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
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Content:
REVIEW RESPONSIBILITIES Primary - Core Performance Branch (CPB)Reactor Systems Branch (SRXB)1 Secondary - Accident Evaluation Branch (AEB)Emergency Preparedness and Radiation Protection Branch (PERB)2 I. AREAS OF REVIEW The CPBSRXB evaluates the consequences of a control rod ejection accident in the area of 3 physicsto determine the potential damage caused to the reactor coolant pressure boundary and to determine whether the fuel damage resulting from such an accident could impair cooling water flow. The review covers the possible initial conditions, rod patterns and worths, scram worth as 4 a function of time, adequacy of the various reactivity coefficients, adequacy of the calculational methods, and any core parameters which affect the peak reactor pressure or the probability of fuel rod failure. The review also examines potential fission product releases resulting from a rod ejection accident. These releases contribute to the source term in analyses for determining compliance with dose limits specified in 10 CFR 100.11.5 This review applies to pressurized water reactors (PWRs) only.6 DRAFT Rev. 3 - April 1996 15.4.8-2 Review Interfaces The SRXB will coordinate other branch evaluations that interface with the overall review of rod ejection accidents, as follows:7 1. SRXB reviews the reactivity coefficient curves and control rod worths as part of its primary review responsibility under Standard Review Plan (SRP) Section 4.3.8 2. SRXB reviews theThe relevant thermal-hydraulic analyses are reviewedas part of its 9 primary review responsibility under SRP Section 4.4. 3. The AEBPERB reviews, as part of its secondaryprimary review responsibility, 10 described in the appendix tounder Appendix A to this SRP section, the radiological 11 consequences of a rod ejection accident. The PERB review by usinguses a source term 12 for dose calculations based on the amount of failed fuel as obtained by CPBSRXB from 13 the reactor core analyses under this SRP section. The evaluation