Document: 10 CFR Part 52
Document ID: 9805c5dc-79e7-4f14-88c7-530acc92c17e
Document Type: cfr
Title: Contents of applications; technical information in final safety analysis report.
Source: 10 CFR Part 52
Source URL: https://www.ecfr.gov/current/title-10/part-52/section-52.79
Revision Date: 
Chapter: 
Section ID: 52.79
CFR Part: 52
CFR Title: 10

Content:
ected values of the reference temperature for reactor vessel beltline materials as defined in §§ 50.60 and 50.61(b)(1) and (b)(2) of this chapter ; ( 8 ) An analysis and description of the equipment and systems for combustible gas control as required by § 50.44 of this chapter ; ( 9 ) The coping analyses, and any design features necessary to address station blackout, as described in § 50.63 of this chapter ; ( 10 ) A description of the program, and its implementation, required by § 50.49(a) of this chapter for the environmental qualification of electric equipment important to safety and the list of electric equipment important to safety that is required by 10 CFR 50.49(d) ; ( 11 ) A description of the program(s), and their implementation, necessary to ensure that the systems and components meet the requirements of the ASME Boiler and Pressure Vessel Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants in accordance with 50.55a of this chapter; ( 12 ) A description of the primary containment leakage rate testing program, and its implementation, necessary to ensure that the containment meets the requirements of appendix J to 10 CFR part 50; ( 13 ) A description of the reactor vessel material surveillance program required by appendix H to 10 CFR part 50 and its implementation; ( 14 ) A description of the operator training program, and its implementation, necessary to meet the requirements of 10 CFR part 55 ; ( 15 ) A description of the program, and its implementation, for monitoring the effectiveness of maintenance necessary to meet the requirements of § 50.65 of this chapter ; ( 16 ) ( i ) The information with respect to the design of equipment to maintain control over radioactive materials in gaseous and liquid effluents produced during normal reactor operations, as described in § 50.34a(d) of this chapter ; ( ii ) A description of the process and effluent monitoring and sampling program required by appendix I to 10 CFR part 50 and its