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:
. 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 finding provided is as indicated in the attached Appendix.14 4. The Instrumentation & Controls Branch (HICB) reviews the The applicant's 15 determination of the reactor trip delay time, i.e., the time elapsed between the instant the sensed parameter reaches the level for which protective action is required and the onset of negative reactivity insertion, is reviewedas part of its primary review responsibility under SRP Sections 7.2 and 7.3. II. ACCEPTANCE CRITERIA 1. CPBSRXB acceptance criteria are based on meeting the requirements of General 16 Design Criterion 28 (GDC 28)(Ref. 1) as it relates to the effects of postulated reactivity 17 accidents that neither resulting in damage to the reactor coolant pressure boundary greater than limited local yielding, nor causing cause sufficient damage to impair 18 significantly the capacity to cool the core. Regulatory positions and specific guidelines necessary to meet the relevant requirements of GDC 28 are in Regulatory Guide 1.77.19 Regulatory Guide 1.77 (Ref. 2) identifies acceptable analytical methods and 20 assumptions that may be used in evaluating the consequences of a control rod ejection accident. Specific criteria used by CPBSRXB in evaluating the control rod ejection 21 accident are: a. Reactivity excursions should not result in a radially averaged enthalpy greater than 280 cal/gm at any axial location in any fuel rod. 22 b. 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 Boiler and Pressure 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