Document: NUREG-0800
Document ID: 58e96831-02fa-4fe0-9367-ac30b1da435a
Document Type: srp
Title: CONTROL ROD MISOPERATION (SYSTEM MALFUNCTION OR OPERATOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600415.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.3
CFR Part: 
CFR Title: 

Content:
for any time in cycle are initial power level and distribution, initial rod 15.4.3-6 Revision 3 - March 2007 configuration, reactivity addition rate, moderator temperature, fuel temperature, and void reactivity coefficients. 2. For each event, the analytical methods used by the applicant are reviewed. Those steady-state and AOO methods that are primarily based on reactor physics considerations are the responsibility of the organization responsible for reactor systems. Where thermal-hydraulic methods are involved, review assistance may be requested as described in SRP Section 4.4. In either case, the reviewer should determine whether the applicant's evaluation methods are acceptable. This may be done by using one or more of the following procedures: A. Determine whether the method has been reviewed and approved previously by considering past safety evaluation reports (SERs) and reports prepared in response to specific technical assistance requests. B. Perform an independent review of the method (usually described in a separate licensing topical report and often completed, on a generic basis, outside the scope of the review for a particular facility). C. Perform auditing-type calculations with methods available to the staff. D. Request additional bounding calculations from the applicant to confirm the validity of those portions of the applicant's analytical method that have not already been fully reviewed and approved. 3. For each event, the results are evaluated. In addition to verifying conformance to the acceptance criteria of subsection II above, the reviewer determines that: A. Input conditions (e.g., pressure, temperature, flow rate) are at the adverse end of the range of values specified as the operating range. B. Initial power is 102% of licensed core thermal power, unless a lower power level is justified by the applicant. C. Output signals (power, temperature, flux perturbation) provide adequate alarm or scram signals. D. Nuclear conditions that interact