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:
ive materials expected to be produced in the operation and the means for controlling and limiting radioactive effluents and radiation exposures within the limits set forth in part 20 of this chapter ; ( 6 ) The information required by § 20.1406 of this chapter ; ( 7 ) The technical qualifications of the applicant to engage in the proposed activities in accordance with the regulations in this chapter; ( 8 ) The information necessary to demonstrate compliance with any technically relevant portions of the Three Mile Island requirements set forth in 10 CFR 50.34(f) , except paragraphs (f)(1)(xii), (f)(2)(ix), and (f)(3)(v) of 10 CFR 50.34(f) ; ( 9 ) For applications for light-water-cooled nuclear power plants, an evaluation of the standard plant design against the Standard Review Plan (SRP) revision in effect 6 months before the docket date of the application. The evaluation required by this section shall include an identification and description of all differences in design features, analytical techniques, and procedural measures proposed for the design and those corresponding features, techniques, and measures given in the SRP acceptance criteria. Where a difference exists, the evaluation shall discuss how the proposed alternative provides an acceptable method of complying with the Commission's regulations, or portions thereof, that underlie the corresponding SRP acceptance criteria. The SRP is not a substitute for the regulations, and compliance is not a requirement; ( 10 ) 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 described in 10 CFR 50.34a(e) ; ( 11 ) The information pertaining to design features that affect plans for coping with emergencies 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