Document: NUREG-0800
Document ID: baab1f26-b869-4986-9c53-36842ceaa7c3
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070723.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
l patterns that are not precluded by an instrumentation system accepted under the review of SRP Section Chapter 7. 18 c. The reviewer determines that an acceptable and conservative function is used to describe the control rod worth as a function of control rod position and that the control rod position as a function of time is suitably conservative. d. The reviewer determines that conservative reactivity coefficients, notably the Doppler coefficient, are used and that they are compatible with those described in SRP Section 4.3. e. The reviewer assures ensures that the scram action is conservatively represented 19 in the use of the integral scram worth curve (SRP Section 4.3) and in the use of the scram delay time. f. The reviewer checks the analytical methods or assures ensures that they have been reviewed and approved previously. The reviewer may also perform an independent audit calculation using methods acceptable to the staff. The applicant's methods should account conservatively for all major reactivity feedback mechanisms. DRAFT Rev. 3 - April 1996 15.4.9-4 2. The reviewer inspects the results of the calculation of maximum reactor pressure to determine compliance with the second criterion listed in subsection II of this SRP (the reviewer may do an audit calculation when appropriate). 3. The number of fuel rods experiencing clad failure and fuel melting is determined (for use in evaluating the radiological consequences) by the following procedures: a. The reviewer determines that the transient critical power ratio (CPR) has been computed by an acceptable technique (either previously reviewed or reviewed de novo during this review) for analyses using full power conditions. b. The reviewer determines that the number of rods with enthalpy exceeding 170 cal/gm has been computed by an acceptable method. c. The reviewer determines that the amount of fuel exceeding melting conditions has been computed by an acceptable method. 4. For ABWR reviews, the reviewer compares