III containment design are