ML17226A135
Text
TURBINE STOP VALVES TURBINE BYPASS CONTAINMENTflOW RESTRICTORS DRYWElL BREAK (DERI REACTOR PRESSURE VESSEL FIGURE 6.2-1 MAIN STEAM LINE BREAK SCHEMA TIC RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT TURBINE STOP VALVES TURBINE BYPASS CONTAINMENTflOW RESTRICTORS DRYWElL BREAK (DERI REACTOR PRESSURE VESSEL FIGURE 6.2-1 MAIN STEAM LINE BREAK SCHEMA TIC RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTMAIN STEAM LINE BREAK FLOW AREA Figure 6.2-2 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTRECIRCULATION LINE BREAK SCHEMATICS Figure 6.2-3REVISION 14SEPTEMBER 20010.0710.354=2.198 REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTCONTAINMENT PRESSURERESPONSE FOR MAIN STEAMLINE BREAK Figure 6.2-4 NOTES: 1) SHORTTERMRESPONSEISBASEDONINITIALHIGHSUPPRESSIONPOOLLEVELANDZEROFEEDWATERADDITION
- 2) LONGTERMRESPONSEISBASEDONINITIALLOWSUPPRESSIONPOOLLEVELANDADDITIONOFALLHOTFEEDWATER
- 3) LONGTERMWETWELLRESPONSEFOLLOWSTHAT OFTHECONTAINMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT PRESSURE RESPONSE FOR RECIRCULATION LINE BREAK FIGURE 6.2-5REVISION 14SEPTEMBER 2001Pressure (psia)NOTES: 1) SHORTTERMRESPONSEISBASEDONINITIALHIGHSUPPRESSIONPOOLLEVELANDZEROFEEDWATER ADDITION 2) LONGTERMRESPONSEISBASEDONINITIALLOWSUPPRESSIONPOOLLEVELANDADDITIONOFALLHOTFEEDWATER
- 3) LONGTERMWETWELLRESPONSEFOLLOWSTHATOFTHECONTAINMENT REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTCONTAINMENT TEMPERATURERESPONSE FOR MAIN STEAMLINE BREAK Figure 6.2-6 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT TEMPERATURE RESPONSE FOR RECIRCULATION LINE BREAK FIGURE 6.2-7REVISION 14SEPTEMBER 2001 NOTES: 1) SHORTTERMRESPONSEISBASEDONINITIALHIGHSUPPRESSIONPOOLLEVELANDZEROFEEDWATERADDITION
- 2) LONGTERMRESPONSEISBASEDONINITIALLOWSUPPRESSIONPOOLLEVELANDADDITIONOFALLHOTFEEDWATER REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTVENT FLOW RATE FOR MAIN STEAMLINE BREAK Figure 6.2-8(M3CPT 0-30 SEC)
REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTBLOWDOWN MASS FLOW RATEFOR MAIN STEAM LINE BREAK Figure 6.2-9Time after LOCA (sec)BLOWDOWN MASS FLOWRATE (LBM/SEC)(M3CPT 0-30 SEC)
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT BLOWDOWN COMPARISON BETWEENRBS & CPS MAIN STEAM LINE BREAK MASS FLOW RATE VS TIMEFIGURE 6.2-9aREVISION 14SEPTEMBER 2001SHEX 0-1800 SECONDS REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTBLOWDOWN COMPARISION BETWEENRBS & CPS MAIN STEAM LINE BREAKENERGY FLOW RATE VS TIME Figure 6.2-9bTime after LOCA (sec)BLOWDOWN MASS FLOWRATE (LBM/SEC)SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTBLOWDOWN MASS FLOW RATE FORRECIRCULATION SUCTION LINE BREAK Figure 6.2-10REVISION 14SEPTEMBER 2001(M3CPT 0-30 seconds)
REVISION 14SEPTEMBER 2001RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORTBLOWDOWN COMPARISION BETWEENRBS & CPS MAIN STEAM LINE BREAKMASS FLOW RATE VS TIMEFigure 6.2-10aTime after LOCA (sec)BLOWDOWN MASS FLOWRATE (LBM/SEC)SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT BLOWDOWN COMPARISON BETWEEN RBS & CPS RECIRCULATION LINE BREAKENERGY FLOW RATE VS TIMEFIGURE 6.2-10bREVISION 14SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED REVISION 17 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT NORMALIZED CORE POWER FOR SHORT-TERM MAIN STEAM LINE BREAK FIGURE 6.2-11Multiply Y-Axis by 816.3 to Obtain Core Power in Btu/hr for 100.3%Rated Power REVISION 17 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT NORMALIZED CORE POWER FOR LONG-TERM MAIN STEAM LINE BREAK FIGURE 6.2-11a (SHEX Long-Term) Multiply Y-Axis by 816.3 to Obtain Core Power in Btu/hr for 100.3%
Rated Power
.
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT FISSION POWER COASTDOWN ENERGYFOR MAIN STEAM LINE BREAKFIGURE 6.2-12REVISION 14SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTMAIN STEAM BREAKINTEGRATED CORE ANDVESSEL METAL ENERGYFIGURE 6.2-13(SHEX Long-Term)
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT METAL WATER REACTION HEATFOR MAIN STEAM LINE BREAKFIGURE 6.2-14REVISION 14SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTECCS AND RHR PUMP HEATFOR MAIN STEAM LINE BREAK Figure 6.2-15Time after LOCA (sec)PUMP HEAT (BTU/SEC)
REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTSUPPRESSION POOL WATERLEVEL MAIN STEAM LINE BREAK Figure 6.2-16M3CPT (0-30 sec)
WATER LEVEL (FT.)Time after LOCA (sec)
REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTSUPPRESSION POOL WATER LEVELMAIN STEAM LINE BREAKFIGURE 6.2-16aSHEX (0-1800 sec)
REVISION 14SEPTEMBER 2001RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTSUPPRESSION POOL WATER LEVELMAIN STEAM LINE BREAKFIGURE 6.2-16bSHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SUPPRESSION POOL WATER LEVELRECIRCULATION LINE BREAKFIGURE 6.2-17REVISION 14SEPTEMBER 2001M3CPT (0-30 sec)
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SUPPRESSION POOL WATER LEVELRECIRCULATION LINE BREAKFIGURE 6.2-17aREVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTRHR HEAT EXCHANGER DUTYFOR MAIN STEAM LINE BREAKFIGURE 6.2-18REVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTRHR HEAT EXCHANGER DUTYFOR RECIRCULATION SUCTION LINE BREAKFIGURE 6.2-19REVISION 14SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT UNIT COOLER DUTYFOR MAIN STEAM LINE BREAKFIGURE 6.2-20REVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT UNIT COOLER DUTYFOR RECIRCULATION SUCTION LINE BREAKFIGURE 6.2-21REVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTPASSIVE DRYWELL HEAT SINK HEAT REMOVAL RATEFOR MAIN STEAM LINE BREAKFIGURE 6.2-22REVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTPASSIVE CONTAINMENT HEAT SINK HEAT REMOVAL RATEFOR MAIN STEAM LINE BREAKFIGURE 6.2-22aREVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTPASSIVE DRYWELL HEAT SINK HEAT REMOVAL RATE FOR RECIRCULATION LINE BREAKFIGURE 6.2-23REVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTPASSIVE CONTAINMENT HEAT SINK HEAT REMOVAL RATE FOR RECIRCULATION LINE BREAKFIGURE 6.2-23aREVISION 14SEPTEMBER 2001SHEX Long-term RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTPASSIVE SINK SURFACE HEATTRANSFER COEFICEIENT FOR MAIN STEAM LINE BREAKFIGURE 6.2-24REVISION 14SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTPASSIVE SINK SURFACE HEATTRANSFER COEFICEIENT FORRECIRCULATION LINE BREAKFIGURE 6.2-25REVISION 14SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED MOV F039 FLOW RESTRICTOR MOV F054 RHR LINE REGENERATIVE HEAT EXCHANGERS (THRH)MOV FOOl I I!--DRYWELL 3"1,1 NON-REGENERATIVE HEAT EXCHANGERS (TWOI FIGURE 6.2-26 3" Ii L R.WCU PUMPS RWCU LINE BREAK SCHEMATIC RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22 MOV F039 FLOW RESTRICTOR MOV F054 RHR LINE REGENERATIVE HEAT EXCHANGERS (THRH)MOV FOOl I I!--DRYWELL 3"1,1 NON-REGENERATIVE HEAT EXCHANGERS (TWOI FIGURE 6.2-26 3" Ii L R.WCU PUMPS RWCU LINE BREAK SCHEMATIC RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT ALLOWABLE SUPPRESSION POOL STEAM BYPASS LEAKAGE CAPACITY(LICENSED POWER 2894 MWt)FIGURE 6.2-27REVISION 14SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTDRYWELL AND CONTAINMENT PRESSURESFOR A BREAK AREA OF 0.1 FT 2 WITH BYPASS LEAKAGE (A/ )OF 1.15 FT 2(LICENSED POWER 2894 MWt)
FIGURE 6.2-27aREVISION 14SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTDRYWELLANDCONTAINMENTPRESSURESFOR A BREAK AREA OF 0.1 FT 2 WITHBYPASS LEAKAGE (A/) 0.81 FT 2(LICENSEDPOWER 30 91 MWt)*FIGURE 6.2-27b REVISION 21
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80%NOMINAL VENT AREA FIGURE 6.2-28 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO VENT AREA RIVER BEND STATION UPDATEDSAFETYANALYSIS REPORT...lI C 1.5r------..,...------,----------r--------,...z 3 1.0...lI=-0.5
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80%NOMINAL VENT AREA FIGURE 6.2-28 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO VENT AREA RIVER BEND STATION UPDATEDSAFETYANALYSIS REPORT
