Document: NUREG-0800
Document ID: 866c6ef6-2f4a-45c7-9e71-43e1f66a8422
Document Type: srp
Title: Draft Revision 3– July 2018
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1807/ML18071A066.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
CFR Part: 
CFR Title: 

Content:
ssure Temperature Limit Curves and Low Temperature Overpressure Protections System Limits,” which relocate portions of the subject requirements from the Technical Specifications (TS). The purpose of this branch technical position is to summarize these requirements and provide guidance, as necessary. Since many of these requirements were not in force when some plants were designed and built, this position also provides guidance for applying the requirements to these older plants. Also included is a description of acceptable procedures for making the conservative estimates and assumptions for older plants that may be used to show compliance with the new requirements. In a memo dated January 30, 2014, industry found that one of the methodologies for conservatively estimating reactor vessel material properties provided in B1.1 of this branch technical position was potentially non-conservative. In response, both industry and the NRC evaluated the methodologies provided under B1.1 and B1.2 for estimating material properties and assessed the impact of potential non-conservatisms on operating plants regarding pressure-temperature limits and PTS. The NRC’s assessment was documented in an April 11, 2017 memorandum with attachments assessing the industry’s two summary reports on this issue and addressing all technical issues related to B1.1 and B1.2. Based on the change-in-risk analyses documented in the memorandum, the NRC determined that the methodologies in B1.1 and B1.2 can be used in pressure-temperature limits and PTS evaluations for up to 72 effective full power years of operation. B. BRANCH TECHNICAL POSITION 1. Preservice Fracture Toughness Test Requirements. The fracture toughness of all ferritic materials used for pressure-retaining components of the reactor coolant pressure boundary shall be evaluated in accordance with the requirements of Appendix G, “Fracture Toughness Criteria for Protection Against Failure,” 10 CFR Part 50, as augmented by the