Document: 10 CFR Part 50
Document ID: e10dbff9-74fb-432e-8a44-c12a03e8ec65
Document Type: cfr
Title: Accident source term.
Source: 10 CFR Part 50
Source URL: https://www.ecfr.gov/current/title-10/part-50/section-50.67
Revision Date: 
Chapter: 
Section ID: 50.67
CFR Part: 50
CFR Title: 10

Content:
§ 50.67 Accident source term. ( a ) Applicability. The requirements of this section apply to all holders of operating licenses issued prior to January 10, 1997, and holders of renewed licenses under part 54 of this chapter whose initial operating license was issued prior to January 10, 1997, who seek to revise the current accident source term used in their design basis radiological analyses. ( b ) Requirements. ( 1 ) A licensee who seeks to revise its current accident source term in design basis radiological consequence analyses shall apply for a license amendment under § 50.90 . The application shall contain an evaluation of the consequences of applicable design basis accidents [ 1 ] previously analyzed in the safety analysis report. ( 2 ) The NRC may issue the amendment only if the applicant's analysis demonstrates with reasonable assurance that: ( i ) An individual located at any point on the boundary of the exclusion area for any 2-hour period following the onset of the postulated fission product release, would not receive a radiation dose in excess of 0.25 Sv (25 rem) [ 2 ] total effective dose equivalent (TEDE). ( ii ) An individual located at any point on the outer boundary of the low population zone, who is exposed to the radioactive cloud resulting from the postulated fission product release (during the entire period of its passage), would not receive a radiation dose in excess of 0.25 Sv (25 rem) total effective dose equivalent (TEDE). ( iii ) Adequate radiation protection is provided to permit access to and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 0.05 Sv (5 rem) total effective dose equivalent (TEDE) for the duration of the accident. [ 64 FR 72001 , Dec. 23, 1999] Footnotes - 50.67 [ 1 ] The fission product release assumed for these calculations should be based upon a major accident, hypothesized for purposes of design analyses or postulated from considerations of possible