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...---"""---....----'85&AI C)Z c(::J: V%NOMINAL VENT SUBMERGENCE FIGURE 6.2-29 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO VENT SUBMERGENCE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 14...._--'---_....__......._-_....__.......-_......0.80.9 1.0 1.1 1.2 1.3 1.4 TIME AFTER LOCA (SEC)=-20.-------..-----.,----..----..------.------,-loll19loll18....c(17 Z lollloll16 o........loll 15 1-----+----+-----+----+----_+_--___1o FIGURE 6.2-30 SENSITIVITY OF DRYWELL DIFFERENTIAL PRESSURE TO AIR CARRYOVER RATE TO CONTAINMENT RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT 14...._--'---_....__......._-_....__.......-_......0.80.9 1.0 1.1 1.2 1.3 1.4 TIME AFTER LOCA (SEC)=-20.-------..-----.,----..----..------.------,-loll19loll18....c(17 Z lollloll16 o........loll 15 1-----+----+-----+----+----_+_--___1o FIGURE 6.2-30 SENSITIVITY OF DRYWELL DIFFERENTIAL PRESSURE TO AIR CARRYOVER RATE TO CONTAINMENT RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT 95100105 110%NOMINAL REACTOR BLOWDOWN o-0.4 1.2 wUoI 0.8A.""" 0(I-Z UoI0.4 u.u."""""" UoI>-0.0o0(UoI A.UoI o z 0(::J: u-0.8.._11II6_90 FIGURE 6.2-31 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO REACTOR BLOWDOWN FOR A RECIRCULATION LINE BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 95100105 110%NOMINAL REACTOR BLOWDOWN o-0.4 1.2 wUoI 0.8A.""" 0(I-Z UoI0.4 u.u."""""" UoI>-0.0o0(UoI A.UoI o z 0(::J: u-0.8.._11II6_90 FIGURE 6.2-31 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO REACTOR BLOWDOWN FOR A RECIRCULATION LINE BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
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.....-.......90 95 100 105 110 115 120 INITIAL SUPPRESSION POOL TEMPERATURE (OF)FIGURE 6.2-33 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO INITIAL SUPPRESSION POOL TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 0.60.4
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.....-.......90 95 100 105 110 115 120 INITIAL SUPPRESSION POOL TEMPERATURE (OF)FIGURE 6.2-33 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO INITIAL SUPPRESSION POOL TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 0.6...-------,----r-----,-------,-------,--------, 108 106 104 102 100 98....Z;0.4 Z--" z:=0.20.0
+----+---------l o-0.2 I Z I-0.4I-0.6 10-__...........__.......__.-.1....1..__.-.1 96%NOMINAL DECAY HEAT RATE FIGURE 6.2-34 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO DECAY HEA T RATE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 0.6...-------,----r-----,-------,-------,--------, 108 106 104 102 100 98....Z;0.4 Z--" z:=0.20.0
+----+---------l o-0.2 I Z I-0.4I-0.6 10-__...........__.......__.-.1....1..__.-.1 96%NOMINAL DECAY HEAT RATE FIGURE 6.2-34 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO DECAY HEA T RATE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 115 110 105 100 95 900.04...------,"'..------,----.---------.-----.--------,I"0.02 Z=0'" u!:.GIl: 0.0w=>>"-,,,'" Zw_GIl:w-0.02
-0.04 85%NOMINAL HEAT TRANSFER COEFFICIENT FIGURE 6.2-35 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO CONTAINMENT UNIT COOLER HEAT TRANSFER COEFFICIENT RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT 115 110 105 100 95 900.04...------,"'..------,----.---------.-----.--------,I"0.02 Z=0'" u!:.GIl: 0.0w=>>"-,,,'" Zw_GIl:w-0.02
-0.04 85%NOMINAL HEAT TRANSFER COEFFICIENT FIGURE 6.2-35 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO CONTAINMENT UNIT COOLER HEAT TRANSFER COEFFICIENT RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT 0.15Z LI.I0.1'" to-_ZV;o A.0.05 u-LI.I4(::)LI.I vt A.0.0 I----+----f-----:'lk----+---+----l-A.og-0.05
-0.1 85 90 95 100 105 110 115%NOMINAL HEAT TRANSFER COEFFICIENT FIGURE 6.2-36 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO RHR HEAT EXCHANGER HEAT TRANSFER COEFFICIENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 0.15Z LI.I0.1'" to-_ZV;o A.0.05 u-LI.I4(::)LI.I vt A.0.0 I----+----f-----:'lk----+---+----l-A.og-0.05
-0.1 85 90 95 100 105 110 115%NOMINAL HEAT TRANSFER COEFFICIENT FIGURE 6.2-36 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO RHR HEAT EXCHANGER HEAT TRANSFER COEFFICIENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
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Q.6....100%HEAT SINK AREA Z w4Z-ce.....z 20 VI I I I ce 0 25 50 75 100 w Q.%NOMINAL HEAT SINK AREA FIGURE 6.2-37 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO PASSIVE HEAT SINK AREA RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT Cl Z;:: C DC Cl JlI J30 20 L NODE NUMBER (TYP)" , , I ,!, J,,-J34 24 J42 NUMBER (TYP), , I ," PIPE DESIGNATION:
A FEEDWATER INLET (4)12" B RECIRC.SUCTION (2)20" C RECIRC.INLET 00)10" D LPCS (2)12" E RHR (4)10" NOTES: 1.(I INDICATES ASSUMED LOCATION OF PIPE NOZZLE 2.FEEDWATU LINE IREAK IS ASSUMED TO OCCUR IN NODES 26 AND 27 FIGURE 6.2-38 NODALIZATION DIAGRAM FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 27 NODE MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT Cl Z;:: C DC Cl JlI J30 20 L NODE NUMBER (TYP)" , , I ,!, J,,-J34 24 J42 NUMBER (TYP), , I ," PIPE DESIGNATION:
A FEEDWATER INLET (4)12" B RECIRC.SUCTION (2)20" C RECIRC.INLET 00)10" D LPCS (2)12" E RHR (4)10" NOTES: 1.(I INDICATES ASSUMED LOCATION OF PIPE NOZZLE 2.FEEDWATU LINE IREAK IS ASSUMED TO OCCUR IN NODES 26 AND 27 FIGURE 6.2-38 NODALIZATION DIAGRAM FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 27 NODE MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 55 1------------4------------+--------1 26,27 45--e(en35 w eM: 27,26 j en en iW eM:25 7 15
___i:J 2 3456789 2 3456789 2 10-3 10-2 10-1 TIME AFTER BREAK (SEC)FIGURE 6.2-39 NODAL PRESSURES FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 27 NODE MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 55 1------------4------------+--------1 26,27 45--e(en35 w eM: 27,26 j en en iW eM:25 7 15
___i:J 2 3456789 2 3456789 2 10-3 10-2 10-1 TIME AFTER BREAK (SEC)FIGURE 6.2-39 NODAL PRESSURES FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 27 NODE MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 40---------------,-----------,-------------,-I Q../(P27-P 2S)'" A.30-------_..-.......Z ill20 ill........Q ill:;)'" 10'" illA.0..__......................10-3 TIME AFTER BREAK (SEC)FIGURE 6.2-40 NODAL PRESSURE DIFFERENTIALS FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 27 NODE MODEL RIVER BEND 5l A liON UPDATED SAFETY ANALYSIS REPORT 40---------------,-----------,-------------,-I Q../(P27-P 2S)'" A.30-------_..-.......Z ill20 ill........Q ill:;)'" 10'" illA.0..__......................10-3 TIME AFTER BREAK (SEC)FIGURE 6.2-40 NODAL PRESSURE DIFFERENTIALS FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 27 NODE MODEL RIVER BEND 5l A liON UPDATED SAFETY ANALYSIS REPORT 20.71'22 J40 J8 J6 11 10 J4 J2 20 18 J36 C)z...c('" C)
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---.......--.i-EL 100'8" I,,,,I,,I I , I ,I 225°240°270°300°330°360°,0°30°60°90°120°150°180°210°225°PIPE DESIGNATION:
A=FEEDWATER INLET (4)12" B=RECIRC.SUCTION (2)20" C=RECIRC.INLET (lO)10" D=lPCS (2)12" E=RHR (4)10" NOTES: 1.,-)INDICATES ASSU MED lOCA TlON-OF PIPE NOZZLE 2.FEEDWATER LINE BREAK IS ASSUMED TO OCCUR IN NODES 2,3,6 AND 7 FIGURE 6.2-41 NODALIZATION DIAGRAM FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 25 NODE MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 20.71'22 J40 J8 J6 11 10 J4 J2 20 18 J36 C)z...c('" C)
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---.......--.i-EL 100'8" I,,,,I,,I I , I ,I 225°240°270°300°330°360°,0°30°60°90°120°150°180°210°225°PIPE DESIGNATION:
A=FEEDWATER INLET (4)12" B=RECIRC.SUCTION (2)20" C=RECIRC.INLET (lO)10" D=lPCS (2)12" E=RHR (4)10" NOTES: 1.,-)INDICATES ASSU MED lOCA TlON-OF PIPE NOZZLE 2.FEEDWATER LINE BREAK IS ASSUMED TO OCCUR IN NODES 2,3,6 AND 7 FIGURE 6.2-41 NODALIZATION DIAGRAM FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 25 NODE MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 35 234567 89 10-1 6"""-__2,3 1,4 5,8 23456 789 10-2 2 15....__"----.l.....'""'-.............
