Document: NUREG-0800
Document ID: 2133c57c-1767-4769-89e9-ceb528fb7c2b
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF STEAM GENERATOR TUBE FAILURE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350149.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.3
CFR Part: 
CFR Title: 

Content:
AME) specific technical specifications to assure that the dose guidelines stated above are not exceeded. The following paragraph is inserted prior to the last paragraph if fuel damage is found to be a possible consequence of the accident: The steam generator tube failure accident has also been evaluated with % fuel damage in the core as a result of the most reactive control rod remaining fully withdrawn. The resulting doses, listed in Table 15. , are within the guidelines of 10 CFR Part 100. At the construction permit stage, the following paragraph is included in the staff's safety evaluation report: On the basis of our experience with the evaluation of steam generator tube failure accidents for pressurized water reactor plants of similar design, we have concluded that the consequences of these accidents can be controlled by limiting the permissible primary and secondary coolant system radioactivity concentrations so that potential offsite doses are small. At the operating license stage the staff will include appropriate 15.6.3-5 Rev. 2 - July 1981 limits on primary and secondary coolant activity concentrations in the technical specifications. V. IMPLEMENTATION The following provides guidance to applicants and licensees regarding the staff's plans for using this .SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 100, Section 11, "Determination of Exclusion Area, Low Population Zone, and Population Center Distance." 2. Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors."