Text

5 to the Updated Safety Analysis Report, Chapter 6, Figures 6.2-1 Through 6.7-2
	ML17226A135
Person / Time
Site:	River Bend
Issue date:	07/28/2017
From:	; Entergy Operations
To:	; Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML17226A087	List: ML17226A095; ML17226A097; ML17226A098; ML17226A099; ML17226A100; ML17226A101; ML17226A102; ML17226A103; ML17226A104; ML17226A107; ML17226A108; ML17226A109; ML17226A111; ML17226A112; ML17226A113; ML17226A114; ML17226A116; ML17226A117; ML17226A118; ML17226A119; ML17226A120; ML17226A121; ML17226A122; ML17226A125; ML17226A126; ML17226A127; ML17226A129; ML17226A130; ML17226A131; ML17226A133; ML17226A134; ML17226A135; ML17226A137; ML17226A138; ML17226A139; ML17226A140; ML17226A141; ML17226A143; ML17226A144; ML17226A146; ML18188A001; ML18188A002; ML18188A003; ML18188A004; ML18188A005; RBG-47776, 5 to the Updated Safety Analysis Report, Index;
References
	RBG-47776, RBF1-17-0089
	Download: ML17226A135 (191)
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{{#Wiki_filter:TURBINE STOP VALVES TURBINE BYPASS CONTAINMENT ~ flOW RESTRICTORS DRYWElL BREAK (DERI REACTOR PRESSURE VESSEL FIGURE 6.2-1 MAIN STEAM LINE BREAK SCHEMATIC RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT TURBINE STOP VALVES TURBINE BYPASS CONTAINMENT ~ flOW RESTRICTORS DRYWElL BREAK (DERI REACTOR PRESSURE VESSEL FIGURE 6.2-1 MAIN STEAM LINE BREAK SCHEMATIC RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT MAIN STEAM LINE BREAK FLOW AREA Figure 6.2-2

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RECIRCULATION LINE BREAK SCHEMATICS Figure 6.2-3 REVISION 14 SEPTEMBER 2001 0.071 0.354 =2.198

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT PRESSURE RESPONSE FOR MAIN STEAM LINE BREAK Figure 6.2-4 NOTES:

1) SHORT TERM RESPONSE IS BASED ON INITIAL HIGH SUPPRESSION POOL LEVEL AND ZERO FEEDWATER ADDITION

2) LONG TERM RESPONSE IS BASED ON INITIAL LOW SUPPRESSION POOL LEVEL AND ADDITION OF ALL HOT FEEDWATER

3) LONG TERM WETWELL RESPONSE FOLLOWS THAT OF THE CONTAINMENT

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT PRESSURE RESPONSE FOR RECIRCULATION LINE BREAK FIGURE 6.2-5 REVISION 14 SEPTEMBER 2001 Pressure (psia) NOTES:

1) SHORT TERM RESPONSE IS BASED ON INITIAL HIGH SUPPRESSION POOL LEVEL AND ZERO FEEDWATER ADDITION

2) LONG TERM RESPONSE IS BASED ON INITIAL LOW SUPPRESSION POOL LEVEL AND ADDITION OF ALL HOT FEEDWATER

3) LONG TERM WETWELL RESPONSE FOLLOWS THAT OF THE CONTAINMENT

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT TEMPERATURE RESPONSE FOR MAIN STEAM LINE BREAK Figure 6.2-6

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT TEMPERATURE RESPONSE FOR RECIRCULATION LINE BREAK FIGURE 6.2-7 REVISION 14 SEPTEMBER 2001 NOTES:

1) SHORT TERM RESPONSE IS BASED ON INITIAL HIGH SUPPRESSION POOL LEVEL AND ZERO FEEDWATER ADDITION

2) LONG TERM RESPONSE IS BASED ON INITIAL LOW SUPPRESSION POOL LEVEL AND ADDITION OF ALL HOT FEEDWATER

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT VENT FLOW RATE FOR MAIN STEAM LINE BREAK Figure 6.2-8 (M3CPT 0-30 SEC)

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT BLOWDOWN MASS FLOW RATE FOR MAIN STEAM LINE BREAK Figure 6.2-9 Time after LOCA (sec) BLOWDOWN MASS FLOWRATE (LBM/SEC) (M3CPT 0-30 SEC)

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT BLOWDOWN COMPARISON BETWEEN RBS & CPS MAIN STEAM LINE BREAK MASS FLOW RATE VS TIME FIGURE 6.2-9a REVISION 14 SEPTEMBER 2001 SHEX 0-1800 SECONDS

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT BLOWDOWN COMPARISION BETWEEN RBS & CPS MAIN STEAM LINE BREAK ENERGY FLOW RATE VS TIME Figure 6.2-9b Time after LOCA (sec) BLOWDOWN MASS FLOWRATE (LBM/SEC) SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT BLOWDOWN MASS FLOW RATE FOR RECIRCULATION SUCTION LINE BREAK Figure 6.2-10 REVISION 14 SEPTEMBER 2001 (M3CPT 0-30 seconds)

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT BLOWDOWN COMPARISION BETWEEN RBS & CPS MAIN STEAM LINE BREAK MASS FLOW RATE VS TIME Figure 6.2-10a Time 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 BREAK ENERGY FLOW RATE VS TIME FIGURE 6.2-10b REVISION 14 SEPTEMBER 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 6.2-11 Multiply 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 ENERGY FOR MAIN STEAM LINE BREAK FIGURE 6.2-12 REVISION 14 SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT MAIN STEAM BREAK INTEGRATED CORE AND VESSEL METAL ENERGY FIGURE 6.2-13 (SHEX Long-Term)

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT METAL WATER REACTION HEAT FOR MAIN STEAM LINE BREAK FIGURE 6.2-14 REVISION 14 SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT ECCS AND RHR PUMP HEAT FOR MAIN STEAM LINE BREAK Figure 6.2-15 Time after LOCA (sec) PUMP HEAT (BTU/SEC)

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SUPPRESSION POOL WATER LEVEL MAIN STEAM LINE BREAK Figure 6.2-16 M3CPT (0-30 sec) WATER LEVEL (FT.) Time after LOCA (sec)

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SUPPRESSION POOL WATER LEVEL MAIN STEAM LINE BREAK FIGURE 6.2-16a SHEX (0-1800 sec)

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SUPPRESSION POOL WATER LEVEL MAIN STEAM LINE BREAK FIGURE 6.2-16b SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SUPPRESSION POOL WATER LEVEL RECIRCULATION LINE BREAK FIGURE 6.2-17 REVISION 14 SEPTEMBER 2001 M3CPT (0-30 sec)