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.....__..........I 10-3-'"Yo!::::)'"
'" 25 1,&.1 7 Gl:TIME AFTER BREAK (SEC)FIGURE 6.2-42 NODAL PRESSURES FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 25 NODE MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 10-2 TIME AFTER BREAK (SEC)o..---......II....10-3 FIGURE 6.2-43 NODAL PRESSURE DIFFERENTIALS FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 25 NODE MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 10-2 TIME AFTER BREAK (SEC)o..---......II....10-3 FIGURE 6.2-43 NODAL PRESSURE DIFFERENTIALS FEEDWATER LINE BREAK RPV-SHIELD WALL ANNULUS 25 NODE MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 24 19 F EL 137'-
13 14 15 16 17 18 LODE NUMBER (TYP)EL 100.67'-
180 0 150 0 120 0 90 0 60 0 30 0 0 0 PIPE DESIGNATION:
A FEEDWATER INLET (4)12" B RECIRC.SUCTION (2)20" C RECIRC.INLET (10)10" D LPCS (2)12" E RHR (4)10" NOTES: 1.()INDICATES ASSUMED LOCATION OF PIPE NOZZLE 2.RECIRC.SUCTION LINE BREAK IS ASSUMED TO OCCUR IN NODE 1 FIGURE 6.2-44 N TINI RAM RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 24 19 F EL 137'-
13 14 15 16 17 18 LODE NUMBER (TYP)EL 100.67'-
180 0 150 0 120 0 90 0 60 0 30 0 0 0 PIPE DESIGNATION:
A FEEDWATER INLET (4)12" B RECIRC.SUCTION (2)20" C RECIRC.INLET (10)10" D LPCS (2)12" E RHR (4)10" NOTES: 1.()INDICATES ASSUMED LOCATION OF PIPE NOZZLE 2.RECIRC.SUCTION LINE BREAK IS ASSUMED TO OCCUR IN NODE 1 FIGURE 6.2-44 N TINI RAM RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 50 45 t-------+--------+--------+-----------J 401--------+-------+----------+----------1 35<C(iii e:....30::J VI lit...Q.25 20 15 10
.....
10-3 10-2 10-1 10°10 1 TIME AFTER BREAK (SEC)FIGURE 6.2-45a NODAL PRESSURES RECIRCULAtiON OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 50 45 t-------+--------+--------+-----------J 401--------+-------+----------+----------1 35<C(iii e:....30::J VI lit...Q.25 20 15 10
.....
10-3 10-2 10-1 10°10 1 TIME AFTER BREAK (SEC)FIGURE 6.2-45a NODAL PRESSURES RECIRCULAtiON OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT J//-50 45 40-35 4(Vi A.-...;30::)en en&UA.25 20 15 10-1 TIME AFTER BREAK (SEC)10 1 FIGURE 6.2-45b NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT J//-50 45 40-35 4(Vi A.-...;30::)en en&UA.25 20 15 10-1 TIME AFTER BREAK (SEC)10 1 FIGURE 6.2-45b NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 50 45 40 35 25 20 15 I J/A/-V 10-1 TIME AFTER BREAK (SEC)10 1 FIGURE 6.2-45c NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 50 45 40 35 25 20 15 I J/A/-V 10-1 TIME AFTER BREAK (SEC)10 1 FIGURE 6.2-45c NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 10'10-1 TIME AFTER BREAK (SEC)I/8 h A ,<'-....-21 10 10-3 lS 50 20 35 40 4S-'"!!:.'II CIl: 30'"'"'II CIl: IlL 25 FIGURE 6.2-45d NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 10'10-1 TIME AFTER BREAK (SEC)I/8 h A ,<'-....-21 10 10-3 lS 50 20 35 40 4S-'"!!:.'II CIl: 30'"'"'II CIl: IlL 25 FIGURE 6.2-45d NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 50 r--------,.--------,.--------,.------------, 45 t--------t---------t---------t------------l 40 t--------t---------t---------t------------l 35 t--------t---------t---------t------------l-e iii!:.: 30" 12r-£\620'0/
10 1 10-1 TIME AFTER BREAK (SEC)10....'--'--"---..1 10-3 10-2 FIGURE 6.2-45e NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIEL.D WALL ANNULUS 26 NODEHALFMODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 50 r--------,.--------,.--------,.------------, 45 t--------t---------t---------t------------l 40 t--------t---------t---------t------------l 35 t--------t---------t---------t------------l-e iii!:.: 30" 12r-£\620'0/
10 1 10-1 TIME AFTER BREAK (SEC)10....'--'--"---..1 10-3 10-2 FIGURE 6.2-45e NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIEL.D WALL ANNULUS 26 NODEHALFMODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PI-P 14 10'3S r---------,----------,.--------r----------, 30 1---------+--------+--------+----------;
2S 1---------+--------+--------+----------;
o'It!:....20 1---------+--------+--------+----------;;:)'It'It...: lS 1---------+--------+--------+----------;
-'z: 10
.........o-S....------......------.....-------.....------....,j 10-3 FIGURE 6.2-46 NODAL PRESSURE DIFFERENTIALS RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND ST A TION UPDATED SAFETY ANALYSIS REPORT PI-P 14 10'3S r---------,----------,.--------r----------, 30 1---------+--------+--------+----------;
2S 1---------+--------+--------+----------;
o'It!:....20 1---------+--------+--------+----------;;:)'It
'It...: lS 1---------+--------+--------+----------;
-'z: 10
.........o-S....------......------.....-------.....------....,j 10-3 FIGURE 6.2-46 NODAL PRESSURE DIFFERENTIALS RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND ST A TION UPDATED SAFETY ANALYSIS REPORT CD DRYWELL HEADDRYWELL BELOW REFUELING SEAL Note: The RCIC head spray line has been deleted and the associated high energy line breaks are no longer possible.However, this failure and infonnation is being provided as the bounding conditions that were established as part of the original plant design and licensing bases.Figure 6.2-47 NODALIZATION DIAGRAM 6-IN.RCIC HEAD SPRAY LINE BREAK DRYWELL HEAD SUBCOMPARTMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 12 December 1999.CD DRYWELL HEADDRYWELL BELOW REFUELING SEAL Note: The RCIC head spray line has been deleted and the associated high energy line breaks are no longer possible.However, this failure and infonnation is being provided as the bounding conditions that were established as part of the original plant design and licensing bases.Figure 6.2-47 NODALIZATION DIAGRAM 6-IN.RCIC HEAD SPRAY LINE BREAK DRYWELL HEAD SUBCOMPARTMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 12 December 1999.
