ML17226A131

From kanterella
Jump to navigation Jump to search
5 to the Updated Safety Analysis Report, Section 5, Figures 5.1-1 Through 5.4-18
ML17226A131
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:
References
RBG-47776, RBF1-17-0089
Download: ML17226A131 (57)
v • d • e


Text

PRESSURE tps*al

1. CORE IN~ET 1075
2. CORE OUTLET 1050 3 SEPARATOR OUTLET !STEAM DOME!

1040

4. STEAM LINE !2ND ISOLATION VALVE!

985

~. FEEOWATER IN~ET IJNCLUDES CLEANUP 1065 RETURN F~OWJ 6

RECIRCULATION PUMP SUCTION 1040 7 RECIRCULATION PUMP DISCHARGE 1310 STEAM DRYERS DRIVING FLOW-------

PUMP

~FLOW CONTROL VALVE F~OW llb/hrl 84.5. !06 84.5. 106 12.45 X 106 12.45 X 106 12.55 X 106 24.6 X 106 24.6 x to" TEMPERATURE ENTHA~Pv (OF I

!Btu/It>)

533 527.8 551 644.7 549 1190.8 543 1190.8 420 397.8 533 527.6 534 528.8 MAIN FEED FLOW FROM TURBINE FIGURE 5.1-1 INITIAL CORE RATED OPERATING CONDITIONS OF THE BOILING WATER REACTOR RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 17

A. l.OWER PLENUM B. CORE C. UPPER PlENUM AND SEPARATORS I

0. DOME lABOVE NORMAL WATER LEVELl E. OOWNCOMEA REGION F RECIAC LOOPS AND JET PUMPS STEAM SEPARATORS DRIVING FLO~'. ---

PUMP VOLUME OFF LUID lftll 33\\0 1680 1990 4780

~----------*-

3400 780 MAIN FEED FLOW FROM TURBINE

~=====<.)

VALVE FIGURE 5.1-2 COOLANT VOLUMES OF THE BOILING WA TEA REACTOR RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

25

AND STEAM CONDITIONS AT 0 PSIG IN THE VESSEL AND THE DRYWELL WITH NO JET PUMP FLOW.

ABOVE WATER LEVEL NOZZLE WITH NO JET PUMP FLOW.

C. NARROW RANGE: (SAFEGAURDS & FEEDWATER): THE INSTRUMENTS ARE D. UPSET RANGE: THE INSTRUMENT IS CALIBRATED FOR SATURATED WATER THE DRYWELL.

B. WIDE RANGE: THE INSTRUMENTS ARE CALIBRATED FOR 1055 PSIG IN THE MIDDLE WATER LEVEL NOZZLE AND SATURATED WATER AND STEAM CONDITIONS CALIBRATED FOR SATURATED WATER AND STEAM CONDITIONS AT 1055 PSIG 2

3 4

2 3

4 PS N676B NS NS NS NS NS NS NS NS CORE PLATE POST ACCIDENT MONITORING PIS N675D PIS N675C PIS N675B PIS N675A PIS N676D PIS N676C PIS N676A 2

POST ACCIDENT MONITORING

  • dPT N032 2

4 3

2 4

3 2

dP 4

4 4

4 4

4 4

4 4

2 PRESS PERM PS N697F PS N698F RHR(B) RHR(C)

NS =NUCLEAR STEAM SUPPLY SHUTOFF (CONTAINMENT ISOLATION) FUNCTION JET PUMP DIFFUSER TAP JET PUMP INTRUMENT NOZZLE 149.0" 159.2"

  • FUNCTION IS IN FEEDWATER CONTROL SYSTEM FOR LOSS OF ONE FEED PUMP NOTES:

WHERE A DIFFERENT PREFIX IS SHOWN.

A. FUEL ZONE: THE INSTRUMENTS ARE CALIBRATED FOR SATURATED WATER

1. ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT TO BE PREFIXED WITH "B21-" EXCEPT
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.
3. WATER LEVEL INSTRUMENTS FOR VARIOUS RANGES ARE CALIBRATED AS STATED BELOW.

ALL WATER LEVEL SWITCH SET POINTS ARE NORMAL: I.E., THE ANALYSES ARE PER-FORMED WITH THE SWITCH TRIP UNCERTAINTY INCLUDED. THE CONTAINMENT BUILDING

  • PT N058E 2

2 3

3 4

4 2

2 3

3 3

3 2

2 RECIRC (B)

RECIRC (B)

RECIRC (A)

HPCS HPCS HPCS HPCS RHR(A)/LPCS/RCIC/ADS(A)

RHR(A)/LPCS/ADS(A)

RHR(B)/RHR(C)/RCIC/ADS(B)

RHR(B)/RHR(C)/ADS(B) 2 2

2 2

2 2

2 2

2 2

PS N669B PS N670B PS N617B PS N618B PS N669E PS N670E PS N616E PS N618E PS N669F PS N670F PS N616F PS N618F PRESS RELIEF PRESS RELIEF PRESS RELIEF REOPEN/RECLOSE (MID)

REOPEN/RECLOSE (HIGH)

PRESS RELIEF PRESS RELIEF PRESS RELIEF REOPEN/RECLOSE (LOW)

REOPEN/RECLOSE (HIGH)

PRESS RELIEF PRESS RELIEF PRESS RELIEF REOPEN/RECLOSE (LOW)

REOPEN/RECLOSE (HIGH)

PRESS RELIEF PRESS RELIEF PRESS RELIEF REOPEN/RECLOSE (LOW)

REOPEN/RECLOSE (HIGH)

PIS N658B PIS N658F PIS N667C PIS N667G PIS N667L PIS N667R PIS N694A PIS N694E PIS N694B PIS N694F PIS N668A PS N669A PS N670A PS N617A PS N618A

  • PT N068E 2
  • PT N068A 2
  • PT N068F LOW LOW SET LOW LOW SET LOW LOW SET LOW LOW SET PIS N668F PIS N668E PIS N668B
  • LT N081B
  • LT N091E
  • LT N091F
  • LT N073C
  • LT N073G
  • LT N073L
  • LT N073R
  • LT N081C
  • LT N081D
  • LT N080A
  • LT N080B
  • LT N080C
  • LT N080D
  • LT N099A
  • LT N099E
  • LT N099B
  • LT N099F
  • LT N095A
  • LT N095B
  • LT N081A
    • TRIPS RHR SHUTDOWN ISOLATION VALVES TO CLOSE 1

PS N697A PS N698A PRESS PERM LPCS/ RHR(A) 2 PRESS PERM PRESS PERM PS N697B PS N698B PS N697E PS N698E RHR(B) RHR(C)

LPCS/ RHR(A) 2 2

LIS N681B LS N682B NS (MSIV) 4 2

2 4

4 3

4 3

3 3

3 3

LIS N691E LS N692E LIS N691F LS N692F LIS N673C LS N674C LIS N673G LS N674L NS 3

4 LIS N673L LIS N673R 3

4 LIS N681C LS N682C HPCS NS (MSIV) 4 NS 4 NS (MSIV) 4 NS 4 LIS N681D LS N682D 2

2 LIS N680A LS N683A RPS(A) NS (A)** 4 RPS(A)

RPS(B) NS (B)** 4 RPS(B)

LIS N680B LS N683B RCIC HPCS RCIC ADS(B)/RHR(B)/RHR(C)

HPCS ADS(A)/RHR(A)/LPCS HPCS 3

4 3

HPCS HPCS 4

LIS N680C LS N683C RPS(C) NS (C)** 4 RPS(C)

RPS(D) NS (D)** 4 RPS(D)

LIS N680D LS N683D 2

2 2

8 2

8 2

2 2

2 2

2 3

3 2

2 2

2 3

8 3

8 3

8 3

8 LIS N699A LIS N699E LIS N699B LIS N699F LIS N695A LIS N695B LIS N681A LS N682A 2

2 2

2 INSTRUMENT LINE NOZZLE RECIRC (B)

RECIRC (B)

RECIRC (A)

ADS(A)

ADS(B)

NS (MSIV)

NS RECIRC (A) 586.25" 4

4 BOOSTER PUMPS.

SCRAM.

HIGH LEVEL ALARM NORMAL WATER LEVEL LOW LEVEL ALARM RUN RECIRC FLOW BACK ON FEEDPUMP TRIP.*

SCRAM & CONTRIBUTE TO AUTO DEPRESSUR-IZATION. RUN RECIRC FLOW BACK. CLOSE RHR SHUTDOWN ISOL VALVES.

520.62" INSTRUMENT LINE NOZZLE WATER LEVEL INSTRUMENT ZERO 509.0" INITIATE RCIC & HPCS.

CLOSE PRIMARY SYSTEMS ISOL VALVES EXCEPT MSIV'S & RHR SHUTDOWN ISOL VALVES. TRIP RECIRC PUMPS START DIV 3 STANDBY DIESEL.

