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

SECTION 14
ACCEPTANCE TEST PROCEDURES (cont)
14.3.8.28.2 Inadvertent Reactor Trip-Relay Failure (19)
14.3.8.26.3 SI Train Failure-Relay (23)
14.3.8.26.4 Containment Isolation Failure (23)
14.3.8.27 Pressurizer Relief Tank
None
14.3.8.28 Reactor Coolant Pump
14.3.8.28.1 RCP Locked Rotor (4)
14.3.8.28.2 RCP Sheared Pump Shaft (4)
14.3.8.28.3 RCP Trip (Below P-8)
14.3.8.29 Reactor Coolant System with Pressurizer
14.3.8.29.1 RCS Control Rod Ejection (I b,c)
14.3.8.29.2 Steam Generator Tube Leak
14.3.8.29.3 Loop Flow Transmitter Failure (22)
14.3.8.29.4 Cold Leg RTD Failure (Narow Range) (22)
14.3.8.29.5 Pressurizer Spray Valve Failure
14.3.8.30 Residual Heat Removal
14.3.8.30.1 RHR Pump Discharge Header Leak (7)
14.3.8.31 Radiation Monitoring
14.3.8.31.1 Containment High Activity
14.3.8.31.2 Plant Vent High Activity
14.3.8.31.3 High Radioiodine Activity
14.3.8.32 Reactor Makeup Water
14.3.8.32.1 RMW Pump Discharge Line Break
14.3.8.33 Reactor Core
None
14.3.8.34 Reactor Vessel Level Indication
14.3.8.34.1 Sensing Line Leak
14.3.8.35 Spent Fuel Pool
14.3.8.35.1 Refueling Range Leak
14.3.8.36 Steam Generator Blowdown
None
14.3.8.37 Steam Generator, Main Steam Header, and Drains
14.3.8.37.1 Steam Generator Safety Valve Failure (17)
14.3.8.37.2 Atmospheric Steam Dump Valve Controller Failure (17)
14.3.8.37.3 Stuck Open Condenser Dump Valve (17)
14.3.8.38 Service Gas System
None
14.3.8.39 Safety Injection System
None
CON MASTER INDEX Rev 3(wvb) Page 55 of 61
01991 Westinghouse Electric Corp.