Panel discussion: Challenges and improvements in accident dose analysis; Regulatory and industry perspective

Conference · 01 July 2022

OSTI ID:23203950

Blumberg, M. ^[1]; Massari, J.; Burns, C. ^[2]; Gardner, S. ^[3]

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1. US Nuclear Regulatory Commission, Washington, DC 20555-0001 (United States)
2. Constellation, 200 Exelon Way, Kennett Square, PA 19348 (United States)
3. GE Hitachi Nuclear Energy, 3901 Castle Hayne RD, Wilmington NC, 28402 (United States)

Full text of publication follows. Design basis accident (DBA) analyses are one of several ways nuclear power plant licensees demonstrate, and the U.S. Nuclear Regulatory Commission (NRC) staff verifies, that the design and location of a nuclear power plant are appropriate and that the protection of health and safety of the public is maintained. In July 2000, the NRC staff issued Regulatory Guide 1.183, 'Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors' (RG 1.183) [1]. RG 1.183 provides a method acceptable to the NRC staff for complying with the regulatory requirements contained in Title 10 of the Code of Federal Regulation (10 CFR) Section 50.67 (50.67), 'Accident source term' [2]. RG 1.183 also provides assumptions and parameters used to model postulated DBA radiological analyses for light-water reactors (LWR). Since the initial issuance of RG 1.183, the NRC staff and the nuclear power plant licensees have both gained substantial experience with the implementation of 10 CFR 50.67 and RG 1.183. Based on this experience, comments from licensees, the anticipation of licensing advanced LWRs, and new research, the NRC is developing a proposed revision to RG 1.183. This panel discussion will provide a discussion of that proposed revision, its potential impact on existing and future evaluations, and the industry perspective on the revised guidance. References: 1) USNRC, Regulatory Guide 1.183, 'Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,' Revision 0, U.S. Nuclear Regulatory Commission, Washington, D.C. (2000), Electronic copies are also available in ADAMS (http://www.nrc.gov/reading-rm/adams.html), under Accession No. ML003716792. 2) U.S. Code of Federal Regulations, Title 10 (Energy), Part 50 (Domestic Licensing of Production and Utilization Facilities), Section 67, (Accident source term), Office of the Federal Register, Washington, DC (1999). (authors)

• Research Organization: American Nuclear Society - ANS, La Grange Park, IL 60526 (United States)
• OSTI ID: 23203950
• Resource Type: Conference paper/presentation
• Conference Information: PHYSOR 2022: International conference on physics of reactors, Pittsburg (United States), 15-20 May 2022; In: Proceedings of the international conference on physics of reactors - PHYSOR 2022| 3701 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
DESIGN-BASIS ACCIDENTS
LICENSING REGULATIONS
RADIATION DOSES
SOURCE TERMS