28 26 24-r*22 I-=20 I::>>"t"t 18 Y.I M'6-----14 12 0.00 ,DRYWELL HEAD r 1.00 2.00 3.00 TIME AFTER BREAK (SEC)P,_____Note: The RCIC head spray line has been deleted and the associated high energy line breaks are no longer possible.However, this failure and information is being provided as the bounding conditions that were established as part of the original plant design and licensing bases.Figure 6.2-48 NODAL PRESSURES 6-IN.RCIC HEAD SPRAY LINE BREAK DRYWELL HEAD SUBCOMPARTMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 12 Decem ber 1999 28 26 24-r*22 I-=20 I::>>"t"t 18 Y.I M'6-----14 12 0.00 ,DRYWELL HEAD r 1.00 2.00 3.00 TIME AFTER BREAK (SEC)P,_____Note: The RCIC head spray line has been deleted and the associated high energy line breaks are no longer possible.However, this failure and information is being provided as the bounding conditions that were established as part of the original plant design and licensing bases.Figure 6.2-48 NODAL PRESSURES 6-IN.RCIC HEAD SPRAY LINE BREAK DRYWELL HEAD SUBCOMPARTMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 12 Decem ber 1999 10.00-a-vt 1.00..(---'""-'2 eM::>>vt 6.00 vt I'" eM....C 4.00-...Z'" eM'" 2.00......-Q 0.00 L......i........."1,,,,0
__0.00 1.00 2.00 3.00 4.00 TIME AFTER BREAK (SEC)Note: The RCIC head spray line has been deleted and the associated high energy line breaks are no longer possible.However, this failure and infonnation is being provided as the bounding conditions that were established as part of the original plant design and licensing bases.Figure 6.2-49 NODAL PRESSURE DIFFERENTIALS 6-IN.RCIC HEAD SPRAY LINE BREAK DRYWELL HEAD SUBCOMPARTMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 12 December 1999 10.00-a-vt 1.00..(---'""-'2 eM::>>vt 6.00 vt I'" eM....C 4.00-...Z'" eM'" 2.00......-Q 0.00 L......i........."1,,,,0
__0.00 1.00 2.00 3.00 4.00 TIME AFTER BREAK (SEC)Note: The RCIC head spray line has been deleted and the associated high energy line breaks are no longer possible.However, this failure and infonnation is being provided as the bounding conditions that were established as part of the original plant design and licensing bases.Figure 6.2-49 NODAL PRESSURE DIFFERENTIALS 6-IN.RCIC HEAD SPRAY LINE BREAK DRYWELL HEAD SUBCOMPARTMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 12 December 1999 EL-2S6'3" J3 EL-186'3" I EL-186'3"::E JS J1 w O 0°c:r:a: RWCU 0.)(-(/)::I:C'l J6 HX ROOM w a:LL.c (NODE 1)J2 c:r:OO-1 WZ=>0-BALANCE OF z_CONTAINMENT Z(/)J7 c:r:'-FREE VOLUME=>0 (NODE 4)EL-147'3" EL-144'6" J4 EL-144'6" J8 BELOW HX ROOM (NODE 3)J9 EL-137'6" EL-90'O" FIGURE 6.2-50 NODALIZATION DIAGRAM 6-IN RWCU LINE BREAK RWCU HEAT EXCHANGER ROOM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT EL-2S6'3" J3 EL-186'3" I EL-186'3"::E JS J1 w O 0°c:r:a: RWCU 0.)(-(/)::I:C'l J6 HX ROOM w a:LL.c (NODE 1)J2 c:r:OO-1 WZ=>0-BALANCE OF z_CONTAINMENT Z(/)J7 c:r:'-FREE VOLUME=>0 (NODE 4)EL-147'3" EL-144'6" J4 EL-144'6" J8 BELOW HX ROOM (NODE 3)J9 EL-137'6" EL-90'O" FIGURE 6.2-50 NODALIZATION DIAGRAM 6-IN RWCU LINE BREAK RWCU HEAT EXCHANGER ROOM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 14.014.515.015.5 16.016.517.00.00.51.01.52.02.53.03.54.04.55.0Time After Break (sec)Pressure (psia)
P1 P2 P3 P4 FIGURE 6.2-51 NODAL PRESSURES 6-IN RWCU LINE BREAK RWCU HEAT EXCHANGER ROOM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
REVISION 22
-1.5-1.0
-0.50.0 0.5 1.0 1.5 2.0 0.0 0.51.01.52.02.5Time After Break (sec)Pressure (psid)1.80 psid @ 1.75 sec FIGURE 6.2-52 NODAL PRESSURE DIFFERENTIAL 6-IN RWCU LINE BREAK RWCU HEAT EXCHANGER ROOM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
REVISION 22 Filter/ Demineralizer North Room (Node 2) Filter/ Demineralizer South Room (Node 1)
Holding Pump Room (Node 3)
Containment (Node 4) J1 J2 J4 J3 J5 J6 J7 J8 J9 J10 J11 EL-1863 EL-1623 EL-1863 EL-163 EL-1863 EL-1623 EL-900EL-2563 FIGURE 6.2-53 NODALIZATION DIAGRAM 8-IN RWCU LINE BREAK RWCU FILTER / DEMINERALIZER ROOM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 19 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 250102030405060708090100Time After Break (seconds)Pressure (psia)
FIGURE 6.2-54 NODAL PRESSURES 8-IN RWCU LINE BREAK RWCU FILTER / DEMINERALIZER ROOM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 19
CONTAINMENTVESSEL SHIELD BLDG'------AUX BLDG RHR'B'RETURN RHR'B'PUMP SUCTION--RHR'A'PUMP SUCTION"---RHR'A'RETURN FIGURE 6.2-56 RHR SUPPRESSION POOL COOLING MODE SUCTION AND RETURN (PLAN)RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENTVESSEL SHIELD BLDG'------AUX BLDG RHR'B'RETURN RHR'B'PUMP SUCTION--RHR'A'PUMP SUCTION"---RHR'A'RETURN FIGURE 6.2-56 RHR SUPPRESSION POOL COOLING MODE SUCTION AND RETURN (PLAN)RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SHIELD BLDG EL 98'-0" EL 83'-0" CONTAINMENT VESSEL RHR RETURN LINE (TYP.)DRYWELL WALLHWL EL 90'-0" (LWL EL 89'-6")
EL 70'-0" SUPPRESSION POOL LEVEL WEIR ELWALL RHR SUCTION (TYP)FIGURE 6.2-57 RHR SUPPRESSION POOL COOLING MODE SUCTION AND RETURN (SECTION 1-1)RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT SHIELD BLDG EL 98'-0" EL 83'-0" CONTAINMENT VESSEL RHR RETURN LINE (TYP.)DRYWELL WALLHWL EL 90'-0" (LWL EL 89'-6")
EL 70'-0" SUPPRESSION POOL LEVEL WEIR ELWALL RHR SUCTION (TYP)FIGURE 6.2-57 RHR SUPPRESSION POOL COOLING MODE SUCTION AND RETURN (SECTION 1-1)RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT
- ,*&,*:
- &#*&#'** / 25,000 &#Q$,%::#Q$,%:
- , 23@ #*&#*#
- #@###,#&####*
- @,&##*#:#@###,#&####*:@,&#?~?~
20 100 20 100 4 20 ci 16 80 i=80HORSEPOWER Z Z...V Ill:-Ill:.........Ill:!:.0;:)12 60>-60 A.sn...sn V sn...Z Ill: Ill:0 A.J: V YoYo<<8 40...40sn 0..__..__.....1....__....__....._-_..__...._-_....__..__.....1....__...4,000 8,000 12,000 16,00020,00024,000 28,000 32,000 36,000 CAPACITY (CFM)FIGURE 6.2-59 SGTS FAN PERFORMANCE CURVE RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 20 100 20 100 4 20 ci 16 80 i=80HORSEPOWER Z Z...V Ill:-Ill:.........Ill:!:.0;:)12 60>-60 A.sn...sn V sn...Z Ill: Ill:0 A.J: V YoYo<<8 40...40sn 0..__..__.....1....__....__....._-_..__...._-_....__..__.....1....__...4,000 8,000 12,000 16,00020,00024,000 28,000 32,000 36,000 CAPACITY (CFM)FIGURE 6.2-59 SGTS FAN PERFORMANCE CURVE RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 20 100 50 10 20 4 0.16 80 40STATIC-I-Z EFFICIENCY Z&II IlIII:-V&II&II IlIII:&II IlIII: Q.0 a 12 60;-30 e;'" loY V'" IlIII: Z IlIII: Q.loY 0 U%I-"-8 40&II 20'" 4,000 8,00012,00016,000 20,000 24,000 28,000 32,000 36,000 CAPACITY (CFM)FIGURE 6.2-60 FUEL BUILDING CHARCOAL FILTRATION SYSTEM FAN PERFORMANCE CURVE RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 20 100 50 10 20 4 0.16 80 40STATIC-I-Z EFFICIENCY Z&II IlIII:-V&II&II IlIII:&II IlIII: Q.0 a 12 60;-30 e;'" loY V'" IlIII: Z IlIII: Q.loY 0 U%I-"-8 40&II 20'" 4,000 8,00012,00016,000 20,000 24,000 28,000 32,000 36,000 CAPACITY (CFM)FIGURE 6.2-60 FUEL BUILDING CHARCOAL FILTRATION SYSTEM FAN PERFORMANCE CURVE RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT PRESSURE IN SHIELD BUILDING ANNULUS VS 11ME 6,..----------------------------------..
5 4:::J21VI;0*-O.25ln W.G.*.**.***
..***.*..*******.*******
- ..1 20.5 sec 0 2/216 sec 250 200 150 100 50-3+---------r---------,..-------..,.-------.....-------f o TIme (MC)FIGURE 6.2-610 PRESSURE IN SHIELD BUILDING ANNULUS VS TIME RIVER BEND STATION UPDATED SAFETY ANAL YSIS REPORT REVISION 13 SEPTEMBER 2000 PRESSURE IN SHIELD BUILDING ANNULUS VS 11ME 6,..----------------------------------..
5 4:::J21VI;0*-O.25ln W.G.*.**.***
..***.*..*******.*******
- ..1 20.5 sec 0 2/216 sec 250 200 150 100 50-3+---------r---------,..-------..,.-------.....-------f o TIme (MC)FIGURE 6.2-610 PRESSURE IN SHIELD BUILDING ANNULUS VS TIME RIVER BEND STATION UPDATED SAFETY ANAL YSIS REPORT REVISION 13 SEPTEMBER 2000 REVISION 14SEPTEMBER 2001RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORTPRESSURE IN AUXILIARYBUILDING VS TIMEFIGURE 6.2-61b RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTPRESSURE IN FUEL BUILDING VS TIMEFIGURE 6.2-62REVISION 14SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED MAIN STEAM lEFF!MAIN STEAM IEFF)MAIN STEAM (EfF,\ ,c.,'--..;...TURIINE PLANTS MISe.I DIAINS (IFf)10" 0-*.....I..r-':"_.J..
t:>I::f-l-+
._,*__
Rill*STEAM SUPPLY AND
...ReIC SlEAM SUPPLY\ffF) tc;;\
EP..."CS**-.!f"'<....fooJ f I
....a.,\lAIN STEAM (lffl f-d.!a Ill'U sc.J:.:JREACtOR VESSEL 10" 1'2" 20" 12" 10" 10" SPAAGU IN REFUELINGC-'" CAVITT:.....__OM CONOENS" TI.....K(UP'AHO..
l10" 10" nEOWATER....-----Cl' (INF)IlIlR RnURN TO FHDWATER IINFI I.'FiEDWATER(INfl LPCS UNf!.*.
