Document: NUREG-0800
Document ID: 8f691af5-cf3a-46e0-92cd-9421a49395c9
Document Type: srp
Title: Revision 2 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070800127.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3
CFR Part: 
CFR Title: 

Content:
lear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to DISTRIBUTION@nrc.gov. Electronic copies of this section are available through the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/, or in the NRC's Agencywide Documents Access and Management System (ADAMS), at http://www.nrc.gov/reading-rm/adams.html, under Accession # ML070800127. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 3-1 CLASSIFICATION OF MAIN STEAM COMPONENTS OTHER THAN THE REACTOR COOLANT PRESSURE BOUNDARY FOR BWR PLANTS REVIEW RESPONSIBILITIES Primary - Organization responsible for mechanical engineering reviews Secondary - Organizations responsible for the review of component performance and testing A. BACKGROUND A pipe classification of "D + QA" for main steam line components of BWR plants was proposed by the General Electric Company in 1971 as an alternative to Quality Group B and has been accepted by the staff in a number of licensing case reviews. However, a number of potential problems which are applicable to main steam lines of BWR plants have been identified. These problems relate to postulated breaks in high-energy fluid-containing lines outside the containment. The criteria pertaining to protection necessary for structures, systems, and components outside containment from the effects of postulated pipe breaks, as described in Appendix C to Branch Technical Position 3-3, reference ASME Section III, Class 2, which corresponds to NRC Quality Group B. ASME Code Section XI contains in-service inspection criteria for Class 2 components. Steam lines classified as "D + QA" could be interpreted to be exempt from these inspection criteria. Such interpretations would be contrary to the intent of the code and inconsistent with BTP 3-1-2 Revision 2 - March 2007 requirements of the NRC Codes and Standards rule, Section