Document: 10 CFR Part 50
Document ID: f3d5df11-b35b-4e81-b016-39463863b59a
Document Type: cfr
Title: Requirements for thermal annealing of the reactor pressure vessel.
Source: 10 CFR Part 50
Source URL: https://www.ecfr.gov/current/title-10/part-50/section-50.66
Revision Date: 
Chapter: 
Section ID: 50.66
CFR Part: 50
CFR Title: 10

Content:
the same time and temperature conditions as those given the beltline material. ( 2 ) Alternatively, the percent recovery due to thermal annealing (R t and R u ) may be determined from the results of a verification test program employing materials removed from the beltline region of the reactor vessel [ 6 ] and that have been annealed under the same time and temperature conditions as those given the beltline material. ( 3 ) Generic computational methods may be used to determine recovery if adequate justification is provided. ( f ) Public information and participation. ( 1 ) Upon receipt of a Thermal Annealing Report, and a minimum of 30 days before the licensee starts thermal annealing, the Commission shall: ( i ) Notify and solicit comments from local and State governments in the vicinity of the site where the thermal annealing will take place and any Indian Nation or other indigenous people that have treaty or statutory rights that could be affected by the thermal annealing, ( ii ) Publish a notice of a public meeting in the Federal Register and in a forum, such as local newspapers, which is readily accessible to individuals in the vicinity of the site, to solicit comments from the public, and ( iii ) Hold a public meeting on the licensee's Thermal Annealing Report. ( 2 ) Within 15 days after the NRC's receipt of the licensee submissions required by paragraphs (c)(1) , (c)(2) and (c)(3)(i) through (iii) of this section, the NRC staff shall make available at the NRC Web site, http://www.nrc.gov , a summary of its inspection of the licensee's thermal annealing, and the Commission shall hold a public meeting: ( i ) For the licensee to explain to NRC and the public the results of the reactor pressure vessel annealing, ( ii ) for the NRC to discuss its inspection of the reactor vessel annealing, and ( iii ) for the NRC to receive public comments on the annealing. ( 3 ) Within 45 days of NRC's receipt of the licensee submissions required by paragraphs (c)(1) , (c)(2) and