Document: NUREG-0800
Document ID: 1929f0b3-718f-4d47-9eae-c06f5f2b7514
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550096.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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 # ML070550096. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 7-8 GUIDANCE FOR APPLICATION OF REGULATORY GUIDE 1.22 REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None A. Background A recent application listed eight functions that are not tested while the reactor is operating at power. The applicant claimed that the periodic testing complied with Regulatory Guide (RG) 1.22, “Periodic Testing of Protection System Actuation Functions.” RG 1.22 does make provisions for actuated equipment that is not tested during reactor operation, but it does not have provisions for excluding any portion of the protection system from the requirements of clauses 4.9 and 4.10 of IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” or the safety system from the requirements of clauses 5.7 and 6.5 of IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” BTP 7-8-2 Revision 5 - March 2007 B. Branch Technical Position All portions of the protection and safety systems should be designed in accordance with IEEE Std 279-1971 or IEEE Std 603-1991, as required by 10 CFR 50.55a(h), “Protection and Safety Systems.” All actuated equipment that is not tested during reactor operation should be identified, and a discussion of how each conforms to the provisions of paragraph D.4 of RG 1.22 should be submitted. In addition to