Document: NUREG-0800
Document ID: fabdf65c-d299-4b3a-a971-ae5b21a97177
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A413.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
with and supports the portion of the application review performed in SRP Subsection 3.11. 3. Added a statement describing requirements in 10 CFR 52.47(a)(22) regarding the use of operating experience. 4. Added a statement describing requirements in 10 CFR 20.1406 regarding minimization of contamination of the facility, the environment, waste generation and facilitation of decommissioning. 5. Removed references to RG 1.3 and RG 1.4, because the guidance contained in these documents is not relevant to review of license applications submitted after 1997. 6. Added a statement regarding the use of the guidance contained in RG 1.89 as it relates to identifying types and sources of radiation in accordance with 10 CFR 50.49(e)(4). 7. Added a statement regarding use of source term information for determining the dose to equipment, consistent with the requirements of 10 CFR 50.49(e)(4). 8. Consistent with the guidance contained in RG 1.206 Subsection C.I.12.2, added clarification to description of the quantity of radiation sources to be identified in the application, to those sources requiring shielding considerations. 9. Added a statement regarding the need to identify sources of neutron and gamma radiation resulting from irradiated material that could result ORE or equipment dose inside containment. 10. Added a statement regarding the need to identify radiation sources that could be expected to result from operation with allowable primary-to-secondary leakage. 11. Added statements regarding the applicability of 10 CFR 50.34(b)(3), 10 CFR 52.47(a)(5), 10 CFR 52.79(a)(3) and 10 CFR 52.157(e) as they relate to identifying the kinds and quantities of radioactive materials expected to be produced in the operation and the means for controlling and limiting radiation exposures within the limits set forth in part 20 of this chapter. III. REVIEW PROCEDURES 1. Added a discussion regarding the use of the types of documents discussed in the EPRI URD and the associated Safety Evaluation