Document: NRC Regulatory Guide
Document ID: e16da529-b6b4-4fdf-bc3f-7490180363f3
Document Type: regulatory_guide
Title: Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2018/ML20183A423.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.89
CFR Part: 
CFR Title: 

Content:
or Babcock & Wilcox plants (4) NEDO-10320 and Supplements 1 and 2 for General Electric plants; NEDO-20533, dated June 1974, and Supplement 1, dated August 1975, for General Electric Mark III C-2. Main Steamline Break The following documents describe acceptable methods for calculating the mass and energy release to determine the main steamline break environment: (1) Topical Report WCAP-8822 (MARVEL/TRANSFLA) for Westinghouse plants, noting that the use of this method is acceptable for all Westinghouse plants with the exception that a plant-specific containment temperature analysis will be required for ice condenser containments (2) Appendix 6B to the preliminary safety analysis report for CESSAR System 80 for Combustion Engineering plants (3) Section 15.1.14 of B-SAR-205 for Babcock & Wilcox plants (4) NEDO 10320 and Supplements 1 and 2 for General Electric plants 10 Documents referenced in this Appendix are publicly available NRC published documents and are available electronically through the NRC Library on the NRC’s public Web site at http://www.nrc.gov/reading-rm/doc- collections/ and through the NRC’s Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html. The documents can also be viewed online or printed for a fee in the NRC’s Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD. For problems with ADAMS, contact the PDR staff at 301-415-4737 or (800) 397-4209; fax (301) 415-3548; or e-mail pdr.resource@nrc.gov. DG-1361, Appendix D, Page D-1 APPENDIX D QUALIFICATION IN THE RADIATION ENVIRONMENT This appendix addresses assumptions associated with equipment qualification that are acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for performing radiological assessments for large light-water reactors similar to those currently in operation. The methodology and assumptions described within may not be appropriate for other reactor designs, and the use of the methodology and