Document: NUREG-0800
Document ID: 644c1fee-247e-4265-9466-5876937a7120
Document Type: srp
Title: INFORMATION SYSTEMS IMPORTANT TO SAFETY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550086.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.5
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acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. IEEE Std. 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” 2. IEEE Std. 497-2002, “IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations.” 3. IEEE Std. 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” 4. IEEE Std. 7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 7.5-14 Revision 5 - March 2007 5. NUREG-0737 Supplement 1, “Clarification of TMI Action Plan Requirements - Requirements for Emergency Response Capability,” January 1983. 6. Regulatory Guide 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems.” Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1973. 7. Regulatory Guide 1.7, “Criteria for Independence of Electrical Safety Systems.” Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2005. 8. Regulatory Guide 1.97, Revision 2, “Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident.” Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1980. 9. Regulatory Guide 1.97, Revision 3,