Document: NUREG-0800
Document ID: a4f5c92f-1c1f-4a9c-b4d4-cb2fcc282cae
Document Type: srp
Title: PUMP FLYWHEEL INTEGRITY (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340666.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.1.1
CFR Part: 
CFR Title: 

Content:
ed surfaces. 4. Flywheel Design The flywheel design information including allowable stresses, design overspeed considerations, and shaft and bearing design adequacy, is reviewed. 5. Overspeed Test The applicant's overspeed test procedures are reviewed to establish their adequacy. 6. Inservice Inspection A description of the preservice and postoperational phases of the inservice inspection program, including types of inspections, areas inspected, frequencies of inspection, and flaw acceptance criteria, is reviewed. The review for quality assurance is coordinated and performed by the Quality Assurance Branch (QAB) as part of its primary review responsibility for Standard Review Plan Sections 17.1 and 17.2. The acceptance criteria neces- sary for the review and the methods of application are contained in the referenced SRP section. II. ACCEPTANCE CRITERIA The MTEB acceptance criteria are based on meeting the relevant requirements of the following regulations: A. General Design Criterion 1 and 10 CFR Part 50, §50.55a(a)(1), as they relate to pump flywheel design, materials selection, fracture toughness, preservice and inservice inspection programs, and overspeed test procedures to determine their adequacy to assure a quality product commensurate with the importance of the safety function to be performed. 5.4.1.1-2 Rev. 1 - July 1981 B. General Design Criterion 4, as it relates to protecting safety-related structures, systems, and components of nuclear power plants from the effects of missiles that might result from reactor coolant pump failure. The following regulatory guide provides positions acceptable to the staff in meeting the requirements listed above: Regulatory Guide 1.14 which describes a method of minimizing the potential for failures of the flywheels of reactor coolant pump motors in light-water-cooled power reactors. Specific criteria necessary to meet the relevant requirements of GDC 1 and 4 and 10 CFR Part 50, §50.55a(a)(1) are as follows: 1. Materials