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:
ctor 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 (c)(3)(i) through (iii) of this section, the NRC staff shall complete full documentation of its inspection of the licensee's annealing process and make available this documentation at the NRC Web site, http://www.nrc.gov . [ 60 FR 65472 , Dec. 19, 1995, as amended at 64 FR 48952 , Sept. 9, 1999; 64 FR 53613 , Oct. 4, 1999] Effective Date Note Effective Date Note: See 64 FR 53582 , Oct. 4, 1999, for effectiveness of § 50.66 (b) introductory text, paragraphs (b)(4), (c)(2), and (c)(3)(iii). Footnotes - 50.66 [ 6 ] For those cases where materials are removed from the beltline of the pressure vessel, the stress limits of the applicable portions of the ASME Code Section III must be satisfied, including consideration of fatigue and corrosion, regardless of the Code of record for the vessel design.