Document: NUREG-0800
Document ID: 8a69e211-8100-413b-aa05-61dd44b10160
Document Type: srp
Title: REVIEW RESPONSIBILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350115.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.4
CFR Part: 
CFR Title: 

Content:
an unplanned increase in heat removal by the secondary system. Those that might be expected to occur with moderate frequency can be.caused by feedwater system or pressure regulator malfunctions or the inadvertent opening of a steam generator safety or relief valve (PWR only). All of these postulated transients have been reviewed. It was found that the most limiting in regard to core thermal margins and pressure within the reactor coolant and main steam systems was the -transient. The staff concludes that the analysis of transients resulting in an unplanned increase in heat removal by the secondary system that are expected to occur with moderate frequency is acceptable and meets the reguirements of General Design Criteria 10, 15, and 26 and TMI Action Plan items II.E.5.1 and II.E.5.2. 1. In meeting GDC 10, 15, and 26 as indicated below we have determined that the applicant's analysis was performed using a mathematical model that had been previously reviewed and found acceptable by the staff. The parameters used as input to-this model were reviewed and .found to be suitably conservative. In addition, we have further determined that the positions of Regulatory Guide 1.53 as related to the single failure criterion and Regulatory Guide 1.105 for instruments have also been satisfied. 2. The applicant has met the requirements of GDC 10 and 26 with respect to demonstrating that resultant fuel damage is maintained since the -specified acceptable fuel design limits were not exceeded for this event. 15.1.1-6 Rev. 1 - July 1981 3. The applicant has met the requirements of GDC 15 with respect to demonstrating that the reactor coolant pressure boundary limits have not been exceeded by this event and that resultant leakage will be within acceptable limits. This requirement has been met since the maximum pressure within the reactor coolant and main steam systems did not exceed 110% of the design pressures. 4. The applicant has met the requirements of GDC 26 with respect to the