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:
ssure Vessel Code (Ref. 3). 23 24 15.4.8-3 DRAFT Rev. 3 - April 1996 c.2. The requirements of 10 CFR 100.11 establish radiation dose limits for individuals at the boundary of the exclusion area and at the outer boundary of the low population zone. 25 The fission product inventory in the fuel rods calculated to experience a departure from nucleate boiling (DNB) condition is an input to the radiological evaluation performed under SRP Section 15.4.8, Appendix A, by AEBPERB. The radiological criteria used 26 27 in the evaluation of control rod ejection accidents (PWRs) are given in Appendix B of Regulatory Guide 1.77 (Ref. 2).28 Technical Rationale The technical rationale for application of these acceptance criteria to reviewing the spectrum of control rod ejection accidents is discussed in the following paragraphs:29 1. Compliance with GDC 28 requires that the reactivity control system be designed with appropriate limits on potential reactivity increases to ensure that the effects of a rod ejection accident can neither result in damage to the reactor coolant pressure boundary nor cause sufficient disturbance to impair the capability to cool the core. The requirements of GDC 28 apply to this section because the reviewer evaluates the maximum reactor pressure during any portion of the transient corresponding to a rod ejection. ASME Codes provide guidance concerning the acceptability of anticipated accident pressure. The review also examines the extent of fuel damage resulting from a rod ejection accident. Regulatory Guide 1.77 provides guidance concerning acceptability of anticipated core damage. Meeting this criterion provides assurance that the capability to bring the reactor to a safe shutdown condition will not be impaired by a control rod ejection accident.30 2. Compliance with 10 CFR 100.11 requires that the exclusion area and the low population zone be defined on the basis of assurances that specified limits will not be exceeded for radiation doses from postulated