Document: NUREG-0800
Document ID: 685c3a08-2aef-45d3-adfa-5101ca619cd1
Document Type: srp
Title: Revision 2 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070850035.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
CFR Part: 
CFR Title: 

Content:
lf toughness, the expected radiation sensitivity of the material (based on copper and nickel content, for example) and the neutron fluence expected at its location in the vessel. 3.2 SAR Criteria With respect to the adequacy of the surveillance program, information requested for beltline materials includes the following: (1) Tensile properties. (2) Dropweight test and Charpy V test results used to determine RTNDT. (3) Charpy V test results to determine the upper shelf toughness. (4) Composition, specifically the copper and nickel content. (5) Estimated maximum fluence for each beltline material. (6) List of materials included in the surveillance program, with basis used for their selection. 3.3 Surveillance Test Procedures Surveillance capsules must be removed and tested at intervals in accordance with Appendix H, 10 CFR Part 50. The proposed removal and test schedule should be included in the Technical Specifications. BTP 5-3-7 Revision 2 - March 2007 3.4 Reporting Criteria All information used to evaluate results of the tests on surveillance materials, evaluation methods, and results of the evaluation should be submitted with the evaluation report. This should include: (1) Original properties and compositions of the materials. (2) Fluence calculations, including original predictions, for both surveillance specimens and vessel wall. (3) Test results on surveillance specimens. (4) Basis for evaluation of changes in RTNDT and upper shelf toughness. (5) Updated prediction of vessel properties. 3.5 Technical Specification Changes Changes in the operating and test limits recommended as a result of evaluating the properties of the surveillance material, together with the basis for these changes, shall be submitted to the Office of Nuclear Reactor Regulation for approval. 4. Pressurized Thermal Shock (PWR only) 4.1 Pressurized Thermal Shock Requirements As required by 10 CFR 50.61, the following is a summary of requirements for the PWR reactor vessels: (1) RTPTS values