INITIATE RHR & LPCS.

CONTRIBUTE TO AUTO DEPRESSURIZATION.

START DIV 1, DIV 2 STANDBY DIESELS.

CLOSE MSIV'S.

TOP OF ACTIVE FUEL 358.56" INSTRUMENT LINE NOZZLE 358.0" TABLE II TABLE II TABLE II 8

51.0" 51.0" 51.0" 38.8" 7

9.7" 9.7" 3

30.8" 4

34.8" 5

0" 0"

0" 0"

0"

-160.0"

-143.0"

-43.0"

-110.0" 2

-310.0"

-162.0" 0"

TRANSMITTER MECH DIV LOC ELEC DIV SYSTEM TRIP UNIT

3 3

2 2

RECIRC (A)

NS (D) (RHR ISOL)

RPS (D)

NS (C) (RHR ISOL)

RPS (C)

NS (B) (RHR ISOL)

RPS (B)

NS (A) (RHR ISOL)

PIS N678A PS N679A PIS N678B PS N679B PIS N678C PS N679C PIS N678D PS N679D PIS N658A PIS N658E 4

4 4

4 TABLE I: PRESSURE INSTRUMENT CONTACT UTILIZATION TRANSMITTER

  • LT N091B
  • LT N091A
  • LT N027
  • LT N044C
  • LT N044D TABLE II: WATER LEVEL INSTRUMENT CONTACT UTILIZATION
  • LT N044E MECH DIV LOC ELEC DIV TRIP UNIT SYSTEM 2

4 LS N693A LS N692A LIS N691A 2

3 2

2 3

LS N693B LS N692B LIS N691B RCIC RCIC ADS(B)/RHR(B)/RHR(C)

RCIC RCIC ADS(A)/RHR(A)/LPCS FUEL ZONE FUEL ZONE SHUTDOWN LEVEL LEVEL TRIP POINT 2

8 2

8 REFERENCE TOP OF HEAD FLANGE (COLD VESSEL)

INCHES ABOVE VESSEL ZERO STEAM LINE NOZZLE 636.5" 842.0" TRIP RCIC TURBINE &

HPCS INJECTION VALVE CLOSURE SIGNAL.

CLOSE MAIN TURBINE STOP VALVES. TRIP FEED PUMPS & CONDENSATE FUEL ZONE DESCRIPTION OF TRIPS INSTRUMENT(S)

PROVIDING TRIP REACTOR VESSEL LEVEL IDENTITY TABLE II FUEL ZONE LR R615 LI R610E,C SAFEGUARDS WIDE RANGE LR/PR R623A,B LI R604 FEEDWATER NARROW RANGE C33/C34 LR R608 C33/C34 LI R606ABC UPSET C33/C34 LR R608 SHUTDOWN LI R605 CONTROL ROOM LEVEL INDICATION AND TRIP LEVELS SEE NOTE 3 180.0" 400.0" 60.0" 60.0" 60.0" TABLE III ELEVATION CORRELATION CHART 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 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 TEMPERATURE ASSUMED TO BE 86.5° F.

VESSEL, 130° F IN THE DRYWELL AND 20 BTU/LB SUB-COOLING BELOW THE IN THE VESSEL AND 130° F IN THE DRYWELL.

AND STEAM CONDITIONS AT 1055 PSIG IN THE VESSEL AND 130° F IN SHUTDOWN: THE INSTRUMENT IS CALIBRATED FOR 120° F WATER AT 0 PSIG VESSEL AND 80° F IN THE DRYWELL.

FIGURE SYSTEM P&ID REVISION 22 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 5.1-3b 051 NUCLEAR BOILER INSTRUMENTATION 25-01B P0148 1

ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "RCS-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

SYSTEM TITLE SYS NO.

REFERENCES:

NOTES:

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 FIGURE SYSTEM P&ID RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 20 5.1-3c 051 REFERENCE LEG BACKFILL SYSTEM 25-1G F

F 1H22*PNLP027 1H22*PNLP004 051 052 NUCLEAR BOILER INSTRUMENTATION CONTROL ROD DRIVE HYDRAULIC 1H22*PNLP005 1H22*PNLP026 1/2" 1/2" 1/2" ALL MANUAL VALVES ARE INSTRUMENT TUBING NEEDLE VALVES.

3.

V3061 V3060A V3059A FLT5A V3060B FLT5B V3059B V3062 V3058B V3058A V3055D V3056D FI 108D D

V3057D V3054D TEST D

  • V3051D TEST D
  • V3049D TEST D
  • V3052D
  • V3050D
  • V3048D
  • V3048B
  • V3050B
  • V3049B V3057B 109B RO V3054B D

TEST D

  • V3051B D

TEST

  • V3052B 108B FI D

TEST V3055B V3056B

  • V3050C
  • V3048C V3057C V3054C D

TEST D

  • V3051C TEST D
  • V3052C 108C FI
  • V3049C TEST D

V3056C V3055C V3057A V3054A D

D TEST 109A RO 108A FI V3056A V3055A

  • V3050A
  • V3049A TEST
  • V3051A TEST D
  • V3052A D
  • V3048A 1/4" 1/4" 1/4" 1/4" V3064A V3064B LC LC LC LC 5.1-3a(H-16) 5.1-3a(H-18) 5.1-3a(E-6) 5.1-3a (J-3) 4.6-5a(D-15)

TEST TEST TEST TEST FIGURE NO.

5.1-3a 4.6-5a ALL LINES ARE UNNUMBERED INSTRUMENT TUBING LINES.

4.

2 2

2 2

V3066A V3066D V3066B V3066C 1/4" 109D RO 1/4" 1/4" RO 109C 1/4" 1.

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.

5.4-8 (J-18) 5.4-8 (H-18)

(J-4)

N-9 209 REACTOR CORE ISOLATION COOLING 5.4-8 RO302 ICS-FI302 ICS-V3020 V3021 ICS-ICS-V3026 1/4" LC V3022 1/4" ICS-ICS-ICS-ICS-V3024 V3023 V3025 LC ICS-RO301 ICS-V3010 ICS-ICS-V3016 1/4" ICS-ICS-V3015 LC ICS-V3014 V3013 V3011 LC ICS-FI301 ICS-1/4" V3012 ICS-H22-PNLP004 V3028 ICS-V3018 ICS-

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT MSIV CLOSURE WITH FLUX SCRAM AND INSTALLED SAFETY/RELIEF VALVE CAPACITY FIGURE 5.2-1 Percent rated power referenced to 3039 MWt.

REVISION 17 TIME (SECONDS)

TIME (SECONDS)

TIME (SECONDS)

TIME (SECONDS)

REACTIVITY COMPONENTS (PERCENT OF RATED)

(VALVE CLOSURE 100 I-CHARACTERISTICS)r-~---

(CODE-APPROVED CAPACITY)

I I

w I

a:

I en en UJa:

80 l-I 0-I-

UJ I

en I-<<

~

>-l-e::><<

0-<<

I o

UJ l-I

..J 60 -

0-UJ I

2:<<z I

UJ>

..J<<

I u.

0 I

~

s:

0 I

..J 40 l-u,

2:

I UJ I-en UJ I

..J<<>

f 20 l-I I

I (0.98 SLOWDOWN OR I RECLOSUREPRESSURE I ONLY TYPICAL)

I I

I I

I I

0 0.96 0.97 0.98 0.99 1.0 1.01 1.02 1.03 1.04 PRESSURE/PRESSURE SETPOINT FIGURE 5.2-2A TYPICAL DUAL SAFETY/RELIEF VALVE CAPACITY CHARACTERISTICS POWER-ACTUATED RELIEF MODE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

100 80 60 40 20 0

CODE APPROVED I

MANUFACTURERS PROBABLE CAPACITY LIFT CHARACTE SSUMED LIFT CHARACTERISTICS

/

/

VALVE CLOSURE /

/

CHARACTER ISTICS

/

/

/

/

/

I I

/

I I

I

- !J I

/

I

/

I 0.98 BLOWDOWN I

OR RECLOSURE PRESS

/ - TYPICAL ONLY I

/

/

I 0.98 0.99 1.o 1.01 1.02 PRESSURE/PRESSURE SETPOINT 1.03 FIGURE 5.2-2B L

TYPICAL DUAL SAFETY/RELIEF VALVE CAPACITY ACTION MODE CHARACTERISTICS-SPRING RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

100 90 80 70 60 50 40 30 20 10 0

SCRAM TIME TECHNICAL SPECIFICATION ROD POSITION TIME

(% INSERTION)

(sec) 1 0.07 + 0.138 = 0.208 10 0.07 + 0.317 = 0.387 40 0.07 + 0.874 = 0.944 75 0.07 + 1.620= 1.690 0

0.5 1.o 1.5 2.0 2.5 3.O 3.5 TIME (sec)

FIGURE 5 - 2 4 CONTROL ROD POSITION VERSUS TIME CHARACTERISTICS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

1450 1400 1350 1300 1250 1200 60 70 90 109.4 115.3 SAFETY VALVE CAPACITY (% NB RATED STEAM FLOW)

I 1

I I

I I

I I

I 1

7 8

9 10 11 12 13 14 15 16 NUMBER OF OPERATING SAFETY VALVES CODE LIMIT = 1375 pstg MSlV CLOSURE -

GENERATOR LOAD REJECTION FIGURE 5.2-4 PEAK VESSEL PRESSURE VERSUS SAFETY/RELIEF CAPACITY RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

1500 1450 1350 1300 1250 1200 1150 1100 1050

\\

MSlV CLOSURE -.

