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