Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
in previous PSARs, FSARs, and licensing topical reports. All previous reviews on which the current review depends should be referenced so that the plant safety evaluation report comprises a completely documented safety evaluation. In particular, the NRC safety evaluation reports for all relevant licensing topical reports should be cited. Staff in the organization responsible for reactor systems has also performed certain generic reviews, the findings of which have been issued as NUREG or WASH series reports. At the present time, these reports include WASH-1236, NUREG-75/077, NUREG-0085, NUREG-0303, NUREG-0401, and NUREG-0418, and they should all be appropriately cited in the plant safety evaluation reports. These reports should also cite the applicable RGs (RG 1.3, RG 1.4, RG 1.25, RG 1.60, RG 1.77, RG 1.126, RG 1.157, and RG 1.183). Deviation from these guides or positions should be explained. After briefly discussing related reviews, the plant safety evaluation should concentrate on those areas in which the application is not identical to one previously reviewed and approved and on areas related to newly discovered problems. Analytical predictions discussed in Subsection II.3.C will be reviewed in PSARs, FSARs, or licensing topical reports. The validity of analytical models used to predict the performance of the fuel system design, and their applicability up to the design’s specified burnup and power limit, should be reviewed. Fuel burnup and power limits should be specified for each fuel type used in the reactor and justified based on irradiated material properties data and prototypic test results. An exception may be made for prototype test assemblies, in which case only an estimate of the maximum burnup and power needs to be provided. When the methods are being reviewed, the staff may perform calculations to verify the adequacy of the analytical methods. Thereafter, audit calculations will not typically be performed to verify the results of an approved method