Document: NUREG-0800
Document ID: bf62536e-58c7-4cb0-a51f-5c5ce2c21d6b
Document Type: srp
Title: DRAFT Rev. 2 - April
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070423.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2.9
CFR Part: 
CFR Title: 

Content:
peak neutron fluence (E > 1 Mev) at the end of the design life of the vessel will not exceed 1017 n/cm . 2 b. Reactor vessels constructed of ferritic materials which do not meet these conditions shall have their beltline regions monitored by a surveillance program complying with the American Society for Testing and Materials (ASTM) standard "Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels," ASTM Designation E-185 (Reference 27) , except as modified by 63 Appendix H to 10 CFR Part 50. c. The surveillance program shall meet the following requirements: (1) Surveillance specimens shall be taken from locations alongside the fracture toughness test specimens required by Section III of Appendix G of 10 CFR Part 50. The specimen types shall comply with the requirements of Section III.A of Appendix G, except that dropweight specimens are not required. (2) Surveillance capsules containing the surveillance specimens shall be located near the inside vessel wall in the beltline region, so that the neutron flux received by the specimens approximates that received by the vessel inner surface, and the thermal environment is as close as practical to that of the vessel inner surface. If the capsule holders are attached to the vessel wall or cladding, inspection shall be done according to the requirements for permanent structural attachments as given in ASME Code Sections III and XI. The design and location of the capsules shall permit insertion of replacement capsules. Accelerated irradiation capsules DRAFT Rev. 2 - April 1996 5.3.1-10 may be used in addition to the required number of surveillance capsules specified in paragraph II.CB.32 of Appendix H. 64 (3) The required number of capsules, which will vary from three to five depending upon the adjusted reference temperature at the end of the service lifetime of the reactor vessel, and their withdrawal schedules, shall be in accordance with the requirements of paragraph II.CB.3 of 65 Appendix H. (4) For