Document: NUREG-0800
Document ID: 06884384-e650-488f-bf96-f48afd211643
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550075.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 # ML070550075. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 7-17 GUIDANCE ON SELF-TEST AND SURVEILLANCE TEST PROVISIONS REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None A. BACKGROUND This branch technical position (BTP) provides guidelines for reviewing the design of the self-test and surveillance test provisions. These guidelines are based on reviews of applicant/licensee submittals and vendor topical submittals describing self-test and surveillance test assumptions, terminology, methodology, and experience gained from NRC inspections of operating plants. 1. Regulatory Basis 10 CFR 50.55a(h), "Protection and Safety Systems," requires compliance with Institute of Electrical and Electronics Engineers (IEEE) Standard. 603-1991, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations," and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant/licensee may elect to comply instead with the plant-specific licensing basis. For nuclear power plants with construction permits issued between BTP 7-17-2 Revision 5 - March 2007 January 1, 1971, and May 13, 1999, the applicant/licensee may elect to comply instead with the requirements stated in IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations." IEEE Std. 603-1991, Clause 5.7, requires that capability for