"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
You also want an ePaper? Increase the reach of your titles
YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.
SECTION 14<br />
ACCEPTANCE TEST PROCEDURES (cont)<br />
14.3.8.40 Switchyard<br />
14.3.8.40.1 138 KV Une Fault (3)<br />
14.3.8.41 Service Water System<br />
14.3.8.41.1 Service Water to CCW Leak (7,6)<br />
14.3.8.42 Synchronizer<br />
None<br />
14.3.8.43 Turbine Supervisory Instrumentation<br />
None<br />
14.3.8.44 Waste Processing System<br />
None<br />
14.3.9 Malfunction Scenario Tests<br />
14.3.9.1 Loss of All AC Power<br />
14.3.9.2 Loss of All Feedwater<br />
14.3.9.3 Natural Circulation <strong>Co</strong>oldown with Steam Void in Vessel (RVLIS<br />
available)<br />
14.3.9.4 SGTR with Loss of Reactor <strong>Co</strong>olant - Saturated Recovery Desired<br />
14.3.9.5 Inadvertent Turbine Trip (Maximum power level that does not cause an<br />
Immediate reactor trip)<br />
14.3.9.6 RCS Rupture<br />
14.3.9.7 Main Steamline Break Inside <strong>Co</strong>ntainment<br />
14.3.9.8 Main Steamline Break Outside <strong>Co</strong>ntainment<br />
14.3.9.9 Simultaneous Trip of Both Main Feedpumps<br />
14.3.9.10 Simultaneous Closure of All Main Steam Isolation Valves<br />
14.3.9.11 Simultaneous Trip of Ali Reactor <strong>Co</strong>olant Pumps<br />
14.3.9.12 Maximum Rate Power Ramp 100% to 75% to 100%<br />
14.3.9.13 LOCA with Blackout<br />
14.3.9.14 Pressurizer PORV Stuck Open Without High Head SI<br />
14.3.9.15 Turbine Trip<br />
14.3.9.16 Loss of Instrument Air<br />
14.3.9.17 Main Generator Trip<br />
14.3.9.18 Main Feedline Break Inside <strong>Co</strong>ntainment<br />
14.3.9.19 Main Feedline Break Outside <strong>Co</strong>ntainment<br />
14.3.9.20 Fuel Clad Failure<br />
14.3.9.21 Loss of <strong>Co</strong>ndenser Vacuum<br />
14.3.9.22 Loss of Shutdown <strong>Co</strong>oling (All RHR Pumps Trip)<br />
14.3.9.23 Manual Reactor Trip<br />
14.3.9.24 RCP Trip at 100% Power<br />
14.3.9.25 Reactor Fails to Trip (ATWS)<br />
14.3.9.26 Loss of Service Water (ALL SWS Pumps Trip)<br />
CON MASTER INDEX Rev 3(wvb) Page 56 of 61<br />
01991 Westinghouse Electfic <strong>Co</strong>rp.