NUREG-1537, Part 2 - NRC

Accepktace Criteria
HEU To LEU CONVEON
Acceptance criteria for the information on I&C systems should be based on the
following considerations: Changes in the I&C systems or operational
characteristics of these systems should not significantly decrease functional
capabilities, including speeds of response, independence of redundant and diverse
systems, or shutdown capability for the LEU-fueled reactor, as compared with
those of the licensed HEU-fueled reactor. Continued use of existing I&C systems
should be acceptable if reactor operating characteristic changes that result from
fuel conversion do not decrease the information provided or the reliability of the
systems. Specific factors that should be compared are discussed in ANSI/ANS
15.15-1978 and ANSI/ANS 15.20 (draft). The licensee should propose only
changes that are required for the conversion, but that do not decrease information,
control of reactor performance, or safe shutdown capability.
Review Procedures
The reviewer should systematically evaluate all proposed modifications to I&C
systems or changes to operation of existing systems to confirm that sensors and
channels are acceptably responsive to all LEU-fueled reactor characteristics. The
design bases and methods of calibration for any changed I&C systems should be
reviewed. The reviewer should consider all factors of I&C systems discussed in-
ANSI/ANS 15.15 and 15.20.
Evaluation Findings
This section of the SAR should contain sufficient information to support the
following types of conclusions, which will be included in the staffs safety
evaluation report:.
* The operating characteristics of the proposed LEU-fueled reactor that
woeld be significantly different from those of the existing HEU-fueled
reactor and the responses of the I&C components and systems that provide
information or control parameters have been analyzed and compared with
the comparable parameters of the iEU-fueled reactor. The power level of
the two reactors, the maximum fuel plate (rod) temperatures, and the
neutron flux per unit power at the nuclear instruments are within the
operational range of existing' senisors and channels. Any differences should
be acceptably addressed by recalibration as part of the LEU-fueled reactor
startup program in Section 12, and in subsequent routine surveillance
activities.
* The response of the I&C systems to the full range of operation and
postulated accidents has been addressed by the licensee, and will cause no
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