Document: NUREG-0800
Document ID: c75a9de4-9927-49e4-b078-7f5dadd37acd
Document Type: srp
Title: DESIGN BASIS ACCIDENT RADIOLOGICAL CONSEQUENCE ANALYSES FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.3
CFR Part: 
CFR Title: 

Content:
Utilization Facilities” 5. 10 CR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants” 6. 10 CFR Part 100, “Reactor Site Criteria” 7. Regulatory Guide RG 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition),” 2007. 8. Regulatory Guide 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,” July 2000 9. NUREG-1793, “Final Safety Evaluation Report Related to Certification of the AP1000 Standard Design,” September 2004 10. NUREG-1465, “Accident Source Terms for Light-Water Nuclear Power Plants,” February 1995 11. NRR Review Standard RS-002, “Processing Applications for Early Site Permits,” May 3, 2004 (ADAMS Accession No. ML040700094 12. SECY-98-154, “Results of the Revised (NUREG-1465) Source Term Re-Baselining for Operating Reactors,” June 1998 PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.