Document: NUREG-0800
Document ID: ef559b35-0671-46e4-b172-09155cca8b81
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350427.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
d review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically. as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Washington, D.C. 2055 Specific criteria necessary to meet the relevant requirements of GDC 28 are as follows: 1. Reactivity excursions should not result in radially averaged fuel rod enthalpy greater-than 280 cal/gm at any axial location .in any fuel rod. 2. The maximum reactor pressure during any portion of the assumed excursion should be less than the value that will cause stresses to exceed the "Service Limit C" as defined in the ASME Code. (Ref. 3). 3. The number of fuel rods predicted to reach assumed fuel failure thresholds and associated parameters such as the amount of fuel reaching melting conditions will be an input to a radiological evaluation. The assumed failure thresholds are a radially averaged fuel rod enthalpy greater than 170 cal/gm at any axial location for zero or low power initial conditions, and fuel cladding dryout for rated power initial conditions. III. REVIEW PROCEDURES 1. Review of the applicant's analyses showing compliance with the first of