Document: NUREG-0800
Document ID: 2f83f917-2d38-4def-9f6a-6368d0c22116
Document Type: srp
Title: SPECTRUM OF ROD EJECTION ACCIDENTS (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070721.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.8
CFR Part: 
CFR Title: 

Content:
e reviewer determines that the maximum value does not exceed 280 cal/gm. 2. Verification of compliance with the second acceptance criterion II.1.b is accomplished 39 as follows: a. The same procedures considered in steps a–f above are followed. 15.4.8-5 DRAFT Rev. 3 - April 1996 b. For each accident, the maximum primary system pressure should be calculated by an analytical method acceptable to the staff or, as before, an independent audit calculation is made by the staff. The reviewer checks the results (as obtained by the applicant or the staff) for compliance with the second criterion. 3. To meet acceptance criterion II.2, theThe number of fuel rods experiencing clad failure 40 is determined (for use by the Appendix A reviewer in evaluating the radiological 41 consequences of the rod ejection accident) by the following procedure: a. The reviewer determines that an acceptable procedure for calculating a departure from nucleate boiling condition during the reactivity excursion has been used. This may be done by referring to previous cases for the same nuclear steam supply system (NSSS) vendor. If no approved technique is available, as might be the case for the first project using a new or substantially revised model, the reviewer must perform a separate detailed review (which may be documented separately in a topical report). b. The reviewer must determine that the number of rods used in the radiological evaluation is the number of rods calculated to have a departure from nucleate boiling. Departure from nucleate boiling must be calculated in accordance with the criteria reviewed and accepted under SRP Section 4.4. Typically, the criterion defines a departure from nucleate boiling ratio (DNBR) less than 1.30 when DNB correlations such as W-3 (Ref. 4) or BAW-2 (Ref. 5) are used. For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the