Document: NUREG-0800
Document ID: 8b6b2506-1305-4f5c-9cd6-725a1d90c61c
Document Type: srp
Title: CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION THAT RESULTS IN A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350402.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.6
CFR Part: 
CFR Title: 

Content:
ant boron concentration event is acceptable and meets the requirements of General Design Criteria 10, 15 and 26. This conclusion is based on the following: 1. The applicant has met the requirements of GOC 10 with respect to demonstrating that the specified acceptable fuel design limits are not exceeded for this event. This requirement has been met since the results of the analysis showed that the thermal margin limits (KDNBR for PWRs) are satisfied as indicated by SER Section 4.4. 2. The applicant has met the requirements of GDC 15 with respect to demonstrat- ing that the reactor coolant pressure boundary limits have not been exceeded for this event. This requirement has been met since the analysis showed that the maximum pressure in the reactor coolant and main steam systems did not exceed 110% of the design pressure. 3. The applicant has met the requirements of GDC 26 with respect to demonstrating that the control rod system has the capability of overcoming the effects of boron dilution events during reactor operation. The applicant has demon- strated the fulfillment of these requirements by showing that under the postulated accident conditions, and with appropriate margins for stuck rods, the specified acceptable fuel design limits are not exceeded. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for comlying 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. 15.4.6-6 Rev. 1 - July 1981 VI. REFERENCES 1. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 2. 10 CFR Part 50, Appendix A, GDC 10, "Reactor Design." 3. 10 CFR Part 50,