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:
cooling water are reviewed under SRP Section 6.3. 15.4.6-3 Revision 2 - March 2007 5. Aspects of the sequence described in the SAR are reviewed to confirm that reactor and plant protection, engineered safety features (EFS) controls, interlocks, and other instrumentation and control systems important to safety will function as assumed in the safety analyses under SRP Sections 7.2 through 7.7. 6. Functional and operational characteristics and potential failure modes of the CVCS are reviewed under SRP Section 9.3.4. This includes the functional and operational characteristics and potential failure modes of other systems identified as having the potential for an inadvertent addition of unborated water into the RCS due to operator error or system malfunction. The reviewer of this section makes use of this review to evaluate initiating causes and the expected sequence of events. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion (GDC) 10, as it relates to the reactor core and its coolant, control, and protection systems with appropriate design margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. 2. GDC 13 as to the availability of instrumentation to monitor variables and systems over their anticipated ranges to assure adequate safety, and of appropriate controls to maintain these variables and systems within prescribed operating ranges. 3. GDC 15, as it relates to the RCS and its auxiliary, control, and protection systems with sufficient design margin to assure that the design conditions of the reactor coolant pressure boundary (RCPB) are not exceeded during any condition of normal operation, including anticipated operational