Document: NRC Regulatory Guide
Document ID: 4d46a966-d280-43da-9b03-8b0abe7b29ce
Document Type: regulatory_guide
Title: Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2120/ML21204A065.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.183
CFR Part: 
CFR Title: 

Content:
ly reference GDC 19 in Appendix A to 10 CFR Part 50 or specify criteria derived from GDC 19. These criteria are generally specified in terms of whole body dose or its equivalent to any body organ. For facilities applying for, or having received, approval to use an AST, licensees should update the applicable criteria for consistency with the TEDE criterion in 10 CFR 50.67(b)(2)(iii). For new reactor applicants, the technical support center (TSC) habitability acceptance criterion is based on the requirement of paragraph IV.E.8 of Appendix E to 10 CFR Part 50 to provide an onsite TSC from which effective direction can be given and effective control can be exercised during an emergency. The radiation protection design of the TSC is acceptable if the total calculated radiological consequences for the postulated fission product release fall within the exposure acceptance criteria specified for the control room (5 rem TEDE for the duration of the accident). DG-1389, Page 28 Table 7.17 Accident Dose Criteria for EAB, LPZ, and Control Room Locations Accident or Case EAB and LPZ Dose Criteria (TEDE) Control Room Dose Criteria18 (TEDE) Analysis Release Duration MHA LOCA 0.25 sievert (Sv) (25 rem) 0.05 Sv (5.0 rem) 30 days for containment, ECCS, and MSIV (BWR) leakage BWR Main Steamline Break Instantaneous puff Fuel Damage or Preincident Spike 0.25 Sv (25 rem) 0.05 Sv (5.0 rem) Equilibrium Iodine Activity 0.025 Sv (2.5 rem) 0.05 Sv (5.0 rem) BWR Rod Drop Accident 0.063 Sv (6.3 rem) 0.05 Sv (5.0 rem) 24 hours PWR Steam Generator Tube Rupture Affected steam generator: time to isolate19 Unaffected steam generator(s): until cold shutdown is established Fuel Damage or Preincident Spike 0.25 Sv (25 rem) 0.05 Sv (5.0 rem) Coincident Iodine Spike 0.025 Sv (2.5 rem) 0.05 Sv (5.0 rem) PWR Main Steamline Break Until cold shutdown is established Fuel Damage or Preaccident Spike 0.25 Sv (25 rem) 0.05 Sv (5.0 rem) Coincident Iodine Spike 0.025 Sv (2.5 rem) 0.05 Sv (5.0 rem) PWR Locked Rotor