Document: NUREG-0800
Document ID: c6f58bab-ddce-42eb-a3ef-02dd3da952fc
Document Type: srp
Title: Revision 3 – December 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16085A315.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3
CFR Part: 
CFR Title: 

Content:
for those portions of piping in the containment penetration areas should be constructed in accordance with the criteria of the ASME Code, Section III, Subsection NE, Class MC, where the guard pipe is part of the containment boundary. In addition, the entire guard pipe assembly should be designed to meet the following criteria and tests: (a) The design pressure and temperature should not be less than the maximum operating pressure and temperature of the enclosed pipe under normal plant conditions. (b) The Level C stress limits in ASME Code, Section III, NE-3220 should not be exceeded under the loading associated with containment design pressure and temperature in combination with the safe shutdown earthquake. BTP 3-4-5 Revision 3 –December 2016 (c) Guard pipe assemblies should be subjected to a single pressure test at a pressure not less than its design pressure. (d) Guard pipe assemblies should not prevent the access necessary to conduct the inservice examination specified in 2.A(ii)(7). Inspection ports, if used, should not be located in that portion of the guard pipe through the annulus of dual barrier containment structures. (7) A 100 percent volumetric inservice examination of all pipe welds should be conducted during each inspection interval as defined in ASME Code, Section XI, IWA-2400. (iii) Postulation of Pipe Breaks in Areas Other Than Containment Penetration (1) With the exceptions of those portions of piping identified in 2.A(ii), breaks in Class 1 piping (ASME Code, Section III) should be postulated at the following locations in each piping and branch run: (a) At terminal ends.3 (b) At intermediate locations where the maximum stress range4 as calculated by Eq. (10) and either Eq. (12) or Eq. (13) exceeds 2.4Sm. (c) At intermediate locations where the cumulative usage factor exceeds 0.1. For new reactor design certification reviews, the staff has considered a CUF limit of 0.4 to be acceptable when the effects of EAF are considered in the piping design.