Document: NUREG-0800
Document ID: feb81401-32fe-404e-84da-ff4b36e788bf
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURE OUTSIDE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350151.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.4
CFR Part: 
CFR Title: 

Content:
- July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications 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 Commissions 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. 1. For a MSLB with an assumed preaccident iodine spike corresponding to the maximum iodine concentration stated in the NSSS vendor standard technical specifications, the calculated doses should not exceed the guideline values of 10 CFR Part 100, paragraph 11 (Ref. 1). 2. For a MSLB with an assumed iodine concentration corresponding to the equilibrium value for continued full power operation stated in the NSSS vendor standard technical specifications, the doses should not exceed a small fraction of the above guideline values, i.e., 10 percent or 2.5 rem and 30 rem respectively, for the whole body and thyroid doses. 3. The methodology and assumptions for calculating the radiological conse- quences should reflect the regulatory positions of Regulatory Guide 1.5 (Ref. 2) except for the atmospheric dispersion factors which are reviewed under SRP Section 2.3.4. 4. A plant specific technical specification is