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:
emperature and current RTNDT at that location. h. Diagnostic instrumentation and displays. i. Primary coolant system pump trip logic.. j. Automatic isolation of auxiliary feedwater to broken steam 1 i nedgenerators. 2. Increased Temperature of Emergency Core Cooling Water and Emergency Feedwater If plant modifications are proposed to prevent overcooling, the report should include an evaluation of undesirable side effects (i.e., undercooling) and a discussion of steps planned to ensure that the modifications represent a net improvement in safety when PTS and non-PTS related events are considered. 8.5 In Si tu Anneal i ng If in situ annealing is part of the licensee's program of corrective mea- sures, the licensee should describe the program to ensure that annealing will achieve the planned increase in vessel toughness, the surveillance program to monitor vessel toughness after annealing, the program directed toward code requalification after annealing, and the program to ensure that annealing does not introduce other safety problems. 9. FURTHER ANALYSES The PTS rule (Q 50.61 of 10 CFR Part 50) requires Commission approval for plant operation with RTpTS values above 270°F. This regulatory guide out1 ines the analyses that should be performed in support of any request to operate a t R T ~ ~ ~ values in excess of 270°F, as required in paragraphs 50,6l(b)(4) and 50.61(b)(5), and states that the s t a f f ' s primary acceptance criterion wi 11 be licensee demonstration that expected through-wall crack frequency will be below 5 x per reactor year for such operation. In the event that a licensee i s unable to meet this primary acceptance criterion, he may request Commission approval for continued operation under the provisions of paragraph 50.61(b)(6), which allows the 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