Document: NUREG-0800
Document ID: b8e8a93f-5bc3-4f5b-9d72-fdf90a3c2e45
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF CONTROL ROD DROP ACCIDENT (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350427.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
s to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them Is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation; Washington. D.C. 205. defined as 25% of the 10 CFR Part 100 exposure guideline values or 75 rem for the thyroid and 6 rem for whole-body doses. The fission product source term used in the dose analysis is acceptable if it meets the guidelines of Regulatory Guide 1.77 (Ref. 2). III. REVIEW PROCEDURES The reviewer selects and emphasizes specific aspects of this appendix to Standard Review Plan Section 15.4.9 as appropriate for the particular plant. The judgment of which areas need to be given attention and emphasis is based on the similarity of the information presented in the SAR or other licensing submittals. Based on past reviews by the staff, a control rod drop accident is expected to result in radiological consequences less than 10% of the Part 100 guideline values even with conservative assumptions. The reviewer should examine the site meteorology, plant features, and fuel damage as a result of the accident for the plant in question and compare these with the corresponding features and resulting doses for previously reviewed plants to ascertain whether a specific calculation of the radiological