Document: NUREG-0800
Document ID: 18897384-49d0-41ca-b285-0b1201052b03
Document Type: srp
Title: CONTROL ROD MISOPERATION (SYSTEM MALFUNCTION OR OPERATOR ERROR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350372.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.3
CFR Part: 
CFR Title: 

Content:
el and distribution, initial rod 15.4.3-2 Rev. 2 - July 1981 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 transient methods that are primarily based on reactor physics considerations are the responsibility of CPB. Where thermal-hydraulic methods are involved, review assistance may be requested as described in SRP Section 4.4. In either case, the reviewer must.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 pre- pared in response to specific technical assistance requests. b. Perform a de novo review of the method (usually described in a separate licensing topical report, and often handled outside the scope of the review for a particular facility). c. Perform auditing-type calculations with methods available to the staff. d. Require additional bounding calculations by 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) provided adequate alarm or scram signals. d. Nuclear conditions that interact with this event (e.g., Doppler coefficient, void coefficient) have been calculated as described in SRP Section 4.3.