Document: NUREG-0800
Document ID: 0b17303b-e5cc-4091-b22c-056b0c78eb34
Document Type: srp
Title: – 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070707.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
ry and reactor vessel as part of its primary review responsibility for SRP Sections 5.2.3 and 5.3.1.18 4. The SPLB reviews the integrity of the reactor coolant pump seals as part of its primary review responsibility for SRP Section 9.2.2.19 For those areas of review identified above as being reviewed as part of the primary review responsibility of other 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 RSBSRXB acceptance criteria for maintaining the ability to insert the control rods insertability and to cool the core coolability during a RCP rotor seizure or broken shaft event 20 are based on meeting the relevant requirements of the following regulations: A. General Design Criterion (GDC) 17, as it relates to providing onsite and offsite electric power systems to ensure that structures, systems, and components important to safety will function. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to ensure that design conditions of the reactor coolant pressure boundary are not exceeded and the core is cooled in the event of postulated accidents.21 AB. General Design Criteria 27 (GDC 27) and 28 (GDC 28), as they relate to the reactor 22 23 coolant system being designed with appropriate margin to assure ensure that the 24 capability to cool the core is maintained. BC. General Design Criterion 31 (GDC 31), as it relates to the reactor coolant system being 25 designed with sufficient margin to assure ensure that the boundary behaves in a nonbrittle manner and that the probability of propagating fracture is minimized. CD. 10 CFR Part 100, as it relates to the calculated doses at the site boundary. DRAFT Rev. 3 - April 1996 15.3.3-4 The basic objectives of the review of the accident resulting from a rotor seizure or shaft break in a reactor