Document: NUREG-0800
Document ID: 504a24fe-9056-495a-8541-0e278016ce80
Document Type: srp
Title: in that offsite AC power remains available to operate the station
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070300702.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
26. This conclusion is based on the following findings: 1. The applicant meets the requirements of GDCs 10 and 26 by demonstrating that SAFDLs are not exceeded for this event. The applicant also meets GDC 15 requirements by preventing plant transients from resulting in unplanned decreases in heat removal by the secondary system and demonstrating reactor coolant pressure limits not exceeded by these events and resultant leakage within acceptable limits. 2. The applicant meets GDC 13 requirements by demonstrating that all credited instrumentation was available, and the actuations of protection systems, automatic and manual, occurred at values of monitored parameters that were within the instruments’ prescribed operating ranges. 3. The transient initiating events that might occur with moderate frequency are: A. turbine trip, B. loss of external load, C. steam pressure regulator malfunctions, D. main steam isolation valve closure (in BWRs), E. loss of condenser vacuum, 1 The SER should present one statement for moderate frequency transients involving unplanned decrease in heat removal by the secondary system; thus, the results of reviews under SRP Sections 15.2.6 and 15.2.7 are included in this statement. 15.2.1-15.2.5-11 Revision 2 - March 2007 F. loss of nonemergency AC power to the station auxiliaries, G. loss of normal feedwater flow.1 4. In a review of the transients that could result from these postulated events, 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. This transient was evaluated by the applicant using a mathematical model that had been previously reviewed and found to be acceptable by the staff. The parameters used as input to this model were reviewed and found to be suitably conservative and in accordance with the recommendation of RG 1.105. The results of the analysis of the transient showed that cladding integrity was maintained by