ML20078G679
| ML20078G679 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/30/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078G682 | List: |
| References | |
| NPF-68-A-083, NPF-81-A-061 NUDOCS 9502030212 | |
| Download: ML20078G679 (2) | |
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION f1GE 3/4.6 CONTAIMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....................................
3/4 6-1 Containment Leakage......................................
3/4 6-2 Containment Air Locks....................................
3/4 6-4 Internal Pressure........................................
3/4 6-6 Air Temperature..........................................
3/4 6-7 Containment Structural Integrity.........................
3/4 6-8 Containment Ventilation System...........................
3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.................................
3/4 6-13 Containment Cooling System...............................
3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................
3/4 6-16 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors........................................
3/4 6-18 Electric Hydrogen Recombiners............................
3/4 6-19 V0GTLE UNI ~G - 1 & 2 IX 9502030212 950130 PDR ADOCK 05000424 P
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS SECTION EME 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves............................................
3/4 7-1 TABLE 3.71 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES........
3/4 7-2 TABLE 3.72 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 Auxiliary feedwater System...............................
3/4 7-4 Condensate Storage Tank..................................
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.71 SECONDARY COOLANT SYSTEM SPECIF E ACTIVITY SAMPLE i
AND ANALYSIS PR0 GRAM.....................................
3/4 7-8 Main Steam Line Isolation Valves.........................
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 NUCLEAR SERVICE COOLING WATER (NSCW) SYSTEM..............
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK.................................
3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (Common System).
3/4 7-14 3/4,7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM....
3/4 7-17 3/4.7.8 SNUBBERS................................................
3/4 7-19 FIGURE 4.71 SAMPLE PLAN 2 FOR SNUBBER FUNCTIONAL TEST...............
3/4 7-24 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL.....................
3/4 7-24a 3/4.7.9 SEALED SOURCE CONTAMINATION..............................
3/4 7-25 3/4.7.10 AREA TEMPERATURE MONITORING..(DELETED)...................
3/4 7-27 TABLE 3.7-3 AREA TEMPERATURE MONITORING..(DELETED).................
3/4 7-28 3/4.7.11 ENGINEERED SAFETY FEATURES (ESF) ROOM COOLER AND SAFETY-RELATED CHILLER SYSTEM...................................
3/4 7-29 3/4.7.12 REACTOR COOLANT PUMP THERMAL BARRIER COOLING WATER IS0LATION................................................
3/4 7-30 3/4.7.13 DIESEL GENERATOR BUILDING AND AUXILIARY FEEDWATER PUMPHOUSE ESF HVAC SYSTEMS..............................
3/4 7-31 V0GTLE UNITS - 1 & 2 X
Amendment No.83 (Unit 1)
Amendment No. 61 (Unit 2)