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT SUPPRESSION POOL WATER LEVEL RECIRCULATION LINE BREAK FIGURE 6.2-17a REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RHR HEAT EXCHANGER DUTY FOR MAIN STEAM LINE BREAK FIGURE 6.2-18 REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RHR HEAT EXCHANGER DUTY FOR RECIRCULATION SUCTION LINE BREAK FIGURE 6.2-19 REVISION 14 SEPTEMBER 2001

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT UNIT COOLER DUTY FOR MAIN STEAM LINE BREAK FIGURE 6.2-20 REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT CONTAINMENT UNIT COOLER DUTY FOR RECIRCULATION SUCTION LINE BREAK FIGURE 6.2-21 REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PASSIVE DRYWELL HEAT SINK HEAT REMOVAL RATE FOR MAIN STEAM LINE BREAK FIGURE 6.2-22 REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PASSIVE CONTAINMENT HEAT SINK HEAT REMOVAL RATE FOR MAIN STEAM LINE BREAK FIGURE 6.2-22a REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PASSIVE DRYWELL HEAT SINK HEAT REMOVAL RATE FOR RECIRCULATION LINE BREAK FIGURE 6.2-23 REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PASSIVE CONTAINMENT HEAT SINK HEAT REMOVAL RATE FOR RECIRCULATION LINE BREAK FIGURE 6.2-23a REVISION 14 SEPTEMBER 2001 SHEX Long-term

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PASSIVE SINK SURFACE HEAT TRANSFER COEFICEIENT FOR MAIN STEAM LINE BREAK FIGURE 6.2-24 REVISION 14 SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PASSIVE SINK SURFACE HEAT TRANSFER COEFICEIENT FOR RECIRCULATION LINE BREAK FIGURE 6.2-25 REVISION 14 SEPTEMBER 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 6.2-27 REVISION 14 SEPTEMBER 2001

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT DRYWELL AND CONTAINMENT PRESSURES FOR A BREAK AREA OF 0.1 FT 2 WITH BYPASS LEAKAGE (A/ )OF 1.15 FT 2 (LICENSED POWER 2894 MWt) FIGURE 6.2-27a REVISION 14 SEPTEMBER 2001

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT DRYWELL AND CONTAINMENT PRESSURES FOR A BREAK AREA OF 0.1 FT2 WITH BYPASS LEAKAGE (A/) 0.81 FT2 (LICENSED POWER 3091 MWt)* FIGURE 6.2-27b REVISION 21 $QDO\\VLV3HUIRUPHGDW0:W

...lIC 1.5r------..,...------,----------r--------, ...z3 1.0 I---'-~---+--.,....-----+------+------I ~ "'~ ...lI =- 0.5 I--------+--"Illili~~---r------+-------t ...lI '" loY "- ~- )-1oY ~ ~ 0.0 I-------+-----~~-----+------I C'" ~~ ~ ~ -0.5 1-------+------+------"'I"~----1 ~ z -1.0 1--------+------+------+------1 120 110 100 90 -1.5....----""""-----"""""""----......----....,/ 80 % NOMINAL VENT AREA FIGURE 6.2-28 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO VENT AREA RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT ...lIC 1.5r------..,...------,----------r--------, ...z3 1.0 I---'-~---+--.,....-----+------+------I ~ "'~ ...lI =- 0.5 I--------+--"Illili~~---r------+-------t ...lI '" loY "- ~- )-1oY ~ ~ 0.0 I-------+-----~~-----+------I C'" ~~ ~ ~ -0.5 1-------+------+------"'I"~----1 ~ z -1.0 1--------+------+------+------1 120 110 100 90 -1.5....----""""-----"""""""----......----....,/ 80 % NOMINAL VENT AREA FIGURE 6.2-28 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO VENT AREA RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

c(- to-Z &AI DII: &AI lAo lAo c z 1.0 r-----.,-----,-----.-----.------~---._, / 0.5 t-----t----t--+--/~v~-------j 0.0 t-----t--/-+-v~~-+--------j -0.5 1-----+-~~~-+----+---+-----+----1 115 110 105 100 95 90 -1.0....---"'--------...---"""---....----' 85 &AI C) Zc(

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V % NOMINAL VENT SUBMERGENCE FIGURE 6.2-29 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO VENT SUBMERGENCE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT c(- to-Z &AI DII: &AI lAo lAo c z 1.0 r-----.,-----,-----.-----.------~---._, / 0.5 t-----t----t--+--/~v~-------j 0.0 t-----t--/-+-v~~-+--------j -0.5 1-----+-~~~-+----+---+-----+----1 115 110 105 100 95 90 -1.0....---"'--------...---"""---....----' 85 &AI C) Zc(

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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...._--'---_....__......._-_....__.......-_...... 0.8 0.9 1.0 1.1 1.2 1.3 1.4 TIME AFTER LOCA (SEC) =- 20.-------..-----.,----..----..------.------, ~ ~- loll ~ 19 r---I--r=:;====F====t::,~J:~1 ~ ~ loll ~ 18 I-----+-~c---t-----+----f'~~~;;;;;...~~~ ~ c( ~ 17 1--_~:...-j-----+----_+_---+__---'lL.~;;:__--_____j Z loll ~ loll ~ 16 ~~--+----+-----+----+__---_+_--___1 o loll 15 1-----+----+-----+----+----_+_--___1 ~ ~o FIGURE 6.2-30 SENSITIVITY OF DRYWELL DIFFERENTIAL PRESSURE TO AIR CARRYOVER RATE TO CONTAINMENT RIVER BEND 8TATION UPDATED SAFETY ANALYSIS REPORT 14...._--'---_....__......._-_....__.......-_...... 0.8 0.9 1.0 1.1 1.2 1.3 1.4 TIME AFTER LOCA (SEC) =- 20.-------..-----.,----..----..------.------, ~ ~- loll ~ 19 r---I--r=:;====F====t::,~J:~1 ~ ~ loll ~ 18 I-----+-~c---t-----+----f'~~~;;;;;...~~~ ~ c( ~ 17 1--_~:...-j-----+----_+_---+__---'lL.~;;:__--_____j Z loll ~ loll ~ 16 ~~--+----+-----+----+__---_+_--___1 o loll 15 1-----+----+-----+----+----_+_--___1 ~ ~o FIGURE 6.2-30 SENSITIVITY OF DRYWELL DIFFERENTIAL PRESSURE TO AIR CARRYOVER RATE TO CONTAINMENT RIVER BEND 8TATION UPDATED SAFETY ANALYSIS REPORT

95 100 105 110 % NOMINAL REACTOR BLOWDOWN o ~ -0.4 1.2 w ~ ~ ~ ~ UoI 0.8 ~ A. 0( I-Z UoI ~ 0.4 u. u. UoI ~>- 0.0 ~o ~ 0( UoI A. UoIoz 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 95 100 105 110