LPCI*A'(lNf) to**CRD SYSTEM.'SUPPLY (lNp)r NNS--t+-SC
- RHR HEAO SPRAY llNFl c.a SC-2-'----SC-lI=;l----roo-,." J.RelC HEAD SHAY IINF}....
...
§3H"C**-!-sc., 6" I SC-2";"" SC-lI.'ru'I----.....-:::---
.......*RWCU y O.RnURN'C.,-fl(*1 IEFf).']UACTOR WAUR....CliANUP PUMP SUCTION (Uff SC**--l.-SC*1 IHI SKUTIlOWN 1." COOLING SUPPLY (fff)$e.;--J.-IC.I." SAM'U_9!!E lr...E
- J t:CONTIOL (INfl REACTOI REORCULATION PUMP A*STANDBY LIOUIE CONlIOL (lNf)np L1HE (TlP),po ,-" ,-FAOM CONOENSA 1&1-2".-1'*I IolAllEUP ,,"D*OJUWOFF MS.'LCS 10" SYSI 10"HPCS (INfl II@sc.a-.t-K-'
f 10"10"LPCl'I'IINF)*
10"l 10".......c**LPCI'C'(lNflUACTOR IECIllCULATION PUMP I CRD INSUT AND r;-':1..WITHDIAW UNES (TYpl",__.....;."_.__....
{TOTAL 290 lINESI DRYWEU_CONTAINMENT*
- '-'L-SHIELD ILDG.LEGEND@MOTOR OPERATED tiD CONTROL 100 DRIVE@AIR OPERATED RHR RESIDUAL HEAT IEMOVAl e LPO lOW PRESSURE COOlANT INJECtiON MODE OF IHR GUARD PiPE LPCS lOW PIESSURE COU SPlAT INF I NfLUENT HPCS HIGH PRESSURE CORE SPlAY Eff EFFLUE!'!T RCIC IUCTOR CORE ISOlATION COOLING E>I<:I HAND VALVE IIIORIFICE I EXCUS flOW VALVE I WAll@LEAKAGl MONITORING
...,.,..SEAL SYSTEM SUPPlY UHE ISSI CONNECTION II ILiND FLANGE NOTE, THIS STSTEM IS SAfETY CLASS I\SC,11 EXCEPT AS OTHElWISE NOreD.ALL VALVES ARE SAME SIZE AS PIPE fOIl DRTWELL lSOLAlION ONLY.NOT A CONTAINMENT ISOUllON VALVE.SHOWN FOR CLARITY.FIGURE 6.2-63 CRITERIA CRITERIONCONTAINMENT ISOLATION VALVES REVISION 12 DECEMBER 1999 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT L-![>6c:}- SPC RETURN (EFT)HPCS TEST RETURN (IN F)HPCS TEST IlETUILN THERMAL RELIEF IINF)HPCS PUMP MINIMUM FLOW BYI'ASS (lNF)RCIC PUMP SUCTION IEFF)HI'CS I'UMP DISCHARGE THEIMAL RELIEF IINf)RCIC I'UMP MINIMUM FLOW BYPASS (IN f)RHR LOOP"C" TEST RETURN liN F)IHI LOOP"B" TEST IETUIN (lNF)RHR PUMP"B" MINIMUM FLOW BYPASS (INF)IHR HEAT EXCHANGER"B" DUMP (INFI RHI PUMP"C" MINIMUM FLOW BYPASS (INF)HI'CS PUMI'SUCTION THEil MAL RElIEf (lNf)SUPPRESSION POOL PUM8ACK__SYSTEM RETURN LINE (INF)
RHR RELIEf VALVE VACUUM'U (EFF)RCIC TUIlIINE EXHAUST (lNF)AND ICte TUIIINE EXHAUST VACUUM IU (EFF)10" ,..I--_L--.....HPCS PUMP SUCTION IEFF),..II
..SPC RETURN (EFF)([I.....:.;;-....,.-DRYWEll SAMPLE (TYP, OF 2)SUPPRESSION I'OOL TO CONTAINMENT TO fLOOR CONT AINMENT DRAIN EQUII'MENT SUMP DRAIN SUMP-Jd RHR.....SUCTION THEil MAL IELIEF (lNf)Ill'HYOIOOEN*..MIXING 1" IlHI"C" SUCTION THEIMALIElIEf (INF)TO DllYWEll ITO.""+:"'IYSITE,M lIN')\1;".....-,..!.2-..--1-" IHI FLUSH LINE THEIMAL IElIEF (IN F)2"" LPCI.....DISCHAIGE RELIEF (INf)CONTAINMENT LI'C1"C'" DISCHAIGE RElIEf (IN F)HYDILOGEN MIXING.1 fM\fM\t}RHRSTEAMCONDENSING SYSTEM TIiERMAL RELIEF**..IHI HEAT EXCHANGEI.....VENT (lNF),......
...........POST ACCIDENT SAMPLING S LIQUID RETURN (INF)f-----..IHR PUMI'..." SUCTION (EFF)RHR PUMP*c*SUCTION (EFF)DIY WELL/HEAD REACTOIL VESSEL...FROM/TO-DIlYWEll/ATMOS.
%"------::fiJiIt-'
-SC2:-t NNS NNS---1, 20'm)4'*3" 10'*'.'/2" 12 LPCS PUMP DISCHARGE (lNF)CONTAINMENT AND DRY WEll PURGE SUPI'L Y (lNf)CONTAINMENT HYDROGEN PURGE SUPPLY (lNF)SHUTDOWN SUCTION THERMAL REliEF (lNFI RHI"A" SUCTION THERMAL REliEF IINF)LPCI"A" DISCHARGE RELIEF(lNF)
RHR STEAM CONDENSING IElIEF TYP.OF 2 (INF)RHR/RCIC, RELIEF{IN F)..6 IHR RElIEF VAL VE VACUUM 8KR.RHR HEAT EXCHANGER"A" VENT (INF)LP(S PUMP SUCTION liN F)CONTAINMENT AND DRYWElL SAMPLE"A" (EFF)FUEL POOL COOLING&CLEANUP SUCTION LINE IEFF): FUEL POOL PURIFICA liON SUCTION (£FF I...-------........----l FUEt POOL PURIFICA liON 6 DISCHARGE (INFI.....---, Fl!El POOL COOLING AND eLE ANUP*-----l.L.-__....."""'=-_....__DISCHARGE IINF)CONTAINMENT AND DRY WELL PURGE OUTlET (EFF)CCNTAINMENT HYDROGEN PURGE OUTlET TO ANNULUS CONTAINMENT LEAKAGE MONITORING tot-CHECK VALVELC.LOCKED CLOSED NOTE: THIS SYSTEM IS SAfETY CLASS 2(SC-2)EXCEPT AS OTHElW/SE NOTED.All VALVES AIlE SAME SIZE AS PIPE EXCEPT AS NOTED.EdITl@@fH INF.,." RELIEF VALVE*HAND VALVE-AIR OPEILI-TED 01 HYDILAUlIC OI'EIATED (HYV)*MOTOI OPERATED*STRAINER-GUAID PIPE-SOLENOID OPERATED*RADIATION MONITOR*LEAKAGE MONITORING CONNECTION EFflUENT flOW INflUENT FLOW LEGEND RHI_IlESIDUAL HEAT REMOVAL LPCI" LOW I'IlESSUIlE COOLANT INJECTION MODE OF RHR LPCS*LOW PRESSUIE COIlE SPR...Y"PCS-HIGH PRESSURE CORE SPIA Y ICIC-IlEACTOR CORE ISOLATION COOLING"FOR DAYWELl/SOLATlON ONLY.NOT A CONTAINMENT ISOLATION VALVE, SHOWN FOA CLAAITY.REVISION 10 APRIL 1998 FIGURE 6.2-64 CRITERION 56-CONTAINMENT ISOLATION VALVES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
NOTES^E_CEPT WHERE A DIFFERENT PREFI_ IS SHOWN.
1.600 CFM CPM`MOb 2B(BB)4B(BB)DRB`Z 57A DRB`Z 57B ELEb. 128c-0f AZ. 326 600 CFM CPM`MOb 4A(AR)2A(AR)106 ELEb. 114c-0f AZ. 170 AU_. BLDG.
