Document: NUREG-0800
Document ID: 4d7d277e-c006-45d6-94df-c84845dd68d0
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF VALVE OR A BWR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350144.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
ave further determined that the position of Regulatory Guide 1.53 with respect to single failure criterion and Regulatory Guide 1.105 for instruments have also been satisfied. 5. The applicant has met Task Action Plan item [identify item No.] by [describe means used by the applicant to implement the action plan item). V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. V. REFERENCES 1. ANSI B95.1-1972, "Terminology for Pressure Relief Devices," American Society of Mechanical Engineers. 2. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 3. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant Pressure Boundary." 4. 10 CFR Part 50, Appendix A, General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 15.6.1-7 Rev. 1 - July 1981 5 ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 6. Standard Review Plan Section 4.2, "Fuel System Design." 7. ANSI N18.2, "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants," American National Standards Institute (1974). 8. ANS Trial Use Standard N212, "Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," American Nuclear Society (1974). 9. Regulatory Guide 1.105, "Instrument Spans and Setpoints." 10. Regulatory Guide 1.53, "Application of the Single Failure Criterion