% NOMINAL REACTOR BLOWDOWN o ~ -0.4 1.2 w ~ ~ ~ ~ UoI 0.8 ~ A. 0( I-Z UoI ~ 0.4 u. u. UoI ~>- 0.0 ~o ~ 0( UoI A. UoIoz 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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-1.0 V 0.7 0.9 1.05 1.1 1.3 1.5 REACTOR LEVEL SWELL TIME (SEC) FIGURE 6.2-32 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO REACTOR LEVEL SWELL TIME FOR A MAIN STEAM LINE BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT c( 1.0 ZW \\ I¥ W 0.5 Q ..... = ~ ..... en Wa. ~- >w I¥I¥ 0.0 Q:::;) f"""ooo"~ l-en I ~~ c(l¥ I wa. I a. I Z -0.5 I w I 0 I Z I c( I

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-1.0 V 0.7 0.9 1.05 1.1 1.3 1.5 REACTOR LEVEL SWELL TIME (SEC) FIGURE 6.2-32 SENSITIVITY OF PEAK DRYWELL DIFFERENTIAL PRESSURE TO REACTOR LEVEL SWELL TIME FOR A MAIN STEAM LINE BREAK RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

0.6 ----.,....---~---...,._--__r_--_____,r_-_ ~ ~ ~ 0.4 I----~----+---+V--~+-----t-------I Z::' 0.2 7 o~ v- ~ ~ 0.0 1------+---/-----:J~--+_--__+_--___1I___-______I L~ Z..., I-----¥=-------+---+_--__+_--~I___-______I ~ -0.2 L Z 1------+------+---+----+---___1----1 ~ -0.4

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V -0.6....--.....--......---"""""---------.....- 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_--_____,r_-_ ~ ~ ~ 0.4 I----~----+---+V--~+-----t-------I Z::' 0.2 7 o~ v- ~ ~ 0.0 1------+---/-----:J~--+_--__+_--___1I___-______I L~ Z..., I-----¥=-------+---+_--__+_--~I___-______I ~ -0.2 L Z 1------+------+---+----+---___1----1 ~ -0.4

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V -0.6....--.....--......---"""""---------.....- 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:= 0.2 8~ ~~ ~ ~ 0.0 L.--"~+- ---+---------l o~ -0.2 I---",,----::o~=---~f__----I Z I ~ -0.4 I-----+---~>-----I-----~---_t_--______l ~ I -0.6 10-__...... .....__.......__.-.1 ....1..__.-.1 96 % NOMINAL DECAY HEAT RATE FIGURE 6.2-34 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO DECAY HEAT RATE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 0.6...-------,----r-----,-------,-------,--------, 108 106 104 102 100 98 Z 0.4 Z ~ z:= 0.2 8~ ~~ ~ ~ 0.0 L.--"~+- ---+---------l o~ -0.2 I---",,----::o~=---~f__----I Z I ~ -0.4 I-----+---~>-----I-----~---_t_--______l ~ I -0.6 10-__...... .....__.......__.-.1 ....1..__.-.1 96 % NOMINAL DECAY HEAT RATE FIGURE 6.2-34 SENSITIVITY OF PEAK CONTAINMENT PRESSURE TO DECAY HEAT RATE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

115 110 105 100 95 90 ~ 0.04...------,"'..------,----.---------.-----.--------, ~ I ~ 0.02 ~--+--~~--+-----+-----I--------l Z= 0'" u!:. ~w ~ GIl: 0.0 ~ w=>> Zw _GIl: w ~ -0.02 1----+------f---+----3k~,-----+------I -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 8TATION UPDATED SAFETY ANALYSIS REPORT 115 110 105 100 95 90 ~ 0.04...------,"'..------,----.---------.-----.--------, ~ I ~ 0.02 ~--+--~~--+-----+-----I--------l Z= 0'" u!:. ~w ~ GIl: 0.0 ~ w=>> Zw _GIl: w ~ -0.02 1----+------f---+----3k~,-----+------I -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 8TATION UPDATED SAFETY ANALYSIS REPORT

0.15 to-Z LI.I ~ 0.1 to-_ ZV; o A. 0.05 I-----t---~"',--------+----+---+-------l u-LI.I ~~ 4(::) LI.I vt A. ~ 0.0 I----+----f-----:'lk----+---+----l Z~ ~ -A.o ~ g -0.05 1-----t-----+---+_----+~,,~--+--~---1 -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 0.15 to-Z LI.I ~ 0.1 to-_ ZV; o A. 0.05 I-----t---~"',--------+----+---+-------l u-LI.I ~~ 4(::) LI.I vt A. ~ 0.0 I----+----f-----:'lk----+---+----l Z~ ~ -A.o ~ g -0.05 1-----t-----+---+_----+~,,~--+--~---1 -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

Q. 10 r-IoU Ol: 8 ~ NO HEAT SINK AREA IoU 4*....-...-. Ol: ~ Q. 6 100% HEAT SINK AREA Zw ~ 4 ~ Z-ce .....z 2 ~ 0 V ~ I 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 5TATION UPDATED SAFETY ANALYSIS REPORT Q. 10 r-IoU Ol: 8 ~ NO HEAT SINK AREA IoU 4*....-...-. Ol: ~ Q. 6 100% HEAT SINK AREA Zw ~ 4 ~ Z-ce .....z 2 ~ 0 V ~ I 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 5TATION UPDATED SAFETY ANALYSIS REPORT

Cl Z;:: C DC Cl JlI J30 20 L NODE NUMBER (TYP) I J,,- J34 24 J42 ~JUNCTION 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 5TATION UPDATED SAFETY ANALYSIS REPORT Cl Z;::

C DC Cl JlI J30 20 L NODE NUMBER (TYP) I J,,- J34 24 J42 ~JUNCTION 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 5TATION UPDATED SAFETY ANALYSIS REPORT

55 1------------4------------+--------1 26,27 45 -e( en ~ 35 w eM: 27,26 j en en iW eM: ~ 25 7 15 ~~~5~!!!!I!!!!!!!!!!!!!!f!:..~~..::~.1_J_L...L..L..1L _ __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( en ~ 35 w eM: 27,26 j en en iW eM: ~ 25 7 15 ~~~5~!!!!I!!!!!!!!!!!!!!f!:..~~..::~.1_J_L...L..L..1L _ __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-P2S) A. 30 ~... Z ill ~ 20 ill........ Q ill ~

)

10 ill ~ A. 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 5lAliON UPDATED SAFETY ANALYSIS REPORT 40---------------,-----------,-------------, I Q ../(P27-P2S) A. 30 ~... Z ill ~ 20 ill........ Q ill ~

)