ELEb. 135c-0f AZ. 34 b3000 101 b1 FC PURGE FAN FN1 30 CFM (MA_)
6 CFM (MIN)
LMC b6 30 CFM (MA_)
6 CFM (MIN)
SYSTEM TITLE SYS NO.REFERENCES 121 403 AIR SERbICE j BREATHING
HbAC-CONTAINMENT BUILDING
`MOb 104(ZB)Fb 103 FE 103 PI 2 ELEb. 141c-0f AZ. 318 CONTAINMENT DRYWELL HYDROGEN MI_ING 600 CFM (MA_)
CPM`FN1A(AR)
DRB`Z 58A DRB`Z 58B CPM`MOb 3A(AR)ELEb. 162c-0f AZ. 50 CONTAINMENT 600 CFM (MA_)
`b3(Z-)FC`b2(Z-)LMC LC`b4(Z-)LMC b5 CPM`FN1B(BB)
`SOb 140 (ZR)FI 2 3B(BB)1B(BB)ELEb. 162c-0f AZ. 225`MOb 105 (ZR)ELEb. 155c-0f AZ. 318CONTAINMENTANNULUS DWG NO.9.3-2k(C-21) 9.3-2 9.4-79.4-7q(D-12)9.4-7q(M-16)9.4-7q(M-15) bALbE LINEUPS.
INFORMATION ONLY. CONSULT THE STATION OPERATING PROCEDURES (SOPcS) FOR ACTUAL bALbE POSITIONS DEPICT THE PLANT IN ITS NORMAL OPERATING MODE AND ARE FOR PIPE CAPS USED ON bENTs DRAINs AND TEST CONNECTIONS THAT ARE NORMALLY ISOLATED FROM SYSTEM PRESSURE ARE NOT REvUIRED BY THE DESIGN FOR SYSTEM OPERABILITY.
ON v-CLASS 1 SYSTEMS THEY ARE REvUIRED BY THE FSAR TO LIMIT LEAKAGE IF bALbE LEAKAGE OCCURS.
1A(AR)3.4.LC LC LC FIGURE SYSTEM PjID27-21AREbISION 1 UPDATED SAFETY ANALYSIS REPORT RIbER BEND STATION 6.2-66 254 HYDROGEN MI_ING PURGE j RECOMBINER AUGUST 1988 P0207 L 212019181716151413121110987654321 212019181716151413121110987654321 J B P N M L K H G F E D C B A P N M K J H G F E D C A2.THE DASH (-) IN THE SYSTEM PREFIX IS REPLACED BY AN ASTERISK
(`) W HERE THE INSTRUMENT, VALVE, OR EQUIPMENT IS PART OF A NUCLEAR SAFETY RELATED SYSTEM.
ALL LINEs INSTRUMENTs bALbEs AND EvUIPMENT NUMBERS TO BE PREFI_ED WITH fCPP-f
`MOb CPM`MOb CPM`MOb CPM`MOb CPM`MOb CPM (THIS FIGURE HAS BEEN DELETED)FIGURE 6.2-67 CONTAINMENT HYDROGEN PURGE SYSTEM P&ID RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT (THIS FIGURE HAS BEEN DELETED)FIGURE 6.2-67 CONTAINMENT HYDROGEN PURGE SYSTEM P&ID RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT HYDROGEN CONCENTRATION VS TIME AFTER LOCA FIGURE 6.2-68REVISION20 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT HYDROGEN GENERATION FROM ALL SOURCES VS TIME AFTER LOCAFIGURE 6.2-69REVISION 14SEPTEMBER 2001 (THIS FIGURE HAS BEEN DELETED)FIGURE 6.2-70 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT (THIS FIGURE HAS BEEN DELETED)FIGURE 6.2-70 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 1*PT 2A'>!::PT 4A..c:y,__---i'll<PDT I------l I 29B
..-..
...
....*.*...j::::I r::::..,_.!."'.*.:.'.*.L-*.:...,j,r I U U
-HYDROGEN ANALYZER SYSTEMH,@--§H 2 FIGURE 6.2-71-....
......I:: c: 7i...A..9.I ITHIS SYSTEM IS SAFETY CLASS2(SC-2) 2.ALL INSTRUMENT NUMBERS TO BE PREFIXED WITH"ICMS" WHERE AN ASTERISK(*)
REPLACES THE DASH(-), THE INSTRUMENT IS PART OF THE NUCLEAR SAFETY SYSTEM.NOTE: RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 1/4" PIPE TAP FOR----'PERIODIC TESTING BElWEEN SEALS lONE EACH DOORI__-""""r"-----
INFLATABLE SEALS 3"TEST CONNECTION VIEW FROM OUTSIDE CONTAINMENT FIGURE 6.2-72 DET AILS OF PERSONNEL LOCK FOR PERIODIC TESTING RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 1/4" PIPE TAP FOR----'PERIODIC TESTING BElWEEN SEALS lONE EACH DOORI__-""""r"-----
INFLATABLE SEALS 3"TEST CONNECTION VIEW FROM OUTSIDE CONTAINMENT FIGURE 6.2-72 DET AILS OF PERSONNEL LOCK FOR PERIODIC TESTING RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
THIS FIGURE HAS BEEN DELETED FIGURE 6.2-73c SYSTEU552 CQNTAINUENT ATNOSPHERE AND LEAKAGE MONI TORING P&dO 3.3-2C REV.6 POCC.3 RIVER BEND STATION UPOA TED SAFETY ANAlYSIS REPORT Revision 6 August 1993 THIS FIGURE HAS BEEN DELETED FIGURE 6.2-73c SYSTEU552 CQNTAINUENT ATNOSPHERE AND LEAKAGE MONI TORING P&dO 3.3-2C REV.6 POCC.3 RIVER BEND STATION UPOA TED SAFETY ANAlYSIS REPORT Revision 6 August 1993
'----#--FEEDWATER NOZZLE Li..x'"1"""",--+---
NODE i v+Mz NOTTO SCALE NOTE: SEE FIGURES 6.2-38 AND 6.2-41 SEE TABLES 6.2-48 AND 6.2-49 FIGURE 6.2-74 ANNULUS PRESSURIZATION GEOMETRY FOR FORCE AND MOMENT CALCULATION FEEDWATER LINE BREAK RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT'----#--FEEDWATER NOZZLE Li..x'"1"""",--+---
NODE i v+Mz NOTTO SCALE NOTE: SEE FIGURES 6.2-38 AND 6.2-41 SEE TABLES 6.2-48 AND 6.2-49 FIGURE 6.2-74 ANNULUS PRESSURIZATION GEOMETRY FOR FORCE AND MOMENT CALCULATION FEEDWATER LINE BREAK RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 6r-----------------------__.
3.0.5\\\FORCE (27 NODE)1 5 ,\2.5" V'ORCE (25 NODE), , 4 MOMENT (27 NODE)2.0 U;(i)Q.S2 Q..S2 MOMENT (25 NODE)t-LL N C 0...3...><1.5-W t-O Z a: w 0LL 02 1.0 2 3456789 10°2345 6789 10-1 0..____1-__1-°.02345 6789 10.2 FIGURE 6.2-75 FORCE AND MOMENT TRANSIENTS FOR THE SHIELD WALL RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT 6r-----------------------__.
3.0.5\\\FORCE (27 NODE)1 5 ,\2.5" V'ORCE (25 NODE), , 4 MOMENT (27 NODE)2.0 U;(i)Q.S2 Q..S2 MOMENT (25 NODE)t-LL N C 0...3...><1.5-W t-O Z a: w 0LL 02 1.0 2 3456789 10°2345 6789 10-1 0..____1-__1-°.02345 6789 10.2 FIGURE 6.2-75 FORCE AND MOMENT TRANSIENTS FOR THE SHIELD WALL RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT 6....-------------------------
..3.0 5 2.5.5 1 4 FORCE (25 NODE)2.0 U;A-U;52 A-I I-52N MOMENT (27 NODE)0 0......3 1.5I-W Z 0 W cz: MOMENT (25 NODE)002 1.0 o..
...-....2...*3....4-5--6-7-8-9"'--2
-.3....4....5"611!17"8-'9*0.0 10-3 10.2 10.1 10 0 FIGURE 6.2-76 FORCE AND MOMENT TRANSIENTS FOR THE RPV RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT 6....-------------------------
..3.0 5 2.5.5 1 4 FORCE (25 NODE)2.0 U;A-U;52 A-I I-52N MOMENT (27 NODE)0 0......3 1.5I-W Z 0 W cz: MOMENT (25 NODE)002 1.0 o..