FLUX SCRAM GENERATOR LOAD- \\

REJECTION WITHOUT BYPASS - DIRECT SCRAM \\

0 1

2 3

4 5

6 7

8 TIME (sec)

FIGURE 5.2-5 TIME RESPONSE FOR PRESSURIZATION TRANSIENTS FOR SAFETY/RELIEF CAPACITY SIZING RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

100

-1

-1 I)

U U

0 g?

50

-1 w

3 0

RELIEF V A L V E OPENING CHARACTERISTICS n

0.3-T I M E (set) 100 LL 0 g? -

4 50 1

0 SAFETY V A L V E OPENING CHARACTER I S 1 w

I

'ICS T I M E (sec)

'i FIGURE 5.2-5A POWER ACTUATED AND SAFETY ACTION VALVE LIFT CHARACTERISTICS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

1200 1100 m

8 -

w n cn cn n

1000 900 1056 11 CLOSE 16 OPEN 955 1 REOPENSAT -

1048 psia

-SIGNALED TO CLOSE

- 3 CLOSE

- 0 REOPEN r S l G N A L E D TO CLOSE r

SIGNALED TO CLOSE L

940 0

20 40 TIME (SECS) 60 80 I FIGURE 5.2-5B REACTOR VESSEL PRESSURE FOLLOWING TRANSIENT ISOLATION EVENT I RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

THIS FIGURE HAS BEEN DELETED FtGURE 5.2-6 NUCLEAR BOILER SYSTEM P&ID DATA RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 10 April 1998

7 SAFETYIRELIEF VALVE

/-- -7 FLOW RE STR IC T m L M A t N STEAM LINE FtGURE 5.2-7 STEEL CONTAlNME h;T

/-

WALL MAIN STEAM ISOLATION VALVES DISC HA RG E LINE SUPPRESSION

/--POOL SAFETY/ RELIEF VALVE SCHEMATIC ELEVATION RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

ISOLAl MAIN STEAM LtNES t t t t MAIN S T E A M

'ION VALVES CONTAINMENT W A L 1 J

LL REACTOR VESSEL FIGURE 5.2-8 SAFETYIRELIEF VALVE AND STEAM LINE SCHEMATIC RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

SET PRESSURE ADJUSTING BOLT THRUST BEARING AND AOAPTER UWER WRING WASHER LOWER STRING WASHER PISTON TYPE ACTUATOR ASS L 'f PNEUMATIC BALANCING PISTON SO:.ENOID ANC)

AlFi CONTROL V A L V E ASSEMBLY

411, tNLET tG RING FIGURE 5.2-9 SCHEMATIC OF DUAL-FUNCTION TYPE SPRING-LOADED DIRECT-ACTING SAFETYIRELIEF VALVE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

STEAM SEPARATOR DRYER RECIR PUMP 3

CLEANUP PUMP LOW PRESSURE TURBINE

---+

F EEDWATER I

I I

DRIVES PRESSURE I TURBINE t

I I

I I

GENERATOR T O STEAM JET AIR EJECTOR CONDENSER c

REACTOR WATER CLEANUP NOTE I NUMBERED LOCATIONS CORRESPOND TO TABLE 5.2-4(WATER CHEMISTRY).

NOTE 2 SINGLE CROSS LINES -INDICATE DRYWELL BOUNDARY DOUBLE CROSS LINES =INDICATE CONTAINMENT BOUNDARY T O CONTROL TREATMENT 0-1 YSYSTEM R O D b DRIVES FIGURE 52-10 TYPICAL BWR FLQW DIAGRAM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

c' UY (v

0 I-a W

0 LL 0

u) v)

a.

100 10 1

0.1 0.01 I I

I I

1 I

4 5

6 7

8 pH ( AT 25°C) 9 10 FIGURE 5.2-11 CONDUCTANCE VS pH AS A FUNCTION OF CHLORIDE CONCENTRATION OF AQUEOUS SOLUTION AT 25OC RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

1000 800 600 400 200 1 00 80 60 15 10 8

6 4

2

\\

?O ksi 0 AXIALLY ORIENTED CRACK 0 SATURATED WATER SYSTEM ASTERISKS DENOTE CRACK A T 1000 psig OPENING OF 0.1 in.

1 0

4 8

12 16 20 24 28 32 36 CRACK LENGTH (in.)

FIGURE 5.2-12 CALCULATED LEAK RATE VS CRACK LENGTH AS A FUNCTION OF APPLIED HOOP STRESS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

13 12 t 1 10 9

8 X.

tiL 6

5 DATA CORRELATION l c = CRITICAL CRACK LENGTH (in.)

D = MEAN PIPE DIAMETER Oh = PIPE HOOP STRESS M A T E R I A L. A1064 Vc/D

.t 0

0 1 5,000/0h I

GE DATA (-60°F)

BMI DATA 0

I I

1 I

I I

I I

0 0.2 0.4 0.6 0.8 1.o 1.2 1.4 1.6 1.8 W I D 8

9 10 12 15 2 0 25 30 40 5 0 60 70 r7 51 6

X I FIGURE 5.2-13 AXIAL THROUGHWALL CRACK LENGTH DATA CORRELATION RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT I

20 15 10 5

0 10 20 30 40 50 CHANGE IN INITIAL PRESSURE (psi)

FIGURE 5.2-1 4 TYPfCAL BWR PRESSURE CHANGE FOR MSlV CLOSURE WITH FLUX SCRAM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

LOW PR I N J t CTl STEAM OUTLET \\ I

, ..I CORE SPRAY INLET ESSURE COOLANT -

h ION INLET CORE SPRAY SPARGER JET PUMP ASSE MB L Y FUEL ASSEMBLIES JET PUMP/

R ECI RCU L A 1 I ON WATER INLET V ESSE L SUPPORT SKIRT CONTROL ROD DRIVE'S I N-COR E FLUX MONITOR STEAM DRYER ASSEMBLY STEAM SEPARATOR ASSEMBLY FEEDWATER INLET F E E DWATER SPARGER CORk SPRAY LINE TOP GUIDE CORE SHROUD CONTROL BLADE CORE PLATE RECIRCULATION WATER OUTLET SHIELD WALL CONTROL ROD DRIVE HYDRAULIC LINES REACTOR VESSEL CUT-AWAY DIAGRAM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

I HIGH WATER LEVEL TRIP (L8)

LOW WATER LEVEL SCRAM (L3)

LOW-LOW WATER LEVEL TRIP (L2)

ECCS INITIATION LEVEL (Ll)

FIGURE 5.3-2 REACTOR VESSEL NOMINAL WATER LEVEL TRIP AND ALARM ELEVATIONS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

A 2 OF BRACKET I

f I

I I

I I

I I

I

\\

1 1

I 1

I

=

  • I I

I I

I I

I I

I I

FIGURE 5.3-3 BRACKET FOR HOLDING SURVEILLANCE CAPSULE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

THIS FIGURE HAS BEEN DELETED RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT MINIMUM TEMPERATURES REQUIRED VERSUS REACTOR PRESSURE (Valid up to 32 EFPY)

Figure 5.3-4a REVISION 17

THIS FIGURE HAS BEEN DELETED RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT MINIMUM TEMPERATURES REQUIRED VERSUS REACTOR PRESSURE (Valid up to 12 EFPY)

Figure 5.3-4b REVISION 17

THIS FIGURE HAS BEEN DELETED RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT MINIMUM TEMPERATURES REQUIRED VERSUS REACTOR PRESSURE (Valid up to 14 EFPY)

Figure 5.3-4c REVISION 17

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT PREDICTED ADJUSTED REFERENCE TEMP.

AS FUNCTION OF EFFECTIVE FULL POWER YEARS OF OPERATION FIGURE 5.3-5 REVISION 14 SEPTEMBER 2001 THIS FIGURE HAS BEEN DELETED

227" 347" 107" 378" I --- --------.I

I)--,------

r)- 358.56" BE LTLl N E ACTIVE FUEL ZONE PLATE HT. NO.

PLATE HT. NO.