10 ill ~ A. 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 5lAliON UPDATED SAFETY ANALYSIS REPORT

20.71' 22 J40 J8 J6 11 10 J4 J2 20 18 J36 C)z... c( C) l ~aC~~C~~~~~~~~~~~~~~~~~~~~~~~~~~~C~_~~EL 11~3r 1--~~~19~-+-~-J.~-+~.........~-+-~-+-~-+-~-,-~+-~....J_3_3~~_2_J~-+-~--lt6'29' EL 110' J38 J28 J30 J32 J34 J42 ~ 9R 24 ~UU~~~~N 'NODE NUMBER I ......~~~~~~~~~~..l{T.:...Y:...:P...!.)~~.......~ .:..{T_Y_P.:..)---.......--.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 5TATION UPDATED SAFETY ANALYSIS REPORT 20.71' 22 J40 J8 J6 11 10 J4 J2 20 18 J36 C)z... c( C) l ~aC~~C~~~~~~~~~~~~~~~~~~~~~~~~~~~C~_~~EL 11~3r 1--~~~19~-+-~-J.~-+~.........~-+-~-+-~-+-~-,-~+-~....J_3_3~~_2_J~-+-~--lt6'29' EL 110' J38 J28 J30 J32 J34 J42 ~ 9R 24 ~UU~~~~N 'NODE NUMBER I ......~~~~~~~~~~..l{T.:...Y:...:P...!.)~~.......~ .:..{T_Y_P.:..)---.......--.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 5TATION UPDATED SAFETY ANALYSIS REPORT

35 ~----------+-----------+---------I 2 3 4 5 6 7 89 10-1 6 """-__~~.2,3 ~f/III(i-~~1,4 --C~--~ 5,8 2 3 4 5 6 789 10-2 2 15....__"----.l.....'""'-.................&...........__......_..L........L..........."""-I..I",j.....__..........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 5TATION UPDATED SAFETY ANALYSIS REPORT 35 ~----------+-----------+---------I 2 3 4 5 6 7 89 10-1 6 """-__~~.2,3 ~f/III(i-~~1,4 --C~--~ 5,8 2 3 4 5 6 789 10-2 2 15....__"----.l.....'""'-.................&...........__......_..L........L..........."""-I..I",j.....__..........I 10-3 ~ ~ Yo! ~

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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 5TATION 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'- f--t-++-f---f-~+-f---+--I----+--J--.l--+-+--I---+-+-":---I 13 14 15 16 17 18 LODE NUMBER (TYP) EL 100.67'- ~---:-::~---l.:-------:,I:-:---_.l-_-_.l-_---'. 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

TI N I RAM RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT 24 19 F EL 137'- f--t-++-f---f-~+-f---+--I----+--J--.l--+-+--I---+-+-":---I 13 14 15 16 17 18 LODE NUMBER (TYP) EL 100.67'- ~---:-::~---l.:-------:,I:-:---_.l-_-_.l-_---'. 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

TI N I RAM RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT

50.----------~------.,---------.-----------. 45 t-------+--------+--------+-----------J 401--------+-------+----------+----------1 35 <C( iii e:.... 30 ~

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~ Q. 25 20 15 J====::~~~~~~~--=-~-----\\lC-----~-------J 10 ~------"'--------.....------~------...J 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 ~

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~ Q. 25 20 15 J====::~~~~~~~--=-~-----\\lC-----~-------J 10 ~------"'--------.....------~------...J 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 ~

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en en &U ~ A. 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 &U ~ A. 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) 101 FIGURE 6.2-45c NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT 50 45 40 35 25 20 15 I J/ A / ~ ~/ "~-V 10-1 TIME AFTER BREAK (SEC) 101 FIGURE 6.2-45c NODAL PRESSURES RECIRCULATION OUTLET LINE BREAK RPV-SHIELD WALL ANNULUS 26 NODE HALF MODEL RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT

10' 10-1 TIME AFTER BREAK (SEC) I/ 8h A ~ ~ ~d ~ ~ .~ 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/ 8h A ~ ~ ~d ~ ~ .~ 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 ~------+__------+__-----_+/+__-----____l ~ " ~------+--------+------#/_--+----------I 12r-£\\6 ~ 20 ~------+__---~t__-+__-~c-----+__---------l 19~ ~:7 ~/ ~ '0/ 151===========~~;;;;;;;;=~_~~~~~~-----1_-----_J 101 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 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 ~------+__------+__-----_+/+__-----____l ~ " ~------+--------+------#/_--+----------I 12r-£\\6 ~ 20 ~------+__---~t__-+__-~c-----+__---------l 19~ ~:7 ~/ ~ '0/ 151===========~~;;;;;;;;=~_~~~~~~-----1_-----_J 101 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 NODE HALF MODEL RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

PI - P 14 10' 3S r---------,----------,.--------r----------, 30 1---------+--------+--------+----------; 2S 1---------+--------+--------+----------; o 'It ... 20 1---------+--------+--------+----------; ~

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'It 'It... lS 1---------+--------+--------+----------; ~ ~z 10 I-----~--I-__>rw--------+--------+----------; o Sr----r-----~___t\\_~--______:=___-__t-------_+_------_____i OI---------\\t-~!l\\__~_N_~=JL..3M_A_~fI!!!!!!S'=----+_------___j -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 STATION UPDATED SAFETY ANALYSIS REPORT PI - P 14 10' 3S r---------,----------,.--------r----------, 30 1---------+--------+--------+----------; 2S 1---------+--------+--------+----------; o 'It ... 20 1---------+--------+--------+----------; ~

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'It 'It... lS 1---------+--------+--------+----------; ~ ~z 10 I-----~--I-__>rw--------+--------+----------; o Sr----r-----~___t\\_~--______:=___-__t-------_+_------_____i OI---------\\t-~!l\\__~_N_~=JL..3M_A_~fI!!!!!!S'=----+_------___j -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 STATION UPDATED SAFETY ANALYSIS REPORT

CD DRYWELL HEAD

DRYWELL 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 HEAD

DRYWELL 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 JDR~~ 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 December 1999 28 26 24-r ~ 22 I ~-=20 I "t "t 18 Y.I M ~ '6 14 12 0.00 ,DRYWELL HEAD r JDR~~ 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 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 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

14.0 14.5 15.0 15.5 16.0 16.5 17.0 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Time 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 -0.5 0.0 0.5 1.0 1.5 2.0 0.0 0.5 1.0 1.5 2.0 2.5 Time 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-900 EL-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 25 0 10 20 30 40 50 60 70 80 90 100 Time 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

