Document: NUREG-0800
Document ID: 65bf963b-2ae7-4caf-aee2-1ceabe52e775
Document Type: srp
Title: INITIAL PLANT TEST PROGRAM - FINAL SAFETY ANALYSIS REPORT1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070650.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.2
CFR Part: 
CFR Title: 

Content:
f the SRP and describes an acceptable initial test program, the successful completion of which will demonstrate the functional adequacy of plant structures, systems, and componentsSSCs . 78 For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP Section.79 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 80 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.81 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES82 DRAFT Rev. 3 - April 1996 14.2-14 201. 10 CFR Part 30, §30.53, "Tests." 21. 10 CFR Part 50, §50.34, "Contents of Applications; Technical Information." 223. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." 234. 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors."83 4. Regulatory Guide 1.18, "Structural Acceptance Test for Concrete Primary Reactor Containments.84 5. Regulatory Guide 1.9,