PLATE HT. NO.

C3138-2 C3054-1 C3054-2 II)- 208.56" D -- # I - - - - - - - I I - - -

0 -.I,.---

- D m 202" 1 I

FIGURE 5.3-6 BELTLINE WELD SEAM AND PLATE LOCATIONS FOR RIVER BEND 1 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT

FO

  • FT N014B (AB)
  • FT N011A (AN)

H22-PNL P025 H22-PNL P025 J-6 NOTES:

SYSTEM TITLE SYS NO.

052 115

1. ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT TO BE PREFIXED WITH "B33-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

3.

THIS DRAWING HAS BEEN REDRAWN FROM GENERAL ELECTRIC COMPANY DRAWING NO. 762E286AA.

122 204 601 609 610 CONTROL ROD DRIVE HYDRAULIC CLOSED COOLING WTR-REACTOR PLANT RESIDUAL HEAT REMOVAL-LPCI REACTOR WTR CLNUP & FILTER DRAINS-FLOOR & EQUIPMENT SAMPLING REACTOR PLANT AIR INSTRUMENT

  • RTD N028B (BN)
  • RTD N023B (BN)

PDT N015B DRYWELL EL 82'-6" RCS*RO 253 (B-)

RCS*RO 256 (B-)

HOSE

  • VF014B (B-)
  • VF013B (B-)

VF017B (B-)

INSIDE DRYWELL 2

H22-PNL P022 RCS

  • RO 250 (B-)
  • PC001B (B-)

DRB

  • Z 492 DRB
  • Z 491 DRB
  • Z 135
  • Z 488
  • MOV F023B (BN)

RCS*HOSE 125(B-)

FO PT N006A H22-PNL P006 PT N006B RCS

  • V115 (B-)

RCS

  • RO 243 (A-)

RCS

  • RO 237 (A-)

RCS

  • RO 238 (A-)
  • FT N014C (AR)
  • FT N014D (AB)
  • FT N014A (AR)

RCS*

HOSE 5 (A-)

RCS*

HOSE 6 (A-)

RCS

  • V112 (A-)

RCS

  • V110 (A-)

RCS

  • V113 (A-)

RCS

  • V111 (A-)

RCS

  • RO 242 (A-)

H22-PNL P025 DRB

  • Z 456 DRB
  • Z 505 DRB
  • Z 467 DRB
  • Z 468 DRB
  • V114 (B-)

RCS*

V3006 RCS*

V3005 RCS*

V3008 RCS*

V3007 RCS*HOSE 7(A-)

RCS*HOSE 8(A-)

(A-)

(A-)

(A-)

(A-)

RCS

  • RO 248 (B-)

RCS*

HOSE 1 (B-)

  • RTD N023A (AN)
  • RTD N028A (AN)

RCS*RO 246 (A-)

RCS*RO 245 (A-)

RCS*

V14 (A-)

RCS*

V12 (A-)

PDT N015A H22-PNL RCS*RO 241 (A-)

(A-)

  • VF014A (A-)
  • VF013A (A-)
  • VF017A (A-)

2

  • Z 466 DRB
  • Z 133 DRB
  • Z 474 DRB
  • Z 473
  • MOV F023A (AN)
  • PC001A (A-)

DRYWELL EL 82'-6" RCS*

FLEX HOSE 103 T/C C001B T/C C001B T/C C001B C001B T/C C001B T/C C001B LS C001B U

LS C001B M

LS C001B N

T/C C001B SPARE SPARE T/C C001B PI R002B RCS*

PI R001B RCS 249 (B-)

H22-PNL P022 DRB DRB

  • Z 487
  • MOV F067B (BN) 3/4" X 1" RED
  • HYV F060B (B-)

SEAL CAVITY NO.2 SEAL CAVITY NO.1 E-14 FC FC PT N005A PI R001A PI R002A H22-PNL P006 H13-PNL P006 H13-PNL P022 PT N005B

  • FT N024D (BB)

RCS

  • RO 251 (B-)

RCS

  • RO (B-)
  • FT N024C (BR)

RCS*

(B-)

  • FT N011B (BN)

RCS

  • V116 (B-)

RCS

  • V117 (B-)

DRB

  • Z 457 DRB
  • Z 490 DRB
  • Z 489 DRB
  • Z 449 RCS RCS RCS*

(B-)

RCS*

HOSE 4 (B-)

(B-)

  • V3011 RCS HOSE 2
  • V3009(B-)

RCS

  • V3012(B-)

RCS

  • RO (B-)

255 254 HOSE 3

  • V3010 (B-)

T/C C001A T/C C001A T/C C001A T/C C001A T/C C001A LS C001A U

T/C C001A LS C001A N

LS C001A M

SPARE SPARE SPARE RCS*RO 240 (A-)

RCS

  • V10 (A-)

RCS

  • V11 C-9 DRB
  • Z 465 DRB
  • HYV F060A (A-)
  • MOV F067A (AN)

SEAL CAVITY NO.2 SEAL CAVITY NO.1 3/4" X 1" RDCR T/C C001A (A-)

RCS*HOSE 108 RCS*HOSE 105 (A-)

T/C C001B T/C C001B T/C C001B T/C C001B T/C C001B T/C C001B T/C C001B T/C C001B T/C MOTOR WINDING COOLER "B" SPARE SPARE LS C001B R

LS C001B S

SPARE SPARE SPARE LOOP "B"

  • VF059 (Z-)

2 TO JET PUMPS F019 (ZB)

  • AOV F020 (ZR)

SAMPLE PROBE

  • SMPTD014 B13*REV D003(Z-)

REACTOR VESSEL T/C C001A T/C C001A T/C C001A T/C C001A T/C C001A T/C C001A T/C C001A MOTOR WINDING COOLER "A" LS C001A S

LS C001A R

SPARE LOOP "A" SPARE SPARE 9.3-7c(M-14) 9.3-7c(L-14) 9.3-7c(F-14) 9.3-1c(D-11) 9.3-7c(M-15) 9.3-7c(E-15)

DWG NO.

4.6-5 9.2-2 9.3-1 5.4-12 5.4-15 9.3-7 9.3-4 9.3-7c(E-15) 9.3-7c(E-14) 5.4-15a(N-1) 9.3-7c(L-6) 5.4-15a(P-5) 9.3-7c(N-12) 9.3-7c(M-12) 9.3-7c(N-10) 9.3-7c(M-10) 9.3-7c(N-10) 9.3-7c(M-12) 4.6-5a(A-9) 4.6-5a(A-9) 9.3-7c(N-14) 9.3-1c(E-13) 9.3-7c(E-6) 9.3-7c(F-13) 9.3-7c(E-13) 9.3-7c(F-10) 9.3-7c(E-10) 9.3-7c(F-10) 9.2-2a(F-6) 9.3-7c(P-13) 9.2-2a(E-6) 9.2-2a(E-7) 9.3-4a(P-17) 5.4-12c(H-6) 9.2-2a(F-12) 9.2-2a(E-12) 9.2-2a(E-13) 9.3-7c(F-13) 9.3-7c(G-13) 9.2-2a(G-7) 9.2-2a(G-6) 9.2-2a(F-7) 9.2-2a(F-6) 9.2-2a(F-7) 9.3-1c(G-12) 9.2-2a(G-13) 9.2-2a(G-12) 9.2-2a(G-13) 9.2-2a(G-12) 9.2-2a(F-13)

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 4.

5.

1 6.

DELETED POO6 FIGURE SYSTEM P&ID REVISION 22 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 5.4-2a 053 REACTOR RECIRCULATION 25-1C PC001A

-NBE

-NBE PC001A PC001A

-NBE

  • RO A1 A2 B2 B1 C1 C2 D2 E2 D1 F2 F1 E1 G2 G1 B1 B2 A1 A2 C1 C2 E1 E2 G1 F2 F1 G2 J1 H1 H2 C001B T/C T/C C001B J2 SPARE SPARE C001A T/C C001A T/C H1 H2 SPARE SPARE J1 J2 FV 101(B-)

DRYWELL INSIDE H22*PNL P041 H22*PNL P042 H22*PNL P042 H22*PNL P015 H22*PNL P015

  • FT N024A (BR)
  • FT N024B (BB)

H22*PNL P041 P041 H22*PNL RCS

  • V24 (B-)

RCS

  • V29 (B-)

RCS

  • V25 (B-)

INSIDE DRYWELL INSIDE DRYWELL

  • AOV RCS*HOSE 124(B-)

INSIDE DRYWELL REFERENCES F075A H22-PNL P022 RCS

  • V27 (B-)

1A 1H 1V PC001A

-NBE 2H PC001A

-NBE 2V

-NBE 4V PC001A

-NBE 4H PC001A PC001B

-NBE 1V PC001B

-NBE 1H PC001B

-NBE 1A PC001B

-NBE 2H PC001B

-NBE 2V PC001B

-NBE 4H PC001B

-NBE 4V PC001B

-NBE 3

B33-T/C001AD1 IS A DAMAGED SPARE (REF. CR96-0473).

