Document: NRC Regulatory Guide
Document ID: da2e0703-3488-44b0-b6d0-089aac7cae3d
Document Type: regulatory_guide
Title: Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740028.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.154
CFR Part: 
CFR Title: 

Content:
submittal of further anal- yses. The content of these further analyses would be determined by the licensee and might include topics such as overall plant risk analyses that are beyond the scope of the vessel failure analyses covered by this regulatory guide. 10. RESULTS AND CONCLUSIONS REGARDING PTS ANALYSES 1 This chapter i s to summarize the models used and the results obtained and provide the conclusions reached with respect to continued operation of the plant. 10.1 Summary of Analysis In this section the major findings of each aspect of the PTS analysis, as described i n the previous chapters, should be presented. These should include: O Expected (mean) value of frequency of reactor vessel through-wall crack penetration versus time, w i t h uncertainty bound (95th percentile). O Identi f ication of dominant accident sequences. O If sensitivi ty/uncertainty analysis shows that slightly different assumptions could lead to different dominant sequences, identification of these assumptions and discussion of the impact on results given the different assumptions. O Identification of important operator actions, control actions, and plant features that can increase or decrease the frequency or severity of overcooling transients, and whether these have been appropriately balanced to ensure optimum overall plant safety. O Major sources and magnitudes of uncertainty i n the analysis. O The re1 ative effectiveness of potential a1 ternati ve corrective measures in reducing the expected (mean) value of through-wall crack penetration. O The program of planned corrective measures. 10.2 Basis for Continued Operation Finally, as part o f the plant-specific analysis package, the licensee should provide a basis for concluding whether or not continued plant operation i s justified. The basis for continued operation should include comparison with NRC's PTS acceptance criteria given in the Introduction to this guide. REFERENCES I -i 1. T. 3. Burns e t a1 . , "Preliminary Development o