Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
he pumps. This will ensure SBLOCA ECCS performance is not later degraded and pump damage is also avoided. The following steps shall be included in PWR emergency operating procedures as a condition for reactor coolant pump startup after a small break LOCA: A. Verify adequate single phase natural circulation, B. If single phase natural circulation cannot be established, verify adequate two phase natural circulation, C. Determine if reactor coolant pump restart is needed and desired, and D. Verify that all reactor coolant pump restart criteria are met. 11. The TMI Action Plans items are reviewed to assure compliance with the acceptance criteria. A. The reviewer evaluates the uncertainty analyses performed by the applicant to assure that the modeling assumptions and phenomena for small-break LOCA calculations are properly accounted for to determine the acceptability of the ECCS performance pursuant to 10 CFR 50.46 and Regulatory Guide 1.157 or Appendix K of 10 CFR Part 50 (Item II.E.2.3). B. For Babcock and Wilcox designs, the reviewer confirms that the auxiliary feedwater system upgrade and automatic auxiliary feedwater initiation performed 15.6.5-12 Revision 3 - March 2007 under this TMI action plan item have been properly accounted for in the LOCA analyses (Item II.K.2.8). C. The reviewer evaluates the assumptions made regarding reactor coolant pump trip to assure that they are consistent and conservatively modeled with respect to the final pump trip criteria which result from resolution of TMI action plan (Item II.K.3.5). D. If, as a result of a LOCA, or as a result of loss of A/C power, containment isolation is indicated to occur, the reactor coolant pump component cooling water may be lost. The reviewer evaluates the applicant's submittal to determine that the reactor coolant pump seal integrity is not lost. If it cannot be established that seal integrity is assured, the reviewer assures that the evaluation of this event correctly accounts for seal failure (Item