Document: NUREG-0800
Document ID: 6209b3e7-917d-48d2-a299-4d1230aa5b51
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550070.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
. To assure this, the protection system must be demonstrated to operate within the time constraints of each anticipated operational transient. 2. Relevant Guidance IEEE Std. 603-1991 is a system-level standard that contains requirements related to performance and timing. This standard requires in part that a reactor safety system have a documented design basis consisting of the following: • Clause 4.4 - limits, ranges, and rates of change of variables should be included in the documented design basis. • Clause 4.10 - critical points in time should be specified for: – Initiation of protective action. – Completion of protective action. – Time when automatic control of protective action is required. – Time when protective system may be returned to normal. • Clause 6.1 - timely automatic control action is required when events occur too quickly for operator intervention. Appendix 7.1-C provides Standard Review Plan (SRP) acceptance criteria for safety system compliance with 10 CFR 50.55a(h). Appendix 7.1-B provides SRP acceptance criteria for protection system compliance with 10 CFR 50.55a(h). Appendix 7.1-D provides SRP acceptance criteria for digital I&C compliance with IEEE Std. 7-4.3.2-2003, "IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations," as endorsed by Regulatory Guide 1.152, Revision 2, "Criteria for Digital Computers in Safety Systems of Nuclear Power Plants." IEEE Std. 7-4.3.2-2003, Clause 2, states that this standard shall be used in conjunction with additional standards, including: • IEEE Std. 1012-1998, "IEEE Standard for Software Verification and Validation," which is endorsed by Regulatory Guide 1.168, Revision 1, "Verification, Validation, Reviews and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants." • IEEE/EIA Std. 12207.0-1996, "Industry Implementation of International Standard ISO/IEC 12207: 1995 (ISO/IEC 12207) Standard for Information Technology