Document: NUREG-0800
Document ID: 2cd63ebf-9196-42c0-880d-a80500b202a4
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550005.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
transients in such a way that the criteria regarding fuel damage and system pressure are met. The specific criteria necessary to meet the requirements of General Design Criteria 10, 15, 20, and 26 for incidents of moderate frequency are: 1. Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design values. 2. 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 correlations (see SRP Section 4.4). 15.1.1-15.1.4-5 Revision 2 - March 2007 3. An incident of moderate frequency should not generate a more serious plant condition without other faults occurring independently. 4. To meet the requirements of General Design Criteria 10, 13, 15, 20, and 26 the positions of Regulatory Guide 1.105, "Instrument Spans and Setpoints," are used with regard to their impact on the plant response to the type of transient addressed in this SRP section. 5. The most limiting plant systems single failure, as defined in the "Definitions and Explanations" of Appendix A to 10 CFR Part 50, shall be identified and assumed in the analysis and shall satisfy the positions of Regulatory Guide 1.53. The applicant's analysis of transients caused by excessive heat removal should be performed using an acceptable analytical model, the NRC approved methodologies and the computer codes. If the applicant proposes to use analytical methods which have not been approved, these methods are evaluated by the staff for acceptability. For new generic methods, the reviewer performs an evaluation based on SRP section 15.0.2, “Transient and Accident Analysis methods.” The values of the parameters used in the analytical model should be suitably conservative. The following values are considered acceptable for use in the model: 1. The initial power level is taken as the licensed core thermal power for the number of loops initially