Document: NUREG-0800
Document ID: a28650b3-fa03-428d-a2bd-4a27f583710b
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070484.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
ypes of protective structures to assure that the suppression pool is not bypassed. If guard pipes are used, they should be designed in accordance with acceptance criteria established by the EMEBMEB as set forth in SRP Section 3.6.2. The allowable leakage areas for 46 steam bypass of the suppression pool should be determined for a spectrum of postulated reactor coolant system pipe breaks. The maximum allowable bypass area of the plant should be based on conservative analyses which consider available energy removal mechanisms and the containment design pressure. d4. In meeting the requirement of General Design Criterion 53 regarding periodic testing at containment design pressure for Mark I, II, and III containments, the maximum allowable leakage area for steam bypass of the suppression pool should be greater than the technical specification limit for leakage measured in periodic drywell-wetwell leakage tests. Specific acceptance criteria for the three types of containments are as discussed in Appendix A. Plants with ABWR containments should follow the specific acceptance criteria for Mark II containments.47 e5. In meeting the requirement of General Design Criterion 50 with respect to the design leakage rate for Mark III containments, justification should be provided for any reduction in the containment leak rate claimed for times less than 30 days after a postulated pipe break accident. This also includes meeting the regulatory position C.1.e of Regulatory Guide 1.3. For plants with ABWR containments, the design leakage rate for primary containment should be assumed for the duration of the loss-of-coolant accident consistent with Regulatory Guide 1.3.48 f6. In meeting the requirement of General Design Criterion 16, provisions should be made in one of the following ways to protect the drywell and wetwell (or containment) of Mark I, II, and III, and ABWR plants, and the operating deck of Mark II plants, against loss of 49 integrity from negative pressure transients or