7.

T/C C001A D2 D1 C001A T/C NOTE 7 NUCLEAR SAFETY RELATED R614 FR H13-PNL P680 C51 H22-PNL P006

-NBE PC001A 3

COMPONENT NUMBER AND SAFETY CLASSIFICATION.

RIVER BEND STATION. REFER TO THE EQUIPMENT DATA BASE (EDB) FOR THE PROPER THE ASTERISK "*" WAS USED IN A PREVIOUS EQUIPMENT IDENTIFICATION SYSTEM AT 2.





 





























 

!"

# 

# 

#$$



  1. 





#

  1. 













 



#$

$

#

#











 

#

 

#

 

#

 

#

 

#

 

#

 

#

 

#



$'"



(

)

  •  *+ #"""+ !

'  ! (!

! -$--#.$$"+#

!  # 

  "+#/

%   

$--.$"$"#!

!  #( #"(#(  

"

 0

"

 



 



 

$

$

# 

# 



 



"

 

"

 

"

 

"

 



 

 

 





  1. 





  1. 







  1. 







 



 





%



 



 



%











%

%











"

 (

"

 

"

 

"

 



!

"



$$

"

 

"

 /

0$

  1. ""$



$







%





  1. 



  1. 





%

 



%

 



  1. 



%

 





%







%





"

 "

"

 

"

 







  1. 



  1. 



  1. 



  1. 



%

 



%





%





%






  1. 



  1. 



%





%







%







%







%







%







%





"

 

"

 #

"



"

 $

"

 

#

  1. 







%







%







%





  1. 



  1. 



  1. 



%





%





%







%





"

 

 ( $

!



"

 

0$

  1. ""$





%





  1. 





%





$









%





%





  1. 
  1. 



%







%

 



 





%





  1. 



  1. 

%







%







%





%







%

 



  1. 



"

 



  1. 



%

 





%









  1. 

 

  1. 

%





%





 



 

 

"

 #







%







%

 





%

 





%





  1. 
  1. 
  1. 

%

 



%

 



%

 



%

 



#

  1. 

 ( $

!







 

!

! 

! 1



! 1



! 1

"

  1. (!

!

! 1



! 1



! 2



$!

"!$ (#$

3 "$

# (##"

$#-#-#  NORMALLY ISOLATED

"$.$# #("!

. .$# "/("

/($!













































































0











/

(















/

0

(







!

!



"($



'#

 1

$##"

#

!2



$

#



$($

24

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT VESSEL COOLANT TEMPERATURE VERSUS TIME (TWO HEAT EXCHANGERS AVAILABLE)

Figure 5.4-10 REVISION 14 SEPTEMBER 2001

RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT VESSEL COOLANT TEMPERATURE VERSUS TIME (ONE HEAT EXCHANGER AVAILABLE)

Figure 5.4-11 REVISION 14 SEPTEMBER 2001

  • V74 (Z-)

H22*PNL P018 H22*PNL P018 E12

  • FT N052A (AR)

E12

  • FT N015A (AR)

MIXING TEE FWS*BL1A(A-)

  • BL1A(A-)
  • V51 (A-)

E12

  • FE (A-)

E12*

MOV F023 E12*

VF019 (Z-)

H22*PNL P018

  • FT N001 (AR)

(E-10)

E12

  • T/C N024 (ZN)

E12

  • CE N025 (ZB) 3 SET @

75 PSIG E12

  • CE N001A (AR) 10.4-7b(J-13) 9.2-21c(H-5) 5.4-15a(D-2) 10.4-7b(J-13) 9.2-21c(H-4) 5.4-8(P-11)

D-17 9.3-3e(P-11) 11.2-1b(N-13) 5.4-15a(G-11) 5.4-12b(J-10) 5.4-8(A-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 6.3-4(F-16)

(M-18) 6.3-4(H-12) 5.4-12b(A-19) 5.4-12c(H-8) 5.4-12b (L-18) 9.3-7j (D-12)

EL 70'-0" AUX BUILDING 6.3-4(A-13) 6.3-4(A-12) 9.2-21c(H-3) 6.3-4(H-14)

(H-9)

LC (A-)

NO56A

  • PT E12 (AR)

NO55A

  • PT E12 P018
  • PNL H22 2

(A-)

  • VF072A E12 (AR)

N053A

  • PT E12 (A-)
  • VF031A E12 (A-)
  • VF029A E12 (A-)

R008A

  • PI E12 LC PIPE GUARD 20
  • Z KJB (Z-)

E12*F001 (ZR)

F008 MOV E12*

2 500 PSIG SET AT LMC (Z-)

  • V147 V

(Z-)

  • V240 (ZB)

F009 MOV E12*

(Z-)

  • V73 23A
  • Z KJB (A-)

D001A

  • RO E12 200 PSIG SET AT E12*PC002A(AR)

REMOVAL PUMP A RESIDUAL HEAT STRT1A T

PE (A-)

80A (A-)

R002A

  • PI E12 (AR)

E12*

MOV F004A S

200 PSIG SET @

LEVEL MIN. WATER (Z-)

  • V155 V

LMC SUPPRESSION POOL (A-)

  • V152 LMC V

25A

  • Z KJB (A-)
  • V150 L.C.

LMC D

(A-)

  • STR1A VF069 E12-2 (A-)

VF071A E12*

24A

  • Z KJB (A-)

F017A

  • RV E12 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.

VALVE POSITIONS DEPICT THE PLANT IN ITS NORMAL OPERATING MODE AND ARE FOR 5.4-12b(C-18) 9.2-1 10.4-7 9.2-21 5.4-15 6.3-4 DWG NO.

9.1-23 11.2-1 9.3-7j(D-18) 9.3-7j(D-17)

(J-15) 5.4-12c(J-11) 9.3-7j(D-16) 9.3-7j(D-13) 9.3-7j(D-14) 9.3-7j(D-12) 9.3-3 9.3-4 9.3-7 5.4-8 5.4-12b(C-18) 9.1-23a (P-11)

E12

F047A (AR)

N026A

  • PT (AN)

N004A

  • T/C E12 (A-)
  • V222 (E-17)

(TYP OF 2) 18" X 14" SERVICE WATER-NORMAL REACTOR WTR CLNUP & FILTER LOW PRESSURE CORE SPRAY 601 205 FEEDWATER CONDENSATE MAKEUP STORAGE & TRANSFER

REFERENCES:

118 107 106 SYS NO.

SYSTEM TITLE RADWASTE-LIQUID FUEL POOL COOLING 603 602 E12 (A-)

  • EB001A (A-)
  • V61 (A-)

(A-)

  • EB001C E12 (Z-)

VF067 E12*

T (A-)

  • V223 PE (AN)

N002A

  • T/C E12 INFORMATION ONLY. CONSULT THE STATION OPERATING PROCEDURES (SOP'S) FOR ACTUAL VALVE LINEUPS.

THIS IS A GENERAL ELECTRIC SYSTEM.

THIS DRWAING HAS BEEN REDRAWN FROM GENERAL ELECTRIC DWG. NO. 762E424AA DENOTES VALVE WELDED TO PENETRATION.

ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "RHS-" EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

1.

NOTES:

REACTOR CORE ISOLATION COOLING 209 SAMPLING TURBINE SAMPLING REACTOR PLANT DRAINS-FLOOR & EQUIPMENT 611 610 609 (BB)

VF066B E12*

2 3

3 2

TUNNEL AUX BLDG

(-R) 45A

  • ZS 2

9.3-3e(P-12) 6.3-4 (N-4) 9.2-21c(J-21) 5.4-12b(P-1) 5.4-12c(N-6) 9.3-7j(H-8) 9.3-7j (H-8) 5.4-12b(M-18)

  • V376(A-)

LC LO VF056A VF039A

(-R) 46A

F041A AOV E12*

(AR)

F042A MOV E12*

(AR)

F037A MOV E12*

1 2

165 HOSE 164 HOSE 10" (A-)

VF099A E12*

2 3

2 (AR)

E12*

DIM MIN

  • REV D003(Z-)

B13 VESSEL REACTOR DIM.

MIN.

(A-)

  • V38 (A-)

E12*

(Z-)

200

  • RO 356
  • Z DRB 355
  • Z DRB (Z-)
  • V71 21A
  • Z KJB (A-)

201

  • RO (ZR)

N080A

  • PDT E31 FC FC (AR) 47A
  • RTD (A-)

47A

  • TW 22A
  • Z DRB (A-)

58A

  • RO (A-)
  • V300 BLDG SHIELD CONTAINMENT P629
  • PNL H13 P004 H22*PNL WELL DRY (AR)

N058A

  • PT E12

(-R)

N658A

  • ES E12 (A-)
  • V301 E12 3.

