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"Consolidated Edison Co Indian Point 2 Nuclear Plant ... - NRC

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I. Major Check Valve Handler<br />

" Assumptions and Simplifications<br />

" Mathematical Derivation<br />

J. Safety and Relief Valve Handier<br />

" Assumptions and Simplifications<br />

" Mathematical Derivation<br />

K. Relay Handler<br />

L. Alarm Handler<br />

* Assumptions and Simplifications<br />

. Mathematical Derivation<br />

3. Handler Initialization Programs<br />

V. MODELING TECHNIQUES<br />

1. Energy Source Systems Models<br />

A. Reactor <strong>Co</strong>re Model - Fundamental Techniques<br />

" Introduction<br />

" Equation Derivation<br />

- Xenon, Iodine Model<br />

- Samarium Model<br />

- Excore Detector Readings<br />

- Incore Detector Readings<br />

- Incore Thermocouples<br />

- Hot Leg Resistance Temperature Detectors (RTDs)<br />

- <strong>Co</strong>re Thermohydraulics Model<br />

- Reactor <strong>Co</strong>re Fuel Failure Model<br />

B. Reactor <strong>Co</strong>re Model (RTC) - Implementation<br />

. Program Description<br />

. Simplifications<br />

. Description of Equations<br />

- <strong>Co</strong>re Thermohydraulic Module (RTCTAH)<br />

- Fuel Failure Model<br />

- Plenum Mixing Model<br />

- Neutron Kinetics Module (RFLUX2)<br />

- Decay Heat and Fission Products (RAUXIL)<br />

. Appendix A.V.1.B<br />

C. Reactor <strong>Co</strong>re Model (CFM)-Implementation<br />

• Program Description<br />

" Simplifications<br />

CON MASTER INDEX Rev 3(wvb) Page 40 of 61<br />

01991 Westinghouse Electric <strong>Co</strong>rp.

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