Document: 10 CFR Part 50
Document ID: d0ed3b22-f5a8-42b0-8cac-2e9eadacfdb8
Document Type: cfr
Title: Contents of applications; technical information.
Source: 10 CFR Part 50
Source URL: https://www.ecfr.gov/current/title-10/part-50/section-50.34
Revision Date: 
Chapter: 
Section ID: 50.34
CFR Part: 50
CFR Title: 10

Content:
ored into the final design of the facility. For licensees identified in the introduction to paragraph (f) of this section, all studies must be completed no later than 2 years following the issuance of the construction permit or manufacturing license. [ 5 ] For all other applicants, the studies must be submitted as part of the final safety analysis report. ( i ) Perform a plant/site specific probabilistic risk assessment, the aim of which is to seek such improvements in the reliability of core and containment heat removal systems as are significant and practical and do not impact excessively on the plant. (II.B.8) ( ii ) Perform an evaluation of the proposed auxiliary feedwater system (AFWS), to include (applicable to PWR's only) (II.E.1.1): ( A ) A simplified AFWS reliability analysis using event-tree and fault-tree logic techniques. ( B ) A design review of AFWS. ( C ) An evaluation of AFWS flow design bases and criteria. ( iii ) Perform an evaluation of the potential for and impact of reactor coolant pump seal damage following small-break LOCA with loss of offsite power. If damage cannot be precluded, provide an analysis of the limiting small-break loss-of-coolant accident with subsequent reactor coolant pump seal damage. (II.K.2.16 and II.K.3.25) ( iv ) Perform an analysis of the probability of a small-break loss-of-coolant accident (LOCA) caused by a stuck-open power-operated relief valve (PORV). If this probability is a significant contributor to the probability of small-break LOCA's from all causes, provide a description and evaluation of the effect on small-break LOCA probability of an automatic PORV isolation system that would operate when the reactor coolant system pressure falls after the PORV has opened. (Applicable to PWR's only). (II.K.3.2) ( v ) Perform an evaluation of the safety effectiveness of providing for separation of high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) system initiation levels so that the RCIC system