Document: NUREG-0800
Document ID: 6ab5aca9-a3b8-4b64-85cb-66e175a6c0aa
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1520/ML15209A319.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

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. ML15209A319. N UREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 7-6 GUIDANCE ON DESIGN OF INSTRUMENTATION AND CONTROLS PROVIDED TO ACCOMPLISH CHANGEOVER FROM INJECTION TO RECIRCULATION MODE 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 Designs are reviewed with regard to the automatic and manual initiation of protective actions, as BTP 7-6-3 Draft Revision 6 – July 2015 set forth in clause 4.17 of IEEE Std 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations," or clauses 6.2 and 7.2 of IEEE Std 603-1991, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." For some designs, the staff concluded that the proposed design of the circuits used to