4.

5.

6.

N014A C61 053 REACTOR RECIRCULATION CONTAINMENT SHIELD BUILDING DRY WELL 1

5.4-2a 1

NOTE 7

7.

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

FIGURE SYSTEM P&ID REVISION 24 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 5.4-12a 204 RESIDUAL HEAT REMOVAL-LPCI 27-07A P0024 L.O.

  • V3012 L.O.
  • V3011 750-358-2
  • RO 208A (A-)

VALVE 1E12*MOVF052A HAS BEEN REPLACED WITH A BLIND FLANGE. REF. MR88-0208.

AIR SUPPLY TO VALVE 1E12*PVF051A IS ISOLATED PER MR88-0208.

VALVE 1E12*MOVF087A IS CURRENTLY INSTALLED WITH FLOW OVER THE SEAT.

VALVES 1E12*MOVF087A AND 1E12*MOVF026A HAVE POWER REMOVED. REF. MR88-0208.

8.

9.

10.

11.

NOTE 11 NOTE 8 NOTE 9

NOTE 10, 11 13.

A 1/8" DIAMETER HOLE HAS BEEN DIRLLED IN THE DOWNSTREAM (REACTOR SIDE) DISC OF 1E12*MOVF042A TO PROVIDE AN INTER-DISC PRESSURE RELIEF PATH.

NOTE 13 DELETED 14.

INTERNALS REMOVED FROM CHECK VALVE RHS*V34.

15.

DELETED 12.

E12

  • MOV F024A (AR)

E12

  • MOV F049 (ZB)

E12

  • MOV F040 (ZR) 2 3
  • V175 (Z-)
  • V21 (Z-)

E12

  • MOV F026A (A-)

E12

  • VF054A (A-)

H22*PNL P018 E12

  • PT N028 (ZR)

E12

  • MOV F011A (AR)

E12

  • RV F036 (Z-)

E12

  • MOV F003A (AR)

E12

  • MOV F048A (AR)

E12

  • T/C N027A (AN)
  • V52 (A-)

E12

  • VF084A (A-)
  • VF085A (A-)

E12

  • V58 (A-)

E12

  • VF018A (A-)
  • VF046A E12 (A-)

E12

  • MOV F064A (AR)
  • V56 (A-)

NOTE 15

  • V34 (A-)

E12

  • MOV F073A (AR)

E12

  • MOV F074A (AR)

E12

  • MOV F006B (BB)

E12

  • PT N057 (ZR)
  • ZS 45B

(-B)

E12

  • VF066A (AR)

E12

  • MOV F006A (AR)

E12

  • RV F005 (Z-)
  • TW
  • V55 (A-)

E12

  • VF070 (Z-)

E12

  • MOV F087A (A-)

E12

  • PV F051A (A-)

E12

  • SOV F075A (AR)

E12

  • SOV F060A (AB)

E12

  • LV F065A (AR)

E12

  • I/P K001A (AR)

E12

  • MOV F027A (AR)

E12

  • FE N012 (Z-)

E12

  • VF050A (A-)
  • RO 4A (A-)

E12

  • RV F025A (A-)

E12

  • MOV F053A (AR)

TO CONTROL CIRCUIT ADS VALVES

  • V68 (A-)

RESIDUAL HEAT REMOVAL HEAT EXCHANGER RED ELBOW

  • V36 (Z-)
  • V59 (A-)

H22*PNL P018

  • V40 (Z-)

12"x6" DRAG RESISTOR.

RHS-R0208A PLATE TYPE RESTRICTING ORIFICE REPLACED WITH INLINE 16.

NOTE 16 ZS 067 3

THE PIPING CLASS CHANGE FROM CLASS 151 TO CLASS 601 IS SEPARATED/PLUGGED 17.

AT THE PRESSURE BOUNDARY BY 1.5" THICK PLATE.

TEMPORARY STRAINER STRT 1A ELEMENT HAS BEEN REMOVED.

18.

NOTE 18 NOTE 17 CL151 CL601 67A RV 500 PSIG SET @

CL151 CL601 NOTE 17 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

  • V3029 NOTE 19 (Z-)

LC 5.4-8(N-12) 19.

VALVE E12-MOVF023 HAS BEEN DETERMINATED. REF MR96-0069

  • TW 80B (B-)

E12

  • PI R002B (B-)

E12

  • PI R008B (B-)

KJB

  • Z 25B
  • V135 (B-)

LMC D

L.C.

T STRT1B E12*

VF071B (B-)

  • V14 (B-)

PE F017B (B-)

E12

  • RV F030 (Z-)
  • STR1B (B-)

SUPPRESSION POOL E12*PC002B(BB)

RESIDUAL HEAT REMOVAL PUMP B AUX BLDG EL 70'-0" MIN WATER LEVEL SET @

200 PSIG SET @

200 PSIG 2

F004B (BB)

MOV E12*

S CONTAINMENT E12*

MOV F064B (BB) 2

  • V66(B-)

RESIDUAL HEAT REMOVAL HEAT EXCHANGER RESIDUAL HEAT REMOVAL HEAT EXCHANGER E12

  • PT N053B (BB)

D001B (B-)

E12

  • PT N055B (BB)

E12

  • PT N056B (BB)

E12*

VF072B(B-)

E12*

VF031B (B-)

E12*

VF084B (B-)

E12*

VF085B (B-)

  • V15 (B-)

2 E12*

  • V16(B-)

VF029B(B-)

H22*PNL P021 LO 209 601 609 611 REACTOR CORE ISOLATION COOLING REACTOR WTR CLNUP & FILTER DRAINS-FLOOR & EQUIPMENT SAMPLING TURBINE NOTES:

1.

ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "RHS-"

EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

3.

DENOTES VALVE WELDED TO PENETRATION.

4.

THIS DRAWING HAS BEEN REDRAWN FROM GENERAL ELECTRIC CO.

DWG NO. 762E424AA. THIS IS A GENERAL ELECTRIC SYSTEM.

VALVE LINEUPS.

E12

  • RV F025B (B-)

SHIELD BUILDING E12

  • RV E12*

VF046B (B-)

E12*

VF018B (B-)

KJB

  • Z 24B KJB
  • Z 23B
  • V65 (B-)

E12

  • I/P K001B (BB)

E12

  • T/C N002B (BN)

PE T

  • V221(B-)

E12

  • MOV F048B (BB)

E12

  • T/C NOO4B (BN)

E12

  • MOV F073B (BB)

E12

  • RO SET @

500 PSIG

  • EB001B E12
  • EB001D (B-)

E12

  • MOV F074B (BB)

SYSTEM TITLE SYS NO.

REFERENCES E12

  • CE N001B (BB)

E12 T/C N027B (BN)

  • TW 47B (B-)
  • RTD 47B (BB)
  • SOV FC 2

3

  • V23(B-)

FC FC 106 107 118 CONDENSATE MAKEUP, STOR & TRANS FEEDWATER SERVICE WATER NORMAL E12

  • LV F065B (BB)

E12

  • MOV F003B (BB)

F060B (BB)

(BR)

F075B

  • SOV E12 E12 E12
  • AOV F098 (ZN)

E12

  • MOV F096 (ZB)
  • MOV E12 F094 (ZB)

E12*

VF104B (B-)

E12*

VF103B (B-)

E12*

VF104A (A-)

E12*

VF103A (A-)

H13*PNLP021 E12*PT N051B E12

  • PT N026B (BB)

H22*PNLP021

  • V20 (B-)

E12

  • VF054B (B-)
  • RO 58B (B-)
  • V303(B-)

E12

  • PV F051B (B-)

E12

  • MOV F087B (BB)

E12

  • MOV F026B E12
  • FT N052B (BB)

E12

  • FT N015B (BB)

E12

  • FE N014B (B-)
  • FT 15B (BB)

(B-)

H22*PNL P021 H22*PNL P021

  • V22(B-)

E12

  • MOV F011B (BB)

E12

  • MOV F024B (BB)

(BB)

H22*PNLP018 H22*PNLP018 E12*PT N050A E12*PT N051A E12*PT N050B H22*PNLP021 E12

  • VF050B (B-)

MIXING TEE

  • BL1B(B-)

FWS*BL1B(B-)

E12

  • MOV FO53B (BB)

(G-16)

  • RO 4B B13
  • REV D003(Z-)

REACTOR VESSEL

  • ZS 46B (B-)
  • RO 203 (Z-)

DRB

  • Z 388 DRB
  • Z 22B 2

2 3

E12*

VF039B (BB)

  • V4(Z-)

E12*

VF099B (B-)

KJB

  • Z 21B CONTAINMENT
  • V224(Z-)

LC E12*

AOV F041B (BB)

E12*

MOV F037B (BB)

E12*

MOV F027B E12*

MOV F042B (BB)

SFC*V107(Z-)

RM SHIELD BLDG

  • HOSE 160(Z-)

LO LC MIN DIST 5.4-12a (C-9) 5.4-12a (D-6) 5.4-12c (H-10) 5.4-12a (D-16) 5.4-12c (D-9) 6.3-1 (A-12) 9.3-7k (L-13) 9.3-7k (K-14) 9.3-7k (K-14) 5.4-12c (D-14) 5.4-8 5.4-15 9.3-7 9.3-3 9.3-7k (K-8)

(M-8) 9.3-7k (K-9) 9.3-7k (K-10) 5.4-12c(H-12)

DWG NO.

