Document: NUREG-0800
Document ID: b085cd1c-2d74-4547-b757-d8513d0cb353
Document Type: srp
Title: OVERPRESSURE PROTECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070419.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.2
CFR Part: 
CFR Title: 

Content:
NUREG-0718 (Ref. 4). Applications for operating license shall meet recommendations of Task Action Plan items II.D.1 and II.D.3 of NUREG-0737 (Ref. 5). Applicants should meet the recommendations of the following TMI action plan items of NUREG 0737 (Reference 6): 1. II.D.1 regarding testing to qualify reactor coolant system relief and safety valves under expected operating conditions for design basis transients and accidents. 10 CFR 50.34(f)(2)(x) establishes an equivalent requirement for those applicants subject to the requirements of 10 CFR 50.34(f).16 2. II.D.3 regarding the provision of direct indication of relief and safety valve position. 10 CFR 50.34(f)(2)(xi) establishes an equivalent requirement for those applicants subject to the requirements of 10 CFR 50.34(f).17 Other specific acceptance criteria necessary to meet the requirements of GDC 15 and 31 are as follows: A. For overpressure protection, during power operation of the reactor, the relief valves shall be designed with sufficient capacity to preclude actuation of safety valves, during normal operational transients, when assuming the following conditions at the plant: a. The reactor is operating at licensed core thermal power level. DRAFT Rev. 3 - April 1996 5.2.2-4 b. All system and core parameters are at values within normal operating range that produce the highest anticipated pressure. c. All components, instrumentation, and controls function normally. Safety valves shall be designed with sufficient capacity to limit the pressure to less than 110% of the RCPB design pressure (as specified by the ASME Boiler and Pressure Vessel Code [Reference. 215] ), during the most severe abnormal operational transient with reactor scram. 18 Also, sufficient margin shall be available to account for uncertainties in the design and operation of the plant assuming: (1) The reactor is operating at a power level that will produce the most severe overpressurization transient. (2) All system and core parameters are at