CONTAINMENT ~ VESSEL 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 CONTAINMENT ~ VESSEL 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 ~--t~t----~--EL 98'-0" ~ -++--~""'d--EL 83'-0" CONTAINMENT VESSEL RHR RETURN LINE (TYP.) DRYWELL WALL ]::::=====~:::::=:==:-:::t=t==1--~<"I--HW L EL 90' -0" (LWL EL 89'-6") s;;;".,;;;,...::.L..---l~;;;"":;:;';;1...- '''''''_---L~_ EL 70'-0" SUPPRESSION POOL LEVEL WEIR EL 91'-3"-- WALL RHR SUCTION (TYP) FIGURE 6.2-57 RHR SUPPRESSION POOL COOLING MODE SUCTION AND RETURN (SECTION 1-1) RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT SHIELD BLDG ~--t~t----~--EL 98'-0" ~ -++--~""'d--EL 83'-0" CONTAINMENT VESSEL RHR RETURN LINE (TYP.) DRYWELL WALL ]::::=====~:::::=:==:-:::t=t==1--~<"I--HW L EL 90' -0" (LWL EL 89'-6") s;;;".,;;;,...::.L..---l~;;;"":;:;';;1...- '''''''_---L~_ EL 70'-0" SUPPRESSION POOL LEVEL WEIR EL 91'-3"-- WALL RHR SUCTION (TYP) FIGURE 6.2-57 RHR SUPPRESSION POOL COOLING MODE SUCTION AND RETURN (SECTION 1-1) RIVER BEND 5TATION UPDATED SAFETY ANALYSIS REPORT

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~ STATIC I-Z EFFICIENCY Z &II IlIII: V &II &II IlIII: ~ &II IlIII: Q. 0 a12 60;- 30 e; loY V IlIII: Z IlIII: Q. loY 0 U ~ ~ I- ~ 8 40 &II 20 4,000 8,000 12,000 16,000 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 5TATION UPDATED SAFETY ANALYSIS REPORT

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~ 2 ~ ~ 1 ~ ~ ~ VI 0 i--~f_------------------------.::~ ~

-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 ANALYSIS REPORT REVISION 13 SEPTEMBER 2000

REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PRESSURE IN AUXILIARY BUILDING VS TIME FIGURE 6.2-61b

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PRESSURE IN FUEL BUILDING VS TIME FIGURE 6.2-62 REVISION 14 SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED

MAIN STEAM lEFF! MAIN STEAM IEFF) MAIN STEAM (EfF, \\ ~lu*ncs ~'ll" ,c., ~ TURIINE PLANTS MISe. I DIAINS (IFf) 10" 0- ~*.. I .. 1~(**1~ a"~ r-':"_.J.. t:>I::f-l-+ ._,*__';"_-CM~....,r-'~ Rill *STEAM SUPPLY AND .~. ",.~!~...~ ReIC SlEAM SUPPLY \\ffF) r;~" tc;;\\ S<-2~ EP~..."CS I'-~C" .!f fooJ f I ~ 1---~--";"--P*-I~"!----,"*~-~--i1*---7-----;---7-1....a. ,\\lAIN STEAM (lffl f-d. !a Ill'U sc.J:.:J ~ REACtOR VESSEL 10" 1'2" 20" 12" 10" 10" SPAAGU IN REFUELING C - CAVITT

.....__.>------~_,

0=-:\\~~" OM CONOENS"TI .....K(UP' AHO ..~iWOF~TS l~~~ 10" 10" nEOWATER....-----Cl' ~Mc:l_-_, (INF) IlIlR RnURN TO lC'2~ FHDWATER IINFI I.' FiEDWATER ~ (INfl LPCS UNf! ~~.*. 'C.2~SC.1 LPCI *A' (lNf) c;'J~ to** CRD SYSTEM ~@~.' SUPPLY (lNp) r NNS--t+-SC** RHR HEAO SPRAY llNFl c.a SC-2 -'---- SC-l ~ I=;l

roo-J.

RelC HEAD SHAY IINF}...._~.J....iI~""M ...~I""':(4i'--..;L+'-Q. §3H"C**-!-sc., 6" I SC-2";"" SC-l ~ I.' ru'I ~

.....-:::---....... ~ ~ ~

~* RWCU y O. RnURN 'C.,-fl(*1 IEFf) .'] UACTOR WAUR ~ CliANUP PUMP SUCTION (Uff SC**--l.- SC*1 IHI SKUTIlOWN c;'J~ 1." COOLING SUPPLY (fff) $e.; --J.-IC.I SAM'U _9!!E lr... E '~(,.~ :J t: ~ I~~!, ~ 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" ~,E?~ SYSI 10" ~ ~ ~ HPCS (INfl II sc.a-.t-K-' f 10" ~ .~ 10" ~ LPCl 'I' IINF) ed-r-sc~ 10" ~93~ l 10" ~ ~.......c** LPCI 'C' (lNfl ~~ UACTOR IECIllCULATION PUMP I fl] L/--...JC"=':-----..:.::.--H~1-CRD INSUT AND r;- ':1.. .~ WITHDIAW UNES (TYpl ",__...,~.SC_" ..;."_.__....C"'..:Lool("'~ {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 INfLUENT HPCS HIGH PRESSURE CORE SPlAY Eff EFFLUE!'!T RCIC IUCTOR CORE ISOlATION COOLING E>I<:I HAND VALVE III ~ ORIFICE I EXCUS flOW VALVE I IMPINGEMlN~ 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 CRITERION 55-CONTAINMENT ISOLATION VALVES REVISION 12 DECEMBER 1999 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

L-![>6c:}- SPC RETURN (EFT) HPCS TEST RETURN (INF) 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 (INf) 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) ~:---=--_~A 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 ~4=---f>f4.---I_[>6c:}--{>CKl--.. SPC RETURN (EFF) ([I.....:.;;-...., DRYWEll SAMPLE (TYP, OF 2) SUPPRESSION I'OOL TO CONTAINMENT TO fLOOR CONTAINMENT DRAIN EQUII'MENT SUMP DRAIN SUMP-Jd RHR..... SUCTION THEilMAL 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 (INF) 2"" LPCI..... DISCHAIGE RELIEF (INf) CONTAINMENT LI'C1 "C'" DISCHAIGE RElIEf (INF) HYDILOGEN MIXING.1 fM\\ fM\\t } RHRSTEAMCONDENSING SYSTEM -~ J~~~~~....!:-"'::==-:- TIiERMAL RELIEF .. IHI HEAT EXCHANGEI..... VENT (lNF) ...._~---t::Jo--...........~ 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, :~---J'SC2~~~~Ha 20'm )4'* 3" 10'* '.'/2" _.......:.:...._~_~_~12 LPCS PUMP DISCHARGE (lNF) CONTAINMENT AND DRY WEll PURGE SUPI'LY (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, CONDENSA~~l4-RELIEF {INF) 6 ~. L--~!::==::'--!:..--l 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 PURIFICAliON 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 VALVE LC. 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. ~ Ed

ITl ~ 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

REVISION 24

NOTES: EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. 1. 600 CFM CPM

MOV 2B(BB) 4B(BB)

DRB

Z 57A DRB
Z 57B ELEV. 128'-0" AZ. 326 600 CFM CPM
MOV 4A(AR) 2A(AR) 106 ELEV. 114'-0" AZ. 170 AUX. BLDG.