9.2-21 10.4-7 9.2-1 9.3-3e (P-9) 9.3-7k (L-16) 9.2-1f (H-5) 5.4-12a (F-16) 5.4-8(G-12) 9.3-4b (G-18) 5.4-12c (G-4) 10.4-7b (N-16) 9.3-7k (P-11) 5.4-12a (N-14) 9.3-7k(P-13) 5.4-8 (K-12) 5.4-12a (K-9) 5.4-8 (K-11) 10.4-7b (N-16) 5.4-15a (E-4) 9.2-21c (K-2) 5.4-12c (H-4) 5.4-12a (N-6) 9.1-23a (K-6) 5.4-12c (N-6) 9.2-21c (K-21) 9.1-23a (H-3)

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 053 REACTOR RECIRCULATION 053 REACTOR RECIRCULATION 602 FUEL POOL COOLING FUEL POOL COOLING 602 5.4-2a 5.4-2b 9.1-23a 9.1-23b 1

PIPE CAPS USED ON VENT, DRAINS, AND TEST CONNECTIONS THAT ARE NORMALLY ISOLATED 5.

6.

  • V302(B-)

NOTE:

FOR PUMP DRAINS SEE FIG 9.3-7k (M-20)

NOTE 7 7.

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

FIGURE SYSTEM P&ID REVISION 23 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 5.4-12b 204 RESIDUAL HEAT REMOVAL-LPCI 27-07B P0025 L.O.

  • V3013 L.O.
  • V3014
  • RO 208B (B-)

VALVE 1E12*MOVF052B HAS BEEN REPLACED WITH BLIND FLANGE.

REF. MR88-0208.

VALVES 1E12*MOVF087B AND *MOVF026B HAVE POWER REMOVED.

REF. MR88-0208.

AIR SUPPLY TO VALVE 1E12*PVF051B IS ISOLATED PER MR88-0208.

VALVE 1E12*MOVF087B IS CURRENTLY INSTALLED WITH FLOW OVER THE SEAT.

1E12*PTNO50A/B & 1E12*PTNO51A/B HAVE BEEN ELECTRICALLY DISCONNECTED AND SERVE NO SYSTEM FUNCTION. THESE INSTRUMENTS ARE SPARED IN PLACE AND THE INSTRUMENT SENSING LINE IS CAPPED NEAR THE ORIGINAL SOURCE CONNECTION POINT.

9.

10.

11.

12.

13.

NOTE 13 NOTE 13 NOTE 9 NOTE 13 NOTES 10,12 NOTE 11 NOTE 10 (B-)

14.

DELETED A 1/8" DIAMETER HOLE HAS BEEN DRILLED IN THE DOWNSTREAM (REACTOR SIDE) DISC OF 1E12*MOVF042B TO PROVIDE AN INTER-DISC PRESSURE RELIEF PATH.

15.

NOTE 15 NOTE 16 INTERNALS REMOVED FROM CHECK VALVE RHS*V65.

16.

8.

DELETED 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 RHS-R0208B PLATE TYPE RESTRICTING ORIFICE REPLACED WITH INLINE DRAG RESISTOR.

17.

NOTE 17 THE PIPING CLASS CHANGE FROM CLASS 151 TO CLASS 601 IS SEPARATED/

PLUGGED AT THE PRESSURE BOUNDARY BY 1.5" THICK PLATE.

18.

NOTE 19 19.

TEMPORARY STRAINER STRT 1B ELEMENT HAS BEEN REMOVED.

20.

INTERNAL BLIND SPOOL PIECES HAVE BEEN INSTALLED IN PIPING PER EC 7093.

NUCLEAR SAFETY RELATED 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.

SET @

500 PSIG 67B RV NOTE 18 CL151 CL601 CL601 NOTE 18 CL151 E12*

VF102 (B-)

PE (B-)

  • V250 T

(BB)

FO47B

  • MOV E12 (B-)
  • EB001B E12
  • V25(B-)
  • V24(B-)

RHS-V3028 NOTE 20 NOTE 20 NOTE 21

21. ONE-TIME DEVIATION TO AS-LEFT SET PRESSURE TOLERANCE FOR E12-RVF017B APPROVED FOR CYCLE 18 ONLY PER EC 45174.

25

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 FIGURE SYSTEM P&ID REVISION 23 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 5.4-15a 601 REACTOR WTR CLNUP & FILTER 26-03A P0203

  • V16
  • V15 G33*

VF013A G33*

VF045A G33-PI R001A G33*R0 D002A G33*VF012A 9.3-7m(G-14)

V D

9.3-7m(G-13) 9.3-7m(G-13)

D 9-1B(F-7) 9-1B(F-7)

G33*PC001A G33-RTD N001A LO G33*VF005A R009A G33-PI

  • V23
  • V24 G33*VF043A LO N001B G33-RTD G33*PC001B 9.2-2b(F-5) 9.2-2b(F-5)

D 9.3-7m(G-10) 9.3-7m(G-11)

D V

9.3-7m(G-11)

G33*VF012B D002B G33*R0 R001B G33-PI G33*VF045B G33*VF013B

  • V18
  • V17 LO G33*VF043B
  • V26

FL. EL. 95'-9" PE

  • V11 G33*RO N043 G33
  • MOV F054 (ZR)

SHIELD BUILDING CONTAINMENT KJB*Z 129 2

3 G33-PT N005 H22*PNLP002

  • V28 D-4 2

3 G33

  • MOV F053 (ZB) 1 3

(ZR)

F004

  • MOV G33 KJB*Z 7

SHIELD BUILDING AUXILIARY BUILDING CONTAINMENT

  • RO 202 (A-)
  • HOSE 2 (Z-)

E31*FT N076A (AR)

H22*PNLP004

  • V10(A-)

DRB*Z 417

  • V8(A-)

N037 G33-FT H22-PNLP009 5.1-3a(B-21)

  • V4(Z-)

MIN. DIST.

DRB*Z 416 418 DRB*Z DRYWELL G33*FE N035 (Z-)

  • RO 203 (A-)

5.4-2aC(C-7) 5.4-2a(D-16)

REACTOR VESSEL B13*REVD003(Z-)

G33

  • MOV F102 (ZN)

(ZN)

F101

  • MOV G33
  • RO 204 (Z-)

MIN. DIST.

1 2

G33

  • MOV F100 (AN)

(BN)

F106

  • MOV G33 B33*T/C N021 (ZN)

(ZN)

N022 B33*T/C

  • V212(B-)
  • V210(B-)

MIN. DIST.

E31*FT N076B (BB)

H22*PNLP015 AUXILIARY BUILDING 398 DRB*Z

  • RO 201 (B-)

DRB*Z 397

  • RO (B-)

200 G33

  • EB001 UNIT C 6" X 4" RED UNIT B
  • EB001 G33 G33
  • EB001 UNIT A REGENERATIVE HEAT EXCHANGERS
  • RV 146 1410 PSIG SET AT H-18 G33
  • RTD N004 G33*

VF105 G33*

VF052B(B-)

  • V233 (B-)

VF052A(A-)

G33*

  • V232 (A-)

G33*

VF051(Z-)

E31*FT N077A (AR)

N040 G33*FE (Z-)

  • V32 (A-)
  • V31 (A-)

(A-)

  • V33 (A-)
  • V34
  • V217 (B-)
  • V216 (B-)

(B-)

  • V214 (B-)
  • V215 (BB)

N077B E31*FT G33

  • MOV F039 (ZR)

F042

  • MOV G33 (ZR)

F040

  • MOV G33 G33*

VF055 (Z-)

LMC LC D

G33

  • RTD N015

2 KJB*Z 6

G33

  • MOV F107 (E-20)

G33

  • MOV F104 DWG. NO.

SYS. NO.

SYSTEM TITLE 053 REACTOR RECIRCULATION 115 609 208 610 CLOSED COOLING WATER-REACTOR PLANT DRAINS-FLOOR & EQUIPMENT MSIV POSITIVE LEAKAGE CONTROL SAMPLING REACTOR PLANT

REFERENCES:

NOTES:

ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "WCS-"

EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

THIS DRAWING HAS BEEN REDRAWN FROM GENERAL ELECTRIC COMPANY DRAWING NO.

