Document: NUREG-0800
Document ID: ecb92ac6-97df-4e4b-a20a-81638c2d573b
Document Type: srp
Title: - 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350157.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section of the corresponding review branch. II. ACCEPTANCE CRITERIA- The RSB acceptance criteria for maintaining control rod insertability and core coolability during a RCP rotor seisure or broken shaft event are based on meeting the relevant requirements of the following regulations: A. General Design Criteria 27 and 28, as they relate to the reactor coolant system being designed with appropriate margin to assure that the capability to cool the core is maintained. B. General Design Criterion 31, as it relates to the reactor coolant system being designed with sufficient margin to assure that the boundary behaves in a nonbrittle manner and that the probability of propagating fracture is minimized. C. 10 CFR Part 100, as it relates to the calculated doses at the site boundary. 15.3.3-r2 Rev. 2 - July 1981 The basic objectives of the review of the accident resulting from a rotor seizure or shaft break in a reactor coolant pump are: 1. To identify which of these accidents is the more limiting. 2. To verify that, for the accident, the plant responds in such a way that the criteria regarding fuel-damage, radiological consequences, and system pressure are met. The specific criteria necessary to meet the relevant requirements of GDC 27, 28, and 31 and 10 CFR Part 100 for the rotor seizure and shaft break event are: 1. Pressure in the reactor coolant and main steam systems should be maintained below acceptable design limits, considering potential brittle as well as ductile failures. 2. The potential for core damage is evaluated on the basis that it is accept- able if the minimum DNBR remains above the 95/95 DNBR limit for PWRs and the CPR remains above the MCPR safety limit for BWRs based on acceptable correlations (see SRP Section 4.4). If the DNBR or CPR falls below these values, fuel failure (rod perforation) must be assumed for all rods that do