Document: NUREG-0800
Document ID: dac334d4-585f-42f5-bde4-118e876f5d4c
Document Type: srp
Title: PIPING SYSTEMS AND COMPONENTS (Tier 1)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070660.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.3
CFR Part: 
CFR Title: 

Content:
Review" section above (SPLB and SRXB). IV. EVALUATION FINDINGS Each review branch verifies that sufficient information has been provided to satisfy the requirements of this SRP section, and concludes that Tier 1 is acceptable. A finding similar to that discussed in the Evaluation Findings section of SRP Section 14.3 should be included in a separate section of the SER. In addition, if DAC are used, a separate finding on the DAC should be included in the SER. 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 design certification and combined license applications submitted by applicants pursuant to 10 CFR 52. Except in those 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. VI. REFERENCES 1. 10 CFR Part 50, §50.55a, "Codes and Standards." 2. 10 CFR Part 52, §52.47 "Contents of Applications." 3. 10 CFR Part 52, §52.97 "Issuance of Combined Licenses." 4. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 5. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 6. 10 CFR Part 50, Appendix A, General Design Criterion 30, "Quality of Reactor Coolant Pressure Boundary." 7. NUREG-1503, "Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor", Volumes 1 and 2, July 1994. 8. NUREG-1462, "Final Safety Evaluation Report Related to the Certification of the System 80+ Design," Volumes 1 and 2, August 1994. DRAFT Rev. 0 - April 1996