Document: 10 CFR Part 52
Document ID: fd69617e-7b5c-49e2-90ee-815727c55e10
Document Type: cfr
Title: Contents of applications; technical information.
Source: 10 CFR Part 52
Source URL: https://www.ecfr.gov/current/title-10/part-52/section-52.137
Revision Date: 
Chapter: 
Section ID: 52.137
CFR Part: 52
CFR Title: 10

Content:
gencies in the operation of the reactor facility or a major portion thereof; ( 12 ) An analysis and description of the equipment and systems for combustible gas control as required by § 50.44 of this chapter ; ( 13 ) The list of electric equipment important to safety that is required by 10 CFR 50.49(d) ; ( 14 ) A description of protection provided against pressurized thermal shock events, including projected values of the reference temperature for reactor vessel beltline materials as defined in 10 CFR 50.60 and 50.61 ; ( 15 ) Information demonstrating how the applicant will comply with requirements for reduction of risk from anticipated transients without scram (ATWS) events in § 50.62 ; ( 16 ) The coping analysis, and any design features necessary to address station blackout, as described in § 50.63 of this chapter ; ( 17 ) Information demonstrating how the applicant will comply with requirements for criticality accidents in § 50.68(b)(2)-(b)(4) ; ( 18 ) A description and analysis of the fire protection design features for the standard plant necessary to comply with part 50, appendix A, GDC 3, and § 50.48 of this chapter ; ( 19 ) A description of the quality assurance program applied to the design of the SSCs of the facility. Appendix B to 10 CFR part 50, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” sets forth the requirements for quality assurance programs for nuclear power plants. The description of the quality assurance program for a nuclear power plant shall include a discussion of how the applicable requirements of appendix B to 10 CFR part 50 were satisfied; ( 20 ) The information necessary to demonstrate that the standard plant complies with the earthquake engineering criteria in 10 CFR part 50, appendix S ; ( 21 ) Proposed technical resolutions of those Unresolved Safety Issues and medium- and high-priority generic safety issues which are identified in the version of NUREG-0933 current on the date up to 6