...-....2...*3....4-5--6-7-8-9"'--2
-.3....4....5"611!17"8-'9*0.0 10-3 10.2 10.1 10 0 FIGURE 6.2-76 FORCE AND MOMENT TRANSIENTS FOR THE RPV RIVER BEND 5T A TION UPDATED SAFETY ANALYSIS REPORT
THIS FIGURE HAS BEEN DELETED FIGURE 6.3-2 HIGH PRESSURE CORE SPRAY PROCESS DIAGRAM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 10 April 1998 2.0 0 M 1.0 J:: "-0 0l.LJ: Vl 0-Z BHP AT SPECIFIC GRAVITY=1.0 (TYPICAL TEST)a: UJo 3000 fu l/l a: o:I: 2000 w:.:<{a: o L--__.L.....L-__
1000 lD o 1000 5000 6000 7000 500 1-------NPSH REOUIRED AT 3 FT.ABOVE MOUNTING FLANGE (TYPICAL TEST)3000 4500 ,..------------------------------, 4000 3500 10002500 w J:...;!2000 oFLOW 19pml FIGURE 6.3-3 HPCS PUMP CHARACTERISTIC CURVES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 20
THIS FIGURE HAS BEEN DELETED FIGURE 6.3-5 LOW PRESSURE CORE SPRAY PROCESS DIAGRAM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 10 April 1998 HEAD CAPACITY CURVE ITYPICAL TEST)0 N 1.0:x:....0 0.::::x:<fl 0-Z 7000 6000 5000 4000 a:1500 0 BHP AT SPECIFIC GRAVITY=1.0 (TYPICAL TEST)fr;<fl 1000I 500<<a:!D 3000 2000 NPSH REQUIRED AT REFERENCE 3 FT.ABOVE MOUNTING FLANGE (TYPICAL TEST)1000 1300 1200 1100 1000 900 800....: '=700 0 4: UJ:x: 600-'4: f-500 0 f-400 300 200 100 0 0 FLOW IGPMI FIGURE 6.3-6 LPCS PUMP CHARACTERISTIC CURVES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 20 IOOOr--------------_---------------------",.o NPSH-REQUIRED AT 3 It ABOVE MOUNTING FLANGEITYPICAL TEST)o o N 1:...o1:....z 200 600..J: W 100 400"<a: CD 0 200 0>000 FLOW Igp",1 FIGURE 6.3-7 RHR (LPCI)PUMP CHARACTERISTIC CURVES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 20 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-8 RESIDUAL HEAT REMOVAL SYSTEM PROCESS DIAGRAM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 1.0 0.8 I-NORMALIZED POWER VERSUS TIME 0.6-a: IU...>-0(U IU 0 0.4-0.2 I-0 I I I I-0.01 0.1 1.0 10 100 1000 10.000 TIME AFTER BREAK l.eel FIGURE 6.3-9 NORMALIZED CORE POWER VERSUS TIME FOR LOSS-OF-COOLANT ACCIDENT ANALYSES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTNOMINAL AND APPENDIX K LOCABREAK SPECTRUM RESULTS FOR GE11 FUELFigure 6.3-10REVISION 14SEPTEMBER 2001
THIS FIGURE HAS BEEN DELETED FIGURE 6.3-19 HOT PIN FUEL AVERAGE TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-20 HOT PIN PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-21 RIVER BEND 8T A TION FINAL SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-22 NORMALIZED CORE AVERAGE INLET FLOW FOLLOWING A 0.8 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-23 CORE INLET ENTHALPY FOLLOWING A 0.8 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-24 MINIMUM CRITICAL POWER RATIO FOLLOWING A 0.8 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-25 WATER LEVEL INSIDE SHROUD FOLLOWING A 0.8 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-26 REACTOR VESSEL PRESSURE FOLLOWING A 0.8 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-27 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT DURING SLOWDOWN AT T HE HIGH POWER AXIAL NODE FOLLOWING A 0.8 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-28 PEAK CLADDING TEMPERATURE FOLLOWING A 0.8 X DBA BREAK RIVER BEND Sl A liON UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-29 CORE AVERAGE PRESSURE FOLLOWING A 0.6 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-30 NORMALIZED CORE AVERAGE INLET FLOW FOLLOWING A 0.6 X DBA BREAK RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-31 CORE INLET ENTHALPY FOLLOWING A 0.6 X DBA BREAK RIVER BEND 8T A TION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 63-32 MINIMUM CRITICAL POWER RATIO FOLLOWING A 0.6 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-33 WATER LEVEL INSIDE SHROUD FOLLOWING A 0.6 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-34 REACTOR VESSEL PRESSURE FOLLOWING A 0.6 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-35 FUEL ROD CONVECTIVE HEAT TRANSFER COEFFICIENT DURiNG SLOWDOWN AT THE HIGH POWER AXIAL NODE FOLLOWING A 0.6 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED FIGURE 6.3-36 PEAK CLADDING TEMPERATURE FOLLOWING A 0.6 X DBA BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTTYPICAL CORE AVERAGE PRESSUREVERSUS TIME AFTER BREAKFigure 6.3-37REVISION 14SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-38 NORMALIZED CORE AVERAGE INLET FLOW VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-39 CORE INLET ENTHALPY VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-40 MINIMUM CRITICAL POWER RATIO VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-41 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-42 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-43 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-44 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 TillS FIGURE HAS BEEN DELETED FIGURE 6.3-45 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-46 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-47 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-48 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-49 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-50 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-51 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-52 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATIONUPDATEDSAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-53 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-54 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-55 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-56 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-57 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-58 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-59 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-60 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-61 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-62 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 TillS FIGURE HAS BEEN DELETED FIGURE 6.3-63 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-64 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-65 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-66 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-67 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED ,--
..-,".....-,....FIGURE 6.3-68 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-69 WATER LEVEL INSIDE SHROUD VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-70 REACTOR VESSEL PRESSURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-71 CONVECTIVE HEAT TRANSFER COEFFICIENT VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION to APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-72 PEAK CLADDING TEMPERATURE VERSUS TIME AFTER BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 THIS FIGURE HAS BEEN DELETED FIGURE 6.3-73 TOTAL TIME FOR WHICH HIGHEST POWERED NODE REMAINS UNCOVERED VERSUS BREAK AREA RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 10 APRIL 1998 GASEOUS EFFLUENT RELEASE POINTS ROAD.LCN 01.02408)
MIN. DISTANCE RELEASE, - NO. - VENT BOUNDARY TO LINE E-. TURBINE BLDG. STANDBY GAS TRMNT.
I c ONTAINMENT PIPE TUNNELS AUXILIARY BLDG. @ RADWASTE BLOC. CONTROL BLOC 0 SMOKE REMOVAL BATTERY RYS MECH RM. UTILITY RMS. 30002 FT 290 2 FT 2850 f FT 2112~~ 2850 f FT. 102 k FT 2900 f FT 177 aFT @ FUEL BLDG 0 CONTROL RM. INTAKE 2800 f FT 161 f FT CONTROL RM REMOTE 2750 f Ff. 154fFT. @ AIR INTAKE 500 500 I000 1500 2000 2500 0 FEET 100 0 100 200. 300 400 500 METERS NOTE 1. DISTANCE FROM CENTERUNE REACTOR NO.l TO PROPERTY BOUND - 3035.15' 5. NEW ROAD AND PARKING LOT ADDED SEWAGE TREATMENT PLANT DELETED. EAST OF THE EAST PLANT ACCESS. LOCATION WASTE WATER E17.600, TREATMENT Nt4.500 PLANT ADDED. (LCN 01.02409)
I I RIVER BEND STATION I UPDATED SAFETY ANALYSIS REPORT I REVISION 10 REVISION 23 APRIL 1998 CA CD CJ 1 2 3 4 5 6 PLAN EL. 135'-0" CA CD CJ 1 2 3 4 PLAN EL. 115'-0" UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION FIG URE 6.4-2 MAIN CONTROL ROOM PRESSURE BOUNDARY REVISION 21 NO. 795E868AAXED WITH "MSI-"*) WHERE THE
!0
+0%0 NORMALLY ISOLATED-,--,-0 +%
+0%
! 8 6
-!!
- V54(B-)*V24(A-)*V52(B-)*V100 (A-)*V115 (A-)*V102(A-)(A-)*PT 22A (AR)*PT 9A (AR)2*V48(B-)*V49(B-)*V18(A-)*V19(A-)*V110(A-)*V111 (A-)FC*V112(A-)FO*PT 26A (AR)2*SOVY 26A (AR)*SOVX 26A (AR)*PT 10A (AR)*V14(A-)(A-)*PT 12A (AR)*V50(B-)*PT 12B (BB)*V41(B-)11B (BB)*PT 10B (BB)*V114 (A-)TO AUX BLDG ATMOSPHERE
- V113 (A-)*V105 (A-)ACCUMULATOR (TYP)(A-)*RV 8A (A-)*FE 20A (AR)*TK6A (A-)19A (AR)11A (AR)SET @140 PSIG SYSTEM TITLE SYS NO.NOTES:*PT 21B (BB)*V65(B-)*RO 202 (B-)KJB*Z 606E DRB*Z 382 KJB*Z 602D DRB*Z 415*RO 201 (A-)*PT 21A (AR)*V64(A-)122 609 109 MAIN STEAM DRAINS-FLOOR & EQUIPMENT AIR INSTRUMENT
REFERENCES:
1.ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "LSV-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
LO LO*V12(A-)*V42(B-)*V46(B-)
- V35(A-)*V17(A-)*V37(B-)*V72(B-)*V36(A-)*V76(B-)*V90(A-)*V77(B-)*V91(A-)*V73(B-)*PT 17B (BB)*MOV 16B (BB)15B (BB)*V94(A-)*PT 17A (AR)15A (AR)*MOV 16A (AR)CONTAINMENT DRYWELL SHIELD BUILDING
- V60(B-)*V61(B-)
- V31(A-)*V30(A-)*V62(B-)*V32(A-)*V33(A-)FC FO 2*V116(B-)*V117 (B-)*PT 26B (BB)*V118(B-)*SOVY (BB)*SOVX 26B (BB)*MOV*PT 14A (AR)13A (AR)*MOV 13B (BB)*MOV FC 2*V119 (B-)*V104 (B-)*V120 (B-)(B-)*V121 (B-)(B-)*V103 (B-)*PT 22B (BB)TO AUX BLDG ATMOSPHERE (B-)10B (BB)*FE 20B (BB)19B (BB)*PT 9B (BB)(B-)*V58(B-)*V59(B-)*V56(B-)*V26(A-)*V27(A-)*V66 (B-)*PT 14B (BB)(A-)9.3-7l(J-10) 10.3-1b(N-21) 6.7-1a(M-21)9.3-7l(H-18) 6.7-1a(M-12) 10.3-1b(M-11)
VALVE LINEUPS.
