Document: NUREG-0800
Document ID: 2c839e4a-a342-4e25-9a7c-82d678a0f754
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340657.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
specified in Appendix A of NUREG-0802 (Ref. le). The acceptability of pool dynamic loads for plants with Mark III contain- ments is based on conformance with the NRC acceptance criteria identified in Appendix C of NUREG-0978. For Mark III plants at the construction permit stage, conformance with the NRC acceptance criteria can be demonstrated if a previously analyzed Mark III plant has sufficient similarity in plant characteristics to make .the analyses performed for that plant design applicable to the Mark III plant design under consideration. The acceptability of pool-dynamic loads associated with the actuation of one or more reactor coolant system safety/relief valves in Mark III containment are specified in Appendix B of NUREG-0802. 3. In meeting the requirements of General Design Criteria 16 and 50 regarding the containment design margin for Mark III plants, high energy lines passing through the containment should be provided with guard pipes or enclosed in other types 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 MEB as set forth in SRP Section 3.6.2. The allowable leakage areas for steam bypass of 6.2.1.1.C-4 Rev. 6 - August 1984 the suppression pD01 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. 4. 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