Document: NUREG-0800
Document ID: ffb5be76-13c5-4cea-a325-0f27b016bdd8
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1520/ML15209A459.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
mmission, 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. ML15209A459. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 7-9 GUIDANCE ON REQUIREMENTS FOR REACTOR PROTECTION SYSTEM ANTICIPATORY TRIPS REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None Review Note: The revision numbers of Regulatory Guides (RG) and the years of endorsed industry standards referenced in this branch technical position (BTP) are centrally maintained in Standard Review Plan (SRP) Section 7.1-T (Table 7-1). Therefore, the individual revision numbers of RGs (except RG 1.97) and years of endorsed industry standards are not shown in this BTP. References to industry standards incorporated by reference into regulation (IEEE Std 279-1971 and IEEE Std 603-1991) and industry standards that are not endorsed by the agency do include the associated year in this BTP. See Table 7-1 to ensure that the appropriate RGs and endorsed industry standards are used for the review. A. Background Several reactor designs have incorporated a number of anticipatory or "back-up" trips for which no credit was taken in the accident analyses. These trips, as a rule, were not designed to the BTP 7-9-2 Draft Revision 6 – August 2015 requirements of IEEE Std 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations," or IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and therefore introduced non-safety-grade equipment into the reactor