Document: NUREG-0800
Document ID: 0e5dd9d7-fef0-46ca-ba6d-f3d06f5c7801
Document Type: srp
Title: REACTOR SYSTEMS (Tier 1)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070662.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.4
CFR Part: 
CFR Title: 

Content:
ly in the SER. 8. Ensure that any Tier 2* information is clearly designated in Tier 2, and consider expiration of these items at first full power, if appropriate. The staff's basis for designating the information as Tier 2* and the rationale for its decision that it requires prior NRC approval to change should be specified in the SER (See also the discussion in Appendix A to SRP Section 14.3). 9. Review Tier 1 definitions, legends, interface requirements, and site parameters to ensure that reactor systems issues are treated consistently and appropriately. 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. 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 52, §52.47 "Contents of Applications." 2. 10 CFR Part 52, §52.97 "Issuance of Combined Licenses." 3. NUREG-1503, "Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor", Volumes 1 and 2, July 1994. 4. NUREG-1462, "Final Safety Evaluation Report Related to the Certification of