ELEV. 135'-0" AZ. 34 V3000 101 V1 FC PURGE FAN FN1 30 CFM (MAX) 6 CFM (MIN) LMC V6 30 CFM (MAX) 6 CFM (MIN) SYSTEM TITLE SYS NO. REFERENCES 121 403 AIR SERVICE & BREATHING HVAC-CONTAINMENT BUILDING

MOV 104(ZB)

FV 103 FE 103 PI 2 ELEV. 141'-0" AZ. 318 CONTAINMENT DRYWELL HYDROGEN MIXING 600 CFM (MAX) CPM*FN1A(AR) DRB

Z 58A DRB
Z 58B CPM
MOV 3A(AR)

ELEV. 162'-0" AZ. 50 CONTAINMENT 600 CFM (MAX)

V3(Z-)

FC

V2(Z-)

LMC LC

V4(Z-)

LMC V5 CPM*FN1B(BB)

SOV 140 (ZR)

FI 2 3B(BB) 1B(BB) ELEV. 162'-0" AZ. 225

MOV 105 (ZR)

ELEV. 155'-0" AZ. 318 CONTAINMENT ANNULUS DWG NO. 9.3-2c(C-21) 9.3-2 9.4-7 9.4-7b(D-12) 9.4-7b(M-16) 9.4-7b(M-15) 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. 1A(AR) 3. 4. LC LC LC FIGURE SYSTEM P&ID 27-21A REVISION 1 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 6.2-66 254 HYDROGEN MIXING PURGE & RECOMBINER AUGUST 1988 P0207 L 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 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 2. THE DASH (-) IN THE SYSTEM PREFIX IS REPLACED BY AN ASTERISK (*) WHERE THE INSTRUMENT, VALVE, OR EQUIPMENT IS PART OF A NUCLEAR SAFETY RELATED SYSTEM. ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "CPP-"

MOV CPM
MOV CPM
MOV CPM
MOV CPM
MOV 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 6.2-68 REVISION 20

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT HYDROGEN GENERATION FROM ALL SOURCES VS TIME AFTER LOCA FIGURE 6.2-69 REVISION 14 SEPTEMBER 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 -H--4-+---1'X1-~ ~i .-----:.:.:.~.;.~ ..-..\\..,~.A ..._i.1>-~,::::.::~,~-.:....*.*...j::::I J~=====:;~I' r::::J~:,..,_.!."'.*.:.'.*.L-

.:...---""::,,,,,,,,;;,,,,,,,,:~,.J.,:~~.,j

-~. r I U U I~' 'ti~t~ HYDROGEN ANALYZER SYSTEM ~ H,@- -§H2 FIGURE 6.2-71 ~~~~~ I c: 7i A ..9. "O~* 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 DETAILS 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 DETAILS OF PERSONNEL LOCK FOR PERIODIC TESTING RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

25

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 UPOATED 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 UPOATED 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 5TATION 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 5TATION 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 0 ~ LL 0 ~ 2 1.0 2 3456789 10° 2 3 4 5 6789 10-1 0.._ 1-_ _1- °.0 2 3 4 5 6789 10.2 FIGURE 6.2-75 FORCE AND MOMENT TRANSIENTS FOR THE SHIELD WALL RIVER BEND 8TATION 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 0 ~ LL 0 ~ 2 1.0 2 3456789 10° 2 3 4 5 6789 10-1 0.._ 1-_ _1- °.0 2 3 4 5 6789 10.2 FIGURE 6.2-75 FORCE AND MOMENT TRANSIENTS FOR THE SHIELD WALL RIVER BEND 8TATION UPDATED SAFETY ANALYSIS REPORT

6....-------------------------.. 3.0 5 2.5 .5 1 4 FORCE (25 NODE) 2.0 U; A-U; 52 A-II-52 ~ N MOMENT (27 NODE) 0 0 3 1.5 ~ ~ I-W Z 0 W cz: MOMENT (25 NODE) ~ 0 ~ 0 ~ 2 1.0 o..-~2-~3~4~5~6~7~8~9...- ....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 5TATION UPDATED SAFETY ANALYSIS REPORT 6....-------------------------.. 3.0 5 2.5 .5 1 4 FORCE (25 NODE) 2.0 U; A-U; 52 A-II-52 ~ N MOMENT (27 NODE) 0 0 3 1.5 ~ ~ I-W Z 0 W cz: MOMENT (25 NODE) ~ 0 ~ 0 ~ 2 1.0 o..-~2-~3~4~5~6~7~8~9...- ....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 5TATION UPDATED SAFETY ANALYSIS REPORT

PUMP E22*RO D003 (J-) E22*VF033(J-) E22*RV F014 (J-)

V70 (J-)

T/C 139 T/C 140 SET AT 100 PSIG LC LMC V52(J-) E22 MOV F015 (JO) LMC E22*VF017(J-) E22*VF016(J-) E22 -VF025 E22

VF019 (J-)

2 KJB

Z 8

SUPPRESSION POOL MIN. DIST.

STR1 (J-)

KJB

Z 11 S

HIGH PRESSURE CORE SPRAY PUMP

FE 126 (J-)
V63 (J-)

DISCHARGE LINE FILL JPB-RAK7 E22* VF034 (J-)

V11 (J-)

JPB-RAK7 PI 127 PDI 104 T

V200 (J-)

(J-) PE E22

PC003 (JO)
STRT-2 E22*RO D001 (J-)

MIN. FLOW BY PASS VALVE E22*FT N005 (JO) H22*PNLP024 LC E22*RO D005 (J-) E22*PT N050 (JO)

V13(J-)

H22*PNLP024

V8(J-)
V39 (J-)
V40 (J-)

E22

VF006 (J-)
V12 (J-)

JPB-RAK7

V64(J-)

FI 126 E22

VF007 (J-)

E22* MOV F023 (JO) E22* MOV F012 (JO)

V302(J-)

LMC V SYSTEM TITLE SYS NO. LMC LC

RO 200 (J-)

(J-) H22*PNLP009 E22*LT N055C (JO) E22*LT N055G (JO) 051 DRB

Z 392

REFERENCES:

(J-) E22 -VF022 (J-) N081 (JO) 204 NOTES: 209 609 795E830, THIS IS A GENERAL ELECTRIC SYSTEM. NUCLEAR BOILER INSTRUMENTATION RESIDUAL HEAT REMOVAL-LPCI REACTOR CORE ISOLATION COOLING DRAINS-FLOOR & EQUIPMENT HOSE *6(J-) ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "CSH-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN. THIS DRAWING HAS BEEN REDRAWN FROM GENERAL ELECTRIC CO. DRAWING (Z-) REVD003

V28 E31*PDT 6.

