Document: NUREG-0800
Document ID: 8a3917be-d66d-44ac-bf51-233e38d1b2a3
Document Type: srp
Title: 6
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350392.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
Rev. 1 - July 1981 VI. REFERENCES 1. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 2. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 3. General Design Criterion 10, "Reactor Design." 4. General Design Criterion 15, "Reactor Coolant System Design." 5. General Design Criterion 20, "Protection System Functions." 6. General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 7. General Design Criterion 28, "Reactivity Limits." 8. Regulatory Guide 1.53, "Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems." 9. Regulatory Guide 1.105, "Instrument Spans and Setpoints."