Document: NUREG-0800
Document ID: 510373f4-479b-4ad4-99a6-93c3c8adf987
Document Type: srp
Title: 2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350154.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
Rev. 1 - July 1981 II. ACCEPTANCE CRITERIA The RSB acceptance criteria are based on meeting the relevant requirements of the following regulations: A. General Design Criterion 10 (Ref. 1), as it relates to the reactor coolant system being designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during normal operations including anticipated operational occurrences. B. General Design Criterion 15 (Ref. 2), as it relates to the reactor coolant system and its associated auxiliaries being designed with appropriate margin to assure that the pressure boundary will not be breeched during normal operations including anticipated operational occurrences. C. General Design Criterion 26 (Ref. 3) as it relates to the reliable control of reactivity changes to assure that specified acceptable fuel design limits are not exceeded, including anticipated operational occurrences. This is accomplished by assuring that appropriate margin for malfunctions, such as stuck rods, are accounted for. The basic objectives of the review of loss of forced reactor coolant flow transients are: 1. To identify which of the transients are the most limiting. 2. To verify that, for the most limiting transients, the plant responds to the loss of flow transients in such a way that the criteria regarding fuel damage and system pressure are met. The specific criteria necessary to meet the relevant requirements of GDC 10, 15 and 26 for incidents of moderate frequency* are: a. Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design valves. (Ref. 5) b. Fuel cladding integrity shall be maintained by ensuring that the minimum DNBR remains above the 95/95 DNBR limit for PWRs and the CPR remains above the MCPR safety limit for BWRs based on acceptable coorelations (see SRP Section 4.4). c. An incident of moderate frequency should not generate a more serious plant condition without other faults occurring independently. d. An