Document: NUREG-0800
Document ID: 598d070d-fb96-43ce-ad4f-27f14623be46
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350119.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15
CFR Part: 
CFR Title: 

Content:
for radiological dose calculations. For such accidents, fuel failure must be assumed for all rods for which the DNBR or CPR falls below those values cited above for cladding integrity unless it can be shown, based on an acceptale fuel damage model (see SRP Section 4.2) that fewer failures occur. There shall be no loss of function of any fission product barrier other than the fuel cladding. 3. The applicant should analyze these transients using an acceptable analytical model. The equations, sensitivity studies, and models described in Refer- ences 4 through 7 are acceptable. If other analytical methods are proposed by the applicant, these methods are evaluated by the staff for acceptability. For new generic methods, the reviewer requests an evaluation by. RSB. The values of the parameters used in the analytical model should be suitably conservative. The following values are considered acceptable for use in the model: a. The reactor is initially at 102% of the rated (licensed) core thermal power (to account for a 2% power measurement uncertainty), and primary loop of flow is at the nominal design flow less the flow measurement uncertainty. b. Conservative scram characteristics are assumed, i.e., maximum time delay with the most reactive rod held out of the core for PWRs and a 0.8 multiplier on the predicted reactivity insertion rate for BWRs. 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. 15.2.1-4 Rev. 1 - July 1981 III. REVIEW PROCEDURES The procedures below are used during both the construction permit (CP) and opera- ting license (OL) reviews. During the CP review the values of system parameters and setpoints used in the analysis will be preliminary in nature and subject to change. At the OL'review stage, final values should be used in the'analysis, and the reviewer should compare these to the limiting safety system