Document: NUREG-0800
Document ID: ed948426-dd77-4047-be5e-2b7ab22de3f5
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAK INSIDE AND OUTSIDE CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550009.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
lines even if the accident occurs with an iodine spike. 8. The applicant meets 10 CFR 50.34(f)(1)(ii) and 10 CFR 50.34(f)(2)(xii) requirements for demonstrating the adequacy of the auxiliary feedwater design to remove decay heat following feedwater piping failures. (See SRP Acceptance Criteria for AP1000 applicability). 9. The applicant meets 10 CFR 50.34(f)(1)(III) requirements for demonstrating RCP seal capability to withstand the postulated accident. (See SRP Acceptance Criteria for AP1000 applicability). For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. Implementation schedules for compliance with parts of the method addressed here are in the referenced regulatory guides and NUREGs, except for the position in subsections II.6.D and III of this SRP section on LOOP and assumed single failures. This new position applies to new applications (for a construction permit, a manufacturing license, or DC). 15.2.8-13 Revision 2 - March 2007 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants." A. GDC 13, “Instrumentation and Control.” B. GDC 17, "Electric Power Systems." C. GDC 27, "Combined Reactivity Control System Capability." D. GDC 28,