Document: NUREG-0800
Document ID: 7a841760-7020-433b-b182-63af2e6f5e72
Document Type: srp
Title: OVERPRESSURE PROTECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340596.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.2
CFR Part: 
CFR Title: 

Content:
on system, will protect the primary system against overpressure in the event of a complete loss of heat sink. The peak primary system pressure following the worst transient is limited to the ASME Code allowable (110% of the design pressure) with no credit taken for nonsafety-grade relief systems. The plant was assumed to be operating at design conditions (X of rated power) and the reactor is shut down by a scram. The calculated pressure at the bottom of the vessel is psig, a value within the code allowable of psig (110% of vessel design pressure). Overpressure protection during low temperature operation (defined in Branch Technical Position RSB 5-2) of the plant is provided by . | The applicant has met GDC 15 and 31 and Appendix G since they have implemented the guideline of BTP RSB 5-2. In addition, the applicant has incorporated into their design the recommendations of Task Action Plan items II.D.1 and II.D.3 of NUREG-0718 and NUREG-0737. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. *Normally, BWRs are analyzed at 105% rated steam flow at a pressure of 1040 psig. 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. 5.2.2-5 Rev. 2 - November 1988 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced NUREGs. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant System Design." 2. ASME Boiler and Pressure Vessel Code, Section III, Article NM-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 3. Branch Technical Position RSB 5-2, "Overpressurization Protection of Pressurized Water Reactors While Operating at Low