Document: NUREG-0800
Document ID: 26aca061-b0de-4983-bbca-3fccb00afc2f
Document Type: srp
Title: PRESSURE-TEMPERATURE LIMITS AND PRESSURIZED THERMAL SHOCK1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070431.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2
CFR Part: 
CFR Title: 

Content:
ses. This would include consideration of the initial RT , the upper shelf toughness, NDT the expected radiation sensitivity of the material (based on copper and phosphorousnickel content, for example) and the neutron fluence expected at its 127 location in the vessel. 3.2 SAR Requirements The adequacy of the surveillance program cannot be evaluated unless all pertinent information is included in the SAR. Information requested for beltline materials includes the following: (1) Tensile properties. (2) DWT and Charpy V test results used to determine RT . NDT (3) Charpy V test results to determine the upper shelf toughness. (4) Composition, specifically the copper and phosphorous 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 shall be included in the Technical Specifications. 5.3.2-25 DRAFT Rev. 2 - April 1996 3.4 Reporting Requirements 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 RT and upper shelf toughness. NDT (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 Division of LicensingOperating Reactor Support for approval. 128 DRAFT Rev. 2 - April 1996 5.3.2-26