Document: NUREG-0800
Document ID: 94ab38ac-ddfc-4ba1-ae38-bc25ffa6e976
Document Type: srp
Title: – 15.4.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070716.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
not exceeded during any condition of normal operation, including the effects of AOOs.29 4. Compliance with GDC 26 requires that one of the reactivity control systems shall use control rods capable of reliably controlling reactivity changes to ensure that, under conditions of normal operation, including anticipated operational occurrences, and with 15.4.4-7 DRAFT Rev. 2 - April 1996 appropriate margin for malfunctions such as stuck rods, specified acceptable fuel design limits are not exceeded. GDC 26 is applicable to this section because the reviewer evaluates the consequences of the events associated with startup of an inactive loop or a recirculation loop at an incorrect temperature and with a flow controller malfunction causing an increase in BWR core flow rate. This section, SRP Sections 15.4.4, 4.2 through 4.4 and 7.2 through 7.5, and Regulatory Guides 1.53 and 1.105 provide guidance for ensuring that the reactivity control system (control rods) is capable of reliably controlling reactivity changes with appropriate margin for malfunctions such as stuck rods. Meeting the requirements of GDC 26 provides assurance that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of AOOs.30 5. Compliance with GDC 28 requires that reactivity control systems be designed with appropriate limits on the potential amount and rate of reactivity increase to ensure that the effects of postulated reactivity accidents can neither (a) result in damage to the reactor coolant pressure boundary greater than limited local yielding nor (b) sufficiently disturb the core, its support structures, or other reactor pressure vessel internals to impair significantly the capability to cool the core. These postulated reactivity accidents shall include consideration of rod ejection (unless prevented by positive means), rod dropout, steam line rupture, changes in reactor temperature and pressure, and cold water addition. GDC 28 is