Document: NUREG-0800
Document ID: 96cbc2a1-0072-44c5-ae86-aadfa416183c
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350118.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
e accidents can be controlled by limiting the permissible primary and secondary coolant system radioactivity concentrations and/or primary-to-second- ary leak rates so that potential offsite doses are small. At the operating license stage, we will include appropriate limits on these parameters to be included in the plant 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 described herein are contained in the referenced regulatory guide. 15.1.5-14 Rev. 2 - July 1981 VI. REFERENCES 1. 10 CFR Part 100, Section 11, "Determination of Exclusion Area, Low Population Zone, and Population Center Distance." 2. Standard Technical Specifications for Combustion Engineering PWRs, NUREG-0212. 3. Standard Technical Specifications for Westinghouse PWRs, NUREG-0452. 4. Standard Technical Specifications for Babcock and Wilcox PWRs, NUREG-0103. 5. R. R. Bellamy, "A Regulatory Viewpoint of Iodine Spiking During Reactor Transients," Trans. Am. Nucl. Soc., 28 (1978). 6. W. F. Pasedag, "Iodine Spiking in BWR and PWR Coolant Systems," CONF-770708, 3-217 (1977). 7. A. K. Postma and P. S. Tam, "Iodine Behavior in a PWR Cooling System Following a Postulated Steam Generator Tube Rupture Accident," NUREG-0409, USNRC, 1978. 8. Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors." 15. 1. 5-15 Rev. 2 - July 1981