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:
ALYSIS, AND REPORT ORGANIZATION , This chapter is to describe the overall approach to the analysis and out- 1 i ne the individual tasks in terms of the nature and source of input, the methods used for analysis, and the nature and subsequent use of the output. The inter- relationship of the tasks should be described and should be illustrated by a flow chart. How the analysis tasks are integrated to achieve the results and conclusions is to be described. Major emphasis should be placed on analyzing event sequences leading to vessel through-wal 1 cracking and corrective actions to prevent this from occurri ng. The report should include both probabilistic and deterministic fracture mechanics analyses. The probabi 1 i stic analyses should be used to determine the statistical 1 i kel i hood of vessel through-wal 1 crack penetration assuming a crack size distribution appropriately justified for the vessel being analyzed and appropriate uncertainties and distribution of the significant input param- eter such as material properties. The deterministic analyses should be used to evaluate the critical time interval in the transient during which mitigat- ing action can be effective. The deterministic analyses should be carried out using the two sigma upper and lower bounding values of the appropriate param- eters such as fluence, copper content, nickel content, fracture initiation toughness, fracture arrest toughness, and ductile fracture toughness. The input to the probabilistic analysis should be best estimates based on appropriate assumptions. Uncertainties and conservatisms should be explicitly , presented in the decision rationale for the 1 icensee' s proposed corrective mea- sures and basis for continued operation. The analysis should include effects of operator actions, control system interactions, and support systems such as electric power, instrument air, and service water cooling. The report should be organized by starting with a description in Chapter 1 of how the