Document: NUREG-0800
Document ID: 1085af08-a4b7-4fe7-bfed-ca7a60f2022c
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070734.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
t have been previously documented and reviewed and approved by the staff. Should the LOCA blowdown calculations 8 be modified for the purpose of studying structural behavior (for example, core support structure design, control rod guide structure design, steam generator design, reactor coolant system piping and support structure design), all differences should be identified and described by the applicant. RSBSRXB reviews these modifications, including analytical techniques, computer programs, 9 values of input parameters, break size, type, and location, and all other pertinent information, and makes recommendations regarding their acceptability to other branches as required. RSBSRXB initiates a generic computer program review as required. 10 The SRXB review of this SRP section covers the following areas:11 1. The RSBSRXB is also responsible for the review of the failure mode analysis of the 12 ECCS to verify that an adequate analysis of possible failure modes of ECCS equipment and the effect of the failure modes on the ECCS performance has been provided in 13 conjunction with the effort described in SRP Section 6.3. 2. The RSBSRXB reviews the analytical techniques and computer programs used by the 14 applicant for the blowdown, refill, and reflood portions of the loss-of-coolant transient. 3. The RSBSRXB also reviews the analytical techniques and computer programs used by 15 the applicant for power transient calculations (including moderator temperature, void and fuel temperature feedback effects, and decay heat) and for the cladding temperature, 16 cladding rupture and swelling calculations. 15.6.5-3 DRAFT Rev. 3 - April 1996 4. The RSBSRXB will performs independent audit blowdown, refill, reflood and cladding 17 calculations as required to verify the applicant's conclusions. 5. For a small break loss-of-coolant accident, the SRXB reviews the potential for the addition of un-borated water into the core from reactor coolant pump seals, and the potential for