E51*LT N035A (-R) E51*LT N035E (-R) E22*PT N052 (JO)

V3(J-)

E22*PI R001 (J-) E22* MOV F001 (JO) E22* VF002 (J-)

V2(J-)

E22

PC001 (JO)

E22*PT N051 (JO) PIPE TUNNEL AUX. BLDG

V18(J-)
V19(J-)

"LOCAL RACK" "LOCAL RACK" MIN. DIST. CSH*TW 102 (J-) STRT-1

V6(J-)

E22*RV F035 (J-) E22* VF026 (J-) E22* VF024 (J-) E22*FT N056 (JO) H22*PNLP024 E22-MOV F004

VF003 (J-)
VF031 (J-)

FLUSHING WATER SUPPLY 2 MIN. DIST. E22*RO DOO2 (J-) MAIN ISOLATION VALVE E22* MOV F010 (JO) SET AT E22*FE N007 (J-)

V22 (J-)
V24 (J-)

KJB

Z 9

DRB

Z 10 E22*

AOV FOO5 (JO) 2 E22* VF036 E22 -VF021 B13* VESSEL REACTOR (JO) LO CONDENSATE STORAGE TANK E22*LT N054G (JO) E22*LT NO54C (JO) LO V1 V20 T AUX. BLDG. TUNNEL AUX. BLDG. E22* VF032(J-) LO YARD RESERVE 125,000 GAL. SEE NOTE 10 CNS-TK1 PE

V17(J-)
V16(J-)

2 3 3 2 E22*RO D004 (J-)

V26 (J-)
V27 (J-)

E22*PI R002 (J-) H22*PNLP024 MOV FO11 (JO) E22*RV FO39 (J-) AUXILIARY BLDG SHIELD BLDG SET AT 1560 PSIG E22* CONTAINMENT DRYWELL 5.4-12b(A-15) 9.3-7p(D-11) DWG NO. 5.1-3 5.4-12 5.4-8 9.3-7 5.4-8(C-13) 5.4-8(L-4) VALVE POSITIONS DEPICT THE PLANT IN ITS NORMAL OPERATING MODE AND ARE FOR 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. INFORMATION ONLY. CONSULT THE STATION OPERATING PROCEDURES (SOP'S) FOR ACTUAL VALVE LINEUPS. 1560 PSIG PIPE CAPS USED ON VENT, DRAIN, AND TEST CONNECTIONS THAT ARE NORMALLY ISOLATED 5. 1 1 5.1-3a (D-21) E22* ZT N008 (J0) E22* ZT N010 (JO) FIGURE SYSTEM P&ID REVISION 23 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 6.3-1 203 HPCS SYSTEM 27-4A P0023 NOTE 7 THE AIR ACTUATOR ON VALVE E22*AOVF005 HAS BEEN DISCONNECTED IN THE FIELD BY REMOVING THE LEVER ARM. 7. E22 E22 SEE NOTE 8 SEE NOTE 8 E22*ZTN008, E22*ZIR606, E22*ZIR604, AND E22*ZTN010 ARE NON-SAFETY RELATED DEVICES CONNECTED TO 1E POWER. THE "*"S REFLECT THE QC INSPECTION REQUIREMENT. 8.

LY 3G (J-)

(J-) 3C

LY (JO)

LO V3008 L 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 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 2. THE ASTERISK "*" WAS USED IN A PREVIOUS EQUIPMENT IDENTIFICATION SYSTEM AT RIVER BEND STATION. REFER TO THE EQUIPMENT DATA BASE (EDB) FOR THE PROPER COMPONENT NUMBER AND SAFETY CLASSIFICATION. NUCLEAR SAFETY RELATED DELETED TEMPORARY STRAINER STRT 1 ELEMENT HAS BEEN REMOVED. 9. NOTE 9 PE RESERVE VOLUME DELIVERED MAY BE LESS THAN 125,000 GALLONS. 10. 1. 3. 4. FOR PUMP DRAINS SEE FIG 9.3-7k(G-18) NOTE: SEE FIG 9.3-7k(F-12) FOR PUMP DRAIN NOTE:

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 0 ~ l.L ~ J: Vl 0-Z BHP AT SPECIFIC GRAVITY = 1.0 (TYPICAL TEST) a: UJ ~o 3000 fu l/la:o

I:

2000 w:.: <{ a: o L--__.L... ..L-__~~---.J----~~---'---~ 1000 lD o 1000 5000 6000 7000 5001------- NPSH REOUIRED AT 3 FT. ABOVE MOUNTING FLANGE (TYPICAL TEST) 3000 4500,..------------------------------, 4000 3500 1000 ~ 2500 wJ:...;! 2000 o ~ FLOW 19pml FIGURE 6.3-3 HPCS PUMP CHARACTERISTIC CURVES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 20

-STRT1(J-) 2 2 2

V1 (J-)

SPOOL PIECE SEE NOTE 2

V31 (J-)

E21* VF008 (J-) E21-VF009 S

STR1 (J-)

NO 795E832 REV 0 THIS IS A GENERAL ELECTRIC SYSTEM.

2. SPOOL PIECE SHALL BE INSTALLED ONLY DURING PLANT SHUTDOWN.

204 609 FLOOR AND EQUIPMENT DRAINS NOTES: EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

1. ALL LINE, INSTRUMENT, VALVE AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "CSL-"

4. THIS DRAWING HAS BEEN REDRAWN FROM GENERAL ELECTRIC CO. DRAWING 7.

E21

PI R002 (J-)

E21

RO D003 (J-)

E21

PI R001 (J-)

E21

PT N052 (JR)

E21

PT N053 (JR)
V7(J-)

T

V6(J-)

PE E21* VF034 (J-) E21* VF033 (J-)

V4 (J-)

PI 125 E21

FE N013 (J-)
TW 116 (J-)

E21

RV F031 (J-)

KJB

Z 12 E21*

MOV F001 (JR)

V2 (J-)

DISCHARGE LINE FILL PUMP E21*PC002(JR) PE PE

V40 (J-)

T

STRT 2(J-)

V28(J-) E21* VF032 (J-) E21* VF035 (J-) SUPPRESSION POOL SET AT 100 PSIG TC 130 TC 129 PDI 135 SYSTEM TITLE SYS NO. REFERENCES E21

FE N002 (J-)

E21

RO D004 (J-)

E21

RO D001 (J-)

E21

FT N051 (JR)

E21* MOV F011 (JR) E21* MOV F012 (JR)

V10 (J-)

E21* VF004 (J-) E21* VF003 (J-) H22

PNL P001
V100 (J-)

LMC V E21

RV F018 (J-)
FI 121 (J-)

E21

PT N054 (JR) 2 1
V13 (J-)

E21* VF025 (J-) H22

PNL FLUSHING CONNECTION TO SUPPRESSION POOL SET AT 570 PSIG P001 VF007 (JR)

B13*REV D003(Z-) REACTOR VESSEL E21

FT N003 (JR)
V15 (J-)
V16 (J-)

H22

PNLP001 E21
RO D002 (J-)

DRB

Z 14 E21
PT N050 (JR)

E21* MOV F005 (JR) KJB

Z 13 AUX.

