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:
DC. Review Interfaces Other SRP sections interface with this section as follows: 1. General information on transient and accident analyses is provided in SRP Section 15.0. 2. Design basis radiological consequence analyses associated with design basis accidents are reviewed under SRP Section 15.0.3. 3. Reactivity coefficients and control rod worths are reviewed under SRP Section 4.3. 4. Relevant thermal-hydraulic analyses are reviewed under SRP Section 4.4. 5. The applicant's determination of the reactor trip delay time (i.e., the time elapsed between when the sensed parameter reaches the level for which protective action is required and the onset of negative reactivity insertion) is reviewed under SRP Sections 7.2 and 7.3. The specific acceptance criteria and review procedures are contained in the reference SRP sections. II. ACCEPTANCE CRITERIA Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 1. General Design Criterion (GDC) 13, as to the availability of instrumentation to monitor variables and systems over their anticipated ranges to assure adequate safety, and of appropriate controls to maintain these variables and systems within prescribed operating ranges. 2. Acceptance criteria are based on GDC 28 requirements as to the effects of postulated reactivity accidents that result in neither damage to the reactor coolant pressure boundary greater than limited local yielding nor result in sufficient damage to impair significantly