Document: NUREG-0800
Document ID: 42e7682f-df25-4a6a-94f4-7d44ea029702
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070677.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
AAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.67 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 68 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.69 DRAFT Rev. 3 - April 1996 15.1.5-14 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced NUREGs. except for the position stated in subsection II, assumptions b and d, and in III.2 regarding loss of offsite power and assumed single failures. This new position will be applied to new applications (for a Construction Permit, a manufacturing license, or design certification).70 VI. REFERENCES 1. Branch Technical Positions ASB 3-1, "Protection Against Postulated Piping Failures in Fluid Systems Outside Containment," attached to SRP Section 3.6.1, and MEB 3-1, "Postulated Break and Leakage Locations in Fluid System Piping Outside Containment," attached to SRP Section 3.6.2. 2. 10 CFR Part 50, General Design Criterion 17, "Electric Power Systems."71 23. 10 CFR Part 50, General Design Criterion 27, "Combined Reactivity Control Systems Capability." 34. 10 CFR Part 50, General Design Criterion 28, "Reactivity Limits." 45. 10 CFR Part 50, General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary." 56. 10 CFR Part 50,