Document: NUREG-0800
Document ID: acd9ebb4-ee58-4db4-b1b3-47182cad2c4f
Document Type: srp
Title: Safe Shutdown Earthquake
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0423/ML042390209.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.5.2.6
CFR Part: 
CFR Title: 

Content:
afi. 23 OL applications are reviewed for any new information developed subsequent to 24 the CP safety evaluation report SER. The review will also determine whether 25 the CP recommendations have been implemented. 26 A typical OL-stage summary finding for this section of the SER follows: 27 In our review of the seismologic aspects of the plant site, we have 28 considered pertinent information gathered since our initial seismologic 29 review whieb atu as made in conjunction with the issuance of the 30 Construction Permit. This new information includes data gained from 31 both site and near-site investigations as well as from a review of 32 recently published literature. 2.5.2-17 1 As a result of our recent review of the seismologic information, we have J 2 determined that our earlier conclusion regarding the safety of the plant 3 from a seismological standpoint remains valid. These conclusions can be 4 summarized as follows: 5 1. Seismologic information provided by the applicant and required by 6 Appendi4xA te El 10 CFR Part 100 provides an 7 adequate basis to establish that no eapable fault-, 8 exist in the plant site area wh4eh E would cause earthquakes to 9 be centered there. 10 2. The response spectrum proposed for the safe shutdown earthquake is 11 the appropriate free-field response spectrum in conformance with 12 Append-ixA bto 10 CFR Part 100. 13 The new information reviewed for the proposed nuclear power plant is 14 discussed in Safety Evaluation Report Section 2.5.2. 15 The staff concludes that the site is acceptable from a seismologic KUJ16 standpoint and meets the requirements of (1) 10 CFR Part 50, Appendix A 17 (General Design Criterion 2), (2) 10 CFR Part 100, and (3) 10 CFR Part 18 100, . This conclusion is based on the 19 following: 20 1. The applicant has met the requirements of: 21 a. 10 CFR Part 50, Appendix A, General Design Criterion 2 with 22 respect to protection against natural phenomena such as 23 faulting. 24 b. 10 CFR Part 100, Reactor