Document: NUREG-0800
Document ID: ff5838f8-986a-4d8b-a039-fb26df280426
Document Type: srp
Title: – 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070725.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
power level is taken as the licensed core thermal power for the number of loops initially assumed to be operating plus an allowance of 2% to account for power measurement uncertainties, unless a lower power level can be justified by the applicant. The number of loops operating at the initiation of the event should correspond to the operating condition which maximizes the consequences of the event. b. Conservative scram characteristics are assumed, i.e., for a PWR maximum time delay with the most reactive rod held out of the core and for a BWR a design conservatism factor of 0.8 times the calculated negative reactivity insertion rate. c. The core burnup is selected to yield the most limiting combination of moderator temperature coefficient, void coefficient, Doppler coefficient, axial power profile, and radial power distribution. d. Mitigating systems should be assumed to be actuated in the analyses at setpoints with allowance for instrument inaccuracy in accordance with Regulatory Guide 1.105. Compliance with Regulatory Guide 1.105 is determined by ICSBHICB under the SRP Chapter 7 reviews.41 Technical Rationale The technical rationale for application of these acceptance criteria to reviewing the inadvertent operation of the ECCS and of the chemical and volume control system malfunctions is discussed in the following paragraphs:42 DRAFT Rev. 2 - April 1996 15.5.1-6 1. Compliance with GDC 10 requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to ensure that fuel design limits are not exceeded during anticipated operational occurrences. The requirements of GDC 10 apply to this section because the reviewer evaluates certain events occurring with moderate frequency and having the potential to result in exceeding fuel design limits. The reviewer evaluates the models for determining the values of the fuel design parameters during such accidents to ensure that the limits will not be exceeded. Meeting