NUREG-1537, Part 2 - NRC

CHAPTER 4
* The control rod design should ensure that positioning is reproducible and
that a readout of positions is available for all reactor operating conditions.
* The drive and control systems for each control rod should be independent
from other rods to prevent a malfunction in one from affecting insertion or
withdrawal of any other.
* The drive speeds and scram times of the control rods should be consistent
with reactor kinetics requirements considering mechanical friction,
hydraulic resistance, and the electrical or magnetic system
* The control rods should allow replacement and inspection, as required by
operational requirements and the technical specifications.
* Technical specifications should be proposed according to the guidance in
Chapter 14 of the format and content guide, which describes important
design aspects and proposes limiting conditions for operations and
surveillance requirements, and should be justified in this section of the
SAR
Review Procedures
The reviewer should confirm that the design bases for the control rods define all
essential characteristics and that the applicant has addressed them completely.
Evaluation Findings
This section of the SAR should contain sufficient information to support the
following types of conclusions, which will be included in the staff's safety
evaluation report:
* The applicant has described the control and safety rod systems for the
reactor and included a discussion of the design bases, which are derived
from the planned operational characteristics of the reactor. All functional
and safety-related design bases can be achieved by the control rod designs.
* The applicant has included information on the materials, components, and
fabrication specifications of the control rod systems. These descriptions
offer reasonable assurance that the control rods conform with the design
bases and can control and shut down the reactor safely from any operating
condition
* The staff has evaluated the information on scram design for the control
rods and compared it with designs at other non-power reactors having
NUREG-1537,PART2 4-6 REV 0, 2/96
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