Document: NUREG-0800
Document ID: 6997f9d9-dedc-49d7-ac15-7615c1bd9713
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550015.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
ed parameters and instrument indications. 2. GDC 28 requires reactivity control system design with appropriate limits on the potential reactivity amount and rate increases so the effects of postulated reactivity accidents neither result in damage to the reactor coolant pressure boundary greater than limited local yielding nor disturb the core, its support structures, or other reactor pressure vessel internals sufficiently for serious impairment of core cooling capability. 3. GDC 28 applies to this section because it is for review of BWR reactivity excursions caused by control rod drop accidents. The review assesses the transient fuel enthalpy for whether cladding failure or fuel rupture is predicted and to what extent, establishes both the coolability of the core after the transient and the source term for evaluation of radiological consequences, and determines the maximum reactor coolant pressure so stress limits for the reactor pressure vessel are not exceeded. 4. GDC 28 requirements provide assurance that fuel damage and reactor vessel pressure will not be excessive in a BWR control rod drop accident. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. 15.4.9-4 Revision 3 - March 2007 These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. The reviewer should be guided by the general considerations in the introductory section to this SRP chapter. Initial conditions and assumptions defining the limiting scenario for each of the subsection II acceptance criteria (e.g. fuel rod failure, peak pressure, long-term cooling) and maximizing fuel rod failures due to each failure mechanism (e.g. pallet/cladding mechanical interaction