INFORMATION ONLY. CONSULT THE STATION OPERATING PROCEDURES (SOP'S) FOR ACTUAL VALVE POSITIONS DEPICT THE PLANT IN ITS NORMAL OPERATING MODE AND ARE FOR PIPE CAPS USED ON VENT, DRAIN, AND TEST CONNECTIONS THAT ARE NORMALLY ISOLATED FROM SYSTEM PRESSURE ARE NOT REQUIRED BY THE DESIGN FOR SYSTEM OPERABILITY.
ON Q-CLASS 1 SYSTEMS THEY ARE REQUIRED BY THE FSAR TO LIMIT LEAKAGE IF VALVE LEAKAGE OCCURS.
L20191817161514131211876543212019181716151413121110987654321 B P N M K J H G F E D C A 3.4.DWG. NO.9.3-1 9.3-7 10.3-1 FIGURE SYSTEM P&ID REVISIO N 23 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 6.7-1b 208 MSIV POSITIVE LEAKAGE CONTROL 27-20B P0204 COMPRESSOR SKID ASSEMBLY
- C3A*C3B COMPRESSOR SKID ASSEMBLY 1/2" X 3/4" RED.
1/2" X 3/4" RED.
- V98 1-1/4" X 1" RED.RED.1-1/4" X 1" 1/2" X 3/4" RED*RV (B-)8B*V84*V86*V82*TK6B 2*V3041B*V3040B 2*V3040A*V3041A*V6*MOV*PV*V95*MOV*MOV 26B*MOV*V34*MOV 6.7-1c (E-3) 6.7-1c (E-3)6.7-1c (P-19)6.7-1d (P-19) 6.7-1d (K-3) 6.7-1d (E-3)9.3-7l (H-18)9.3-7l(J-10)(SEE 6.7-1c FOR DETAIL)(SEE 6.7-1d FOR DETAIL) 2086.7-1MSIV POSITIVE LEAKAGE CONTROL
- V53(B-)2.THE ASTERISK "*" WAS USED IN A PREVIOUS EQUIPMENT IDENTIFICATION SYSTEM AT RIVER BEND STATION. REFER TO THE EQUIPMENT DATA BASE (ED B) FOR THE PROPER COMPONENT NUMBER AND SAFETY CLASSIFICATION.
NUCLEAR SAFETY RELATED ALL PIPING AND COMPONENTS WITHIN THIS HATCHED CLOUD HAVE BEEN ABANDONED IN PLACE PER MR96-0059.
5.NOTE 5 LO LO LCN 06.02-098 LO LO L212019181716151413121110987654321212019181716151413121110987654321 J B P N M L K H G F E D C B A P N M K J H G F E D C A*V10HA*V110AA*V110EA COOLER*E10CA.125 PERFORATED AUXILIARY BUILDING SUCTION FROM ATMOSPHERE SCREEN STR10BA S 44A COMPRESSOR (A-)52A*TW (AR)*V10EA*V110CA*PS (AR)49A*PS*AOV VALVE POSTIONS DEPICT THE PLANT IN ITS NORMAL OPERATING MODE ANDARE FOR INFORMATION ONLY. CONSULT THE STATION OPERATING PROCEDURES(SOP's) FOR ACTUAL VALVE LINEUPS.
ALL LINE, INSTRUMENT, VALVE AND EQUIPMENT NUMBERS TO BE PREFIXEDWITH "LSV-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.
3.1.*V10CA NOTES:*V10DA (A-)SEPARATOR TANK LG 51A (A-)*TW 46A*LC*V10FA*V10GA*V10BA 30A*V10AA 47A*PS 57A*PS 48A*PS 58A*PS
REFERENCES:
SYS NO.SYSTEM TITLE 208 118 MSIV POSITIVE LEAKAGE CONTROL SERVICE WATER NORMAL LS 28A*V3033A*V3034A 57A*PCV 41A (A-)*SP1A*V3037A*V3038A*C3A 59A (AR)*V3036A*V3035A*PCV (A-)42A*V3039A 6.ALL TUBING IS STAINLESS STEEL.
MULTI-LEVEL SWITCH ASSY.
- RO 40A 36A*RO 29A*RO*SOV 44A 50A*TW 32A*TW (A-)(A-)37A*RO MARK NUMBER IDENTIFIES INTERNAL COMPONENT WHICH IS NOT A PART OF THE PRESSURE BOUNDARY.
- PI 4.DELETED 5. 1LSV*AOV45A & B HAVE BEEN REPLACED BY CHECK VALVES 1LSV*V3032A & B.
AIR OUTLET FROM SOV*45A & B ASSOCIATED WITH THE AOV's IS PLUGGED PERMR92-0087 FCN4.
NOTE 5*V3032A FIGURE SYSTEM P&ID 27-20CREVISIONUPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 6.7-1c 208 LSV*C3A COMPRESSOR SKID 9.2-1c (J-19) 9.2-1c (J-20) 9.2-1c (H-20) 6.7-1b (B-15) 6.7-1b (D-15)6.7-1b (D-17) 6.7-1 9.2-1 DWG NO.LO 2.THE ASTERISK "*" WAS USED IN A PREVIOUS EQUIPMENT IDENTIFICATION SYSTEM ATRIVER BEND STATION. REFER TO THE ENT DATA BASE (DB) FOR THE PROPERCOMPONENT NUMBER AND SAFETY CLASSIFICATION.
NUCLEAR SAFETY RELATED 42*RO 7. THE LEVEL CONTROLLER OPERATING MECHANISM HAS BEEN REMOVED BY EC 40798.
LEVEL CONTROLLER SEAT ORIFICE CONTROLS SEPARATOR LEVEL.
NOTE 7 L212019181716151413121110987654321212019181716151413121110987654321 J B P N M L K H G F E D C B A P N M K J H G F E D C A6.7-1b (N-17)
- AOV 44B (BB)S STR10BB.125 PERFORATED SCREEN SUCTION FROM AUXILIARY BUILDING ATMOSPHERE
- TW 52B (B-)*V10EB*PS 49B (BB)*PS*V110CB LG SEPARATOR TANK*LC 46B (B-)*V10GB*PI 30B*V10AB*V10BB*PS*PS*PS*PS 47B 57B 48B 58B*V10FB*V10DB*V10CB*V110AB COOLER*E10CB*V110EB*V10HB COMPRESSOR NOTES: 1. ALL LINE, INSTRUMENT, VALVE AND EQUIPMENT NUMBERS TO BE PREFIXED
- 3. ALVE POS TIONS DEPICT THE PLANT IN ITS NORMAL OPERATING MODE AND ARE FOR INFORMATION ONLY. CONSULT THE STATION OPERATING PROCEDURES (SOP's) FOR ACTUAL VALVE LINEUPS.
- 4. DELETED SERVICE WATER NORMAL MSIV POSITIVE LEAKAGE CONTROL 118 208 SYSTEM TITLE SYS NO.
REFERENCES:
- V3039B*C3B LS 28B*SP1B*V3033B*V3034B 57B*PCV 41B(B-)*V3037B*V3038B*V3035B*V3036B 6. ALL TUBING IS STAINLESS STEEL.
- PCV 42B*RO 40B*RO 36B 29B*RO 37B*RO 59B (BB)(B-)*SOV 44B MULTI-LEVEL SWITCH ASSY.(B-)(B-)(B-)*TW 32B*TW 50B*TW 51B MARK NUMBER IDENTIFIES INTERNAL COMPONENT WHICH IS NOT A PART OF THE PRESSURE BOUNDARY.
5.1LSV*AOV45A & B HAVE BEEN REPLACED BY CHECK VALVES 1LSV*V3032A & B.AIR OUTLET FROM SOV*45A & B ASSOCIATED WITH THE AOV's IS PLUGGED PER
MR92-0087 FCN4.
NOTE 5*V3032B FIGURE SYSTEM P&ID 27-20DREVISIONUPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 6.7-1d 208 LSV*C3B COMPRESSOR SKID 9.2-1f (D-20) 9.2-1f (D-20) 9.2-1f (D-20) 6.7-1 9.2-1 DWG NO.6.7-1b (N-15) 6.7-1b (L-15)
LO NUCLEAR SAFETY RELATED COMPONENT NUMBER AND SAFETY CLASSIFICATION.
RIVER BEND STATION. REFER TO THE EQUIPMENT DATA BASE (EDB) FOR THE PROPER WITH "LSV-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN..THE ASTERISK "*" WAS USED IN A PREVIOUS EQUIPMENT IDENTIFICATION SYSTEM AT 41*RO 7. THE LEVEL CONTROLLER OPERATING MECHANISM HAS BEEN REMOVED BY EC 40798. LEVEL CONTROLLER SEAT ORIFICE CONTROLS SEPARATOR LEVEL.
NOTE 7