BLDG. CONTAINMENT DRYWELL SHIELD BLDG. WALL H22

PNL P001
V23 (J-)
V20 (J-)

E21* AOV F006 (JR) E21* LO

V36 (J-)

9.3-7k(B-14) 9.3-7k(B-14) 9.3-7k(C-13) 9.3-7k(B-13) 5.4-12a(C-15) 5.4-12a(A-19) 5.4-12 9.3-7 AUX. BLDG. EL. 70'-0" 5.4-12a(F-13) 9.3-7k(C-11) 5.4-12a(B-18) 5.4-12a(D-17) 5.4-12a(P-1) 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. L 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 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 5. 6.

8. THE AIR ACTUATOR ON THIS VALVE HAS BEEN DISCONNECTED IN THE FIELD BY REMOVING THE LEVER ARM.

NOTE 8 FIGURE SYSTEM P&ID REVISION 23 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 6.3-4 205 LPCS 27-5A P0075 L.C.

V38 (J-)
V37
V3 (J-)

RESIDUAL HEAT REMOVAL 9. PRESSURE TRANSMITTER INSTRUMENT VALVES E21-PTN050-V2 AND E21-PTN050-V3 ARE REQUIRED TO BE SEALED CLOSED PER MR96-0013. NOTE 9 FIG NO.

3. THE ASTERISK "*" WAS USED IN A PREVIOUS EQUIPMENT IDENTIFICATION SYSTEM AT RIVER BEND STATION. REFER TO THE EQUIPMENT DATA BASE (EDB) FOR THE PROPER COMPONENT NUMBER AND SAFETY CLASSIFICATION.

NUCLEAR SAFETY RELATED DELETED TEMPORARY STRAINER STRT 1 ELEMENT HAS BEEN REMOVED. 10. NOTE 10

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 1000 ~ I 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 0f-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:...o ~ 1:....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 REPORT NOMINAL AND APPENDIX K LOCA BREAK SPECTRUM RESULTS FOR GE11 FUEL Figure 6.3-10 REVISION 14 SEPTEMBER 2001

FIGURE 6.3-11a GE14 DBA - HPCS-DG FAILURE (APP. K) HOT AND AVERAGE CHANNEL WATER LEVELS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-11b ATRIUM-10 DBA - LPCS-DG FAILURE (APP. K) HOT AND AVERAGE CHANNEL WATER LEVELS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-11c GNF2 DBA - LPCS-DG FAILURE (APP. K) HOT AND AVERAGE CHANNNEL WATER LEVELS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

FIGURE 6.3-12a GE14 DBA - HPCS-DG FAILURE (APP. K) REACTOR VESSEL PRESSURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-12b ATRIUM-10 DBA - LPCS-DG FAILURE (APP. K) REACTOR VESSEL PRESSURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-12c GNF2-10 DBA - LPCS-DG FAILURE (APP. K) REACTOR VESSEL PRESSURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

FIGURE 6.3-13a GE14 DBA - HPCS-DG FAILURE (APP. K) PEAK CLADDING TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-13b ATRIUM-10 DBA - LPCS-DG FAILURE (APP. K) PEAK CLADDING TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-13c GNF2 DBA - LPCS-DG FAILURE (APP. K) PEAK CLADDING TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

FIGURE 6.3-14a GE14 DBA - HPCS-DG FAILURE (APP. K) ECCS FLOW RATE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-14b ATRIUM-10 DBA - LPCS-DG FAILURE (APP. K) ECCS FLOW RATES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-14c GNF2 DBA - LPCS-DG FAILURE (APP. K) ECCS FLOW RATES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

FIGURE 6.3-15a GE14 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) HOT AND AVERAGE CHANNEL WATER LEVELS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-15b ATRIUM-10 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) HOT AND AVERAGE CHANNEL WATER LEVELS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-15c GNF2 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) HOT AND AVERAGE CHANNEL WATER LEVELS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

FIGURE 6.3-16a GE14 0.05 FT2 - HPCS-DG FAILURE (APP. K) REACTOR VESSEL PRESSURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-16b ATRIUM-10 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) REACTOR VESSEL PRESSURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-16c GNF2 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) REACTOR VESSEL PRESSURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

FIGURE 6.3-17a GE14 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) PEAK CLADDING TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-17b ATRIUM-10 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) PEAK CLADDING TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-17c GNF2 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) PEAK CLADDING TEMPERATURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

FIGURE 6.3-18a GE14 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) ECCS FLOW RATE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-18b ATRIUM-10 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) ECCS FLOW RATES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT THIS FIGURE HAS BEEN DELETED.

FIGURE 6.3-18c GNF2 0.05 FT2 BREAK - HPCS-DG FAILURE (APP. K) ECCS FLOW RATES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 22

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 8TATION 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 SlAliON 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 8TATION 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 8TATION 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 REPORT TYPICAL CORE AVERAGE PRESSURE VERSUS TIME AFTER BREAK Figure 6.3-37 REVISION 14 SEPTEMBER 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 STATION UPDATED SAFETY 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 2 1 1 2 ~ ~ 2850 f FT. 102 k FT 2900 f FT 177 a F T @ 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 FIGURE 6.4-2 MAIN CONTROL ROOM PRESSURE BOUNDARY REVISION 21

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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. L 20 19 18 17 16 15 14 13 12 11 8 7 6 5 4 3 2 1 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 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 REVISION 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) 208 6.7-1 MSIV 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 (EDB) 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

L 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 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 PER MR92-0087 FCN4. NOTE 5

V3032A FIGURE SYSTEM P&ID 27-20C

REVISION UPDATED 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 AT RIVER BEND STATION. REFER TO THE E48,30(NT DATA BASE ((DB) FOR THE PROPER COMPONENT 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

L 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 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 6.7-1b (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. 9ALVE 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 27-20D

REVISION UPDATED 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}}

ML17226A135

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