Document: NUREG-0800
Document ID: cf61f16a-4e82-42da-8333-e100f557fd60
Document Type: srp
Title: PLANT DESIGN FOR PROTECTION AGAINST POSTULATED PIPING FAILURES IN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550032.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.1
CFR Part: 
CFR Title: 

Content:
hnology to exclude the dynamic effects of postulated pipe ruptures from the design basis of plant SSCs is in accordance with SRP Section 3.6.3. 7. The acceptability of inservice inspection criteria of piping within protective structures or guard pipes, between containment isolation valves is evaluated in accordance with SRP Section 6.6. 8. The acceptability of environmental effects of piping failures inside containment is evaluated in accordance with SRP Sections 6.2.1 and 3.11. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. 3.6.1-4 Revision 3 - March 2007 II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR Part 50, Appendix A, GDC 2, as it relates to protection against natural phenomena, such as seismically-induced failures of non-seismic piping. The application of 10 CFR Part 50, Appendix A, GDC 2 to this section is to incorporate environmental effects of full-circumferential ruptures of non-seismic moderate energy piping in areas where effects are not already bounded by failures of high energy piping. Acceptance is based on conformance to BTP 3-3. 2. GDC 4, as it relates to SSCs important to safety being designed to accommodate the effects of and to be compatible with the environmental conditions associated with postulated pipe rupture. Acceptance is based on conformance to BTP 3-3. 3. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations; 4. 10 CFR 52.80(a), which requires that a