Document: NUREG-0800
Document ID: 6174d4a8-865d-4333-9b2a-1d83817c1e95
Document Type: srp
Title: Maintenance Bypass  (IEEE Std. 603-1991 Clause 7.5)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550088.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.5
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CFR Title: 

Content:
The review of bypass and removal from operations should be coordinated with the organization responsible for reviewing technical specification format and content to confirm that the provisions for this bypass are consistent with the required actions of the proposed plant technical specifications. 8. POWER SOURCE REQUIREMENTS (IEEE Std. 603-1991 Clause 8) The organization responsible for reviewing electrical systems reviews power source requirements. I&C reviewers should coordinate with the electrical systems reviewers to confirm that I&C safety system power sources are adequate. 9. REFERENCES 1. IEEE Std. 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” 7.1-C-16 Revision 5 - March 2007 2. IEEE Std. 323-1974, “IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations.” 3. IEEE Std. 338-1987, “Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems.” 4. IEEE Std. 379-1988, “Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems.” 5. IEEE Std. 384-1992, “IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits.” 6. IEEE Std. 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” 7. IEEE Std. 7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 8. IEEE Std. 828-1990, “IEEE Standard for Software Configuration Management Plans.” 9. Regulatory Guide 1.22, “Periodic Testing of Protection System Actuation Functions,” Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1972. 10. 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. 11. Regulatory Guide 1.53, “Application of the Single-Failure Criterion