Document: NUREG-0800
Document ID: 41b2cf88-b6dc-4005-939a-cf3fb1a561d2
Document Type: srp
Title: INADVERTENT DECREASE IN BORON CONCENTRATION IN THE REACTOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380222.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.6
CFR Part: 
CFR Title: 

Content:
ed parameters that were within the instruments’ prescribed operating ranges. 3. The applicant meets GDC 15 requirements by demonstrating whether the RCPB limits are not exceeded for this event. This requirement is met as the analysis show that the maximum pressure in the reactor coolant and main steam systems did not exceed 110 percent of the design pressure. 4. The applicant meets GDC 26 requirements by demonstrating that the control rod system can overcome the effects of boron dilution events during reactor operation. The applicant fulfills these requirements by showing under the postulated operational occurrence conditions, and with appropriate margins for stuck rods, that the specified acceptable fuel design limits are not exceeded. 15.4.6-10 Revision 2 - March 2007 For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, GDC 10, "Reactor Design." 2. 10 CFR Part 50, Appendix A, GDC 13, “Instrumentation and Control.” 3. 10 CFR Part 50, Appendix A, GDC 15, "Reactor Coolant System Design." 4. 10 CFR Part 50, Appendix A, GDC 26, "Reactivity Control System Redundancy and Capability." 5. American Society of Mechanical Engineers (ASME) Boiler and