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:
voiding grossly overconservative assumptions and procedures. 2.3 Reporting Requirements The Technical Specifications must include the operating and test limits discussed above, and the basis for their determination. The Technical Specifications must also include information on the intended operating procedures, and justify that adequate margins between the expected conditions and the limit conditions will be provided to protect against unexpected or upset conditions. 3. Inservice Surveillance of Fracture Toughness The reactor vessel may be exposed to significant neutron radiation during the service life. This will affect both the tensile and toughness properties. A material surveillance program in conformance with Appendix H, 10 CFR Part 50, must be carried out. DRAFT Rev. 2 - April 1996 5.3.2-24 3.1 Surveillance Program Requirements The minimum requirements for the surveillance program are covered by Appendix H, 10 CFR Part 50. It is strongly recommended that consideration bybe given to the desirability of additional surveillance methods, such as the 125 inclusion of CT, DWT, DT, or other specimens to provide the capability of redundant test methods and analytical procedures, particularly if the estimated neutron fluence is over 2x10 , or the toughness of the vessel material is marginal. 19 The selection of material to be included in the surveillance program should be in accordance with ASTM E-185-7382 , unless the intent of the program is better 126 realized by using more rigorous criteria. For example, the approach of estimating the actual RT and upper shelf toughness of each plate, forging, or weld in the NDT beltline as a function of service life, and choosing as the surveillance materials those that are expected to be most limiting, may be preferable in some cases. 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)