Document: NUREG-0800
Document ID: 588057ff-3b28-45e0-8136-e2253c8a82e6
Document Type: srp
Title: Revision 6 - August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A033.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
latory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, 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 ADAMS Accession No. ML16020A033. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 7-5 GUIDANCE ON SPURIOUS WITHDRAWALS OF SINGLE CONTROL RODS IN PRESSURIZED WATER REACTORS REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None A. BACKGROUND The operating experience with pressurized water reactors (PWRs) and subsequent reviews of PWR designs with regard to the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criteria 20, “Protection System Functions,” and 25, “Protection System Requirements for Reactivity Control Malfunctions,” have shown that single failures can cause inadvertent single-rod withdrawals. The intent of this branch technical position is to provide specific guidance toward an acceptable interpretation and application of General Design Criteria 20 and 25. BTP 7-5-2 Revision 6 - August 2016 B. BRANCH TECHNICAL POSITION General Design Criterion (GDC) 20 requires that the protection system shall be designed to initiate automatically the operation of appropriate systems, including the reactivity control systems, to ensure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences. GDC 25 requires that these limits shall not be exceeded for any single malfunction of the