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

SECTION 10
DESIGN BASIS AND MODEL DOCUMENTATION (cont)
10.2.1.6 System Failure Data Sheets
102.1.7 Computer Inputs
10.2.1.8 System Diagrams
10.2.1.9 Software Communication and Hierarchy Diagram
10.2.1.10 Model Assumptions
10.2.1.11 Model Simplifications
10.2.1.12 Description of Equations
10.2.1.13 Derivation of Constants
10.2.1.14 Program Description
10.2.1.15 Database References
10.2.1.16 Program Listing
10.2.1.17 Datapool Source Listing
10.2.2 Excore Nuclear Instrumentation (NIS)
10.2.3 Inoore Nuclear Instrumentation (CFM)
10.2.4 Control Rod Drive (CRF)
10.2.5 Reactor Coolant System and Pressurizer (RCS)
10.2.6 Reactor Coolant Pump (RCP)
10.2.7 Reactor Vessel Level Indication (RVL)
10.2.8 Pressurizer Relief Tank (PRT)
10.2.9 Steam Generation and Main Steam Header and Drains (SGN)
10.2.10 Steam Generator Slowdown (SGB)
10.2.11 Chemical and Volume Control (CVC)
10.2.12 Residual Heat Removal (RHR)
10.2.13 Safety Injection (SIS)
10.2.14 Component Cooling Water (CCW)
10.2.15 Containment Spray (CNS)
10.2.16 Containment and Containment HVAC (CNM)
10.2.17 Waste Processing (WPS)
10.2.18 Nuclear Sampling (NSS)
10.2.19 Radiation Monitoring (RMS)
10.2.20 Spent Fuel Pool Cooling (SFP)
10.2.21 Penetration Seaing Water (PSW)
10.2.22 Digital Impact Monitor (DIM) - Refer to Section 8.4.21.1
10.3 Balance of Plant (BOP) Models
10.3.1 Fire Protection (FPS)
10.3.2 Main Turbine, Main Steam (MSS)
10.3.? Turbine Control and Auxiliaries (TCA)
10.3.4 Secondary Sampling System (SSS)
10.3.5 Condensate and Main Feedwater (CFW)
CON MASTER INDEX Rev 3(wvb) Page 18 of 61
01991 Westinghouse Electric Corp.