TABLE OF CONTENTS This Appendix gives an example of a USNRC Regulatory Guide and a chapter of the Standard Review Plan to provide useful reference technical information and data. The numbering system and cross-references of the original documents are retained. All illustrations in the original documents have been removed.
REGULATORY GUIDE 1.3
Assumptions used for evaluating the potential radiological consequences of a loss of coolant accident for boiling water reactors.
INTRODUCTION
Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The design basis loss of coolant accident (LOCA) is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to the public health and safety. This guide gives acceptable assumptions that may be used in evaluating the radiological consequences of this accident for a boiling water reactor. In some cases, unusual site characteristics, plant design features, or other factors may require different assumptions which will he considered on an individual case basis. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
DISCUSSION
[ ] within the guidelines of 10 CFR Part 100. (During the construction permit review, guideline exposures of 20 rem whole...