796E737, REV. 0. THIS IS A GENERAL ELECTRIC SYSTEM.

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.

VALVE POSITIONS DEPICT THE PLANT IN ITS NORMAL OPERATING MODE AND ARE FOR INFORMATION ONLY. CONSULT THE STATION OPERATING PROCEDURES (SOP'S) FOR ACTUAL VALVE LINEUPS.

1.

3.

4.

5.

5.4-15b(K-7) 5.4-15b(D-7)

G33

  • MOV F044 G33*

VF020

  • V169 3

G33*SMPT D014 G33*RTD N007 N019 G33*RTD N020 G33*TS G33*

EB002B EB002A G33*

  • RV 141 SET @

1410 PSIG 148

-RV SET @

150 PSIG G33

  • RTD N006 PE
  • V171 T

(K-6)

  • V167 G33*

VF021B VF021A G33*

  • V168 3

G33*SMPT D015A G33*SMPT D015B E31*FT N075A (AR)

  • V221(A-)
  • V220(A-)
  • V219(A-)
  • V218(A-)

(Z-)

N011 G33*FE

  • V44(B-)
  • V43(B-)

E31*FT N075B (BB)

G33

  • MOV F046 G33
  • SOV F041 V163 3

G33-RV F036 F035

  • MOV G33 3

SET AT 150 PSIG 9.3-7h(J-6)

  • RV 144 (Z-)

SET AT 1410 PSIG LC SHIELD BUILDING CONTAINMENT G33

  • MOV F034 (ZR)

(ZB) 111

  • MOV
  • V46 (B-)

(B-)

  • V45 2

3 KJB*Z 4

(ZB)

F028

  • MOV G33 2

3 H22*PNLP002 G33-PS N014

  • V47 G33*RO D001 G33
  • MOV F031
  • V41 N013 G33-PS H22*PNLP002 G33
  • PV F033 FC G33-PI R008
  • V49 G33*VF032 5.4-2 9.2-2 9.3-7 6.7-1 9.3-4 5.4-15b(M-15) 9.4-4a(P-14) 9.3-4a(P-13) 5.4-15b(E-16) 9.3-4a(P-16) 9.3-7h(L-3) 7.3-7h(L-6) 9.3-7h(L-6) 9.3-7h(L-6) 9.3-7h(L-3) 9.2-2a(N-6) 9.3-7h(M-4) 9.3-7h(M-3) 9.3-7h(N-6) 9.2-2a(M-2) 9.3-8c(G-8) 5.4-12a(P-15) 9.3-7h(M-8) 9.3-7h(M-11) 9.3-7h(M-8) 9.3-7h(M-11) 9.3-7h(M-13) 9.3-7h(M-15) 9.3-7h(M-15) 9.3-7h(M-13) 5.4-12b(P-10) 5.4-12a(J-17) 9.3-7h(L-8) 9.3-7h(L-8) 9.3-7h(L-11) 9.3-7h(L-11) 9.3-7h(L-15) 9.3-7h(L-15) 9.3-7h(N-4)

LMC G33*VF109(Z-)

(ZB)

F001

  • MOV G33
  • HOSE 1 (Z-)

H22*PNLP002 1

2 CHEMICAL DECON CONNECTION B33*

VF029 DECON CHEMICAL CONNECTION RCS-V3068B 2

1 CONNECTION DECON CHEMICAL NOTE 6

NOTE 6 4" BLIND CONNECTION FOR CHEMICAL DECONTAMINATION REF. MR91-0087.

6.

36-1A(N-3) 36-1A(N-2)

  • V3016(Z-)

V3010A V3010B WCS-TI 28B WCS-TI 28A G33-RTDN001A AND G33-RTDN001B READ WATER TEMPERATURE AS IT EXITS THEIR 7.

RESPECTIVE PUMP SEAL CAVITIES, UPSTREAM OF SEAL WATER HEAT EXCHANGERS NOTE 7 NOTE 7

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 4"x2" RED.

2 RED.

4"x2" 1

V3068A RCS-1 2

3 V3027 V3028 V3024 V3025 V3026 V3023 3

PID-21-02C(N-20)

PID-21-02C(M-20) 610 SAMPLING REACTOR PLANT MITIGATION MONITORING SYSTEM PID-21-02C WCS*E4A AND WCS*E4B.

V179 G36-VF062 V

V194 V193 G36-LT N018 G36-VF076 G36-VF061 PRECOAT TANK D

G36

  • VFO36B
  • AOV FO06B P-21 G36 CHEMICAL CLEANING CONNECTIONS SYSTEM TITLE SYS NO.

REFERENCES:

106 121 CONDENSATE MAKE-UP STORAGE & TRANSFER 403 603 609 HVAC-CONTAINMENT BUILDING AIR-SERVICE & BREATHING RADWASTE LIQUID DRAINS-FLOOR AND EQUIPMENT NOTES:

EXCEPT WHERE A DIFFERENT PREFIX IS SHOWN.

794E766AA REV. 0. THIS IS A GENERAL ELECTRIC SYSTEM.

4. FILTER HOLDER AND FILTER SHALL BE ATTACHED WHEN SAMPLE IS DESIRED THEN REMOVED.
3. THIS DRAWING HAS BEEN REDRAWN FROM GENERAL ELECTRIC COMPANY DRAWING NO.
1. ALL LINE, INSTRUMENT, VALVE, AND EQUIPMENT NUMBERS TO BE PREFIXED WITH "WCS-G36-VFO46 T

V118 G36-PNLP001 G36-TKA002 AGITATOR SUPPLIED WITH TANK RESIN FEED TANK G36-FO63 DUST COLLECTOR SUPPLIED WITH TANK FC FC AG1 G36-VFO45 G36-VFO25 G36-TKA001 PI RO12 FC PE G36-FG D004 F023 G36-AOV F052 G36-FV F021 G36-AOV FO20 G36-SET AT 150 PSIG AG2 G36-RV FO87 G36-G36-FG DO06B 3

FC G36

  • AOV FO14B G36
  • AOV F013B G36
  • AOV FO15B V139 LMC V

KJB

  • Z 5

SHIELD BLDG LMC V

CONTAINMENT PI 42B

  • RV 154 (Z-)

AOV 110 2

2 V56

  • V55 (Z-)

LMC V141 FC V180 V142 V140 P5B 10"X8" 3

  • EJ2B(B-)

2 1/2"X1 1/2" (TYP OF 2)

V136 AUX BLDG TUNNEL RAD BLDG V131

  • MOV 173
  • MOV 172 (ZR)
  • MOV 178 (ZB)

BACKWASH RECEIVING TANK PUMPS SET AT 150 PSIG LC SOV 110 G36-LT NO09 (ZB) 2 1/2"X1" (TYP OF 2)

FC V122 G36-PC003 TYGON TUBING V144 V119 T

FC RESIN METERING PUMP G36-PNLP001 G36-PCV FO89 G36-G36-PI RO13 PE F003A G36-AOV F022 G36-AOV FO24 REACTOR BLDG FL EL 162'-3" G36-PC002 REACTOR BLDG.

FL EL 162'-3" V231 FC

  • V77
  • V75
  • V71
  • V69

T T

T

  • V83 V79 V81 G36-
  • VFO33A G36*VFO31A FC FC FC 2"X1 1/2" G36
  • VFO34A DO13A RM PE PE G36-PT NO13A G36-PDT N004A G36
  • RV FO81A
  • V67
  • V63
  • V65 FC G36
  • VF029A
  • V128
  • V130 G36*VFO18A
  • STRT DO09A RM RM RM RM G36*VFO38A G36*VFO35A OUTLET INLET CHEMICAL CLEANING CONNECTION G36-FG DO05A G36*VFO37A RM 3

FC 3

RM G36*VFO36A FC G36

  • VFO30A PT N015A G36
  • STR G36*VFO32A PE G36
  • VF069A G36*PCOO1A 3

G36

  • FE N001A
  • STRT 2A
  • AOV FO16A G36
  • AOV F008A G36
  • AOV F007A G36
  • AOV F005A G36
  • AOV F006A G36
  • AOV FO02A G36

-PDT NO17A G36

-PDT N016A HOLDING PUMP P-19

  • V3000 V

SET AT 1410 PSIG G36 T

V133 PE PI 42A STRT 5A STRT 5B V137 V138 3

3 EJ6 EJ5 EJ4 PE EJ3 BACKWASH RECEIVING TANK G36*TKA003 V135 T

V134 P5A 3

FC FC 3"X2 1/2" G36

3 G36-VFO58 G36-VFO73 G36-PNLP001 PRECOAT PUMP 4"X 3" V123 NOTE 8 G36-PI R011 G36-RV F085 G36-RV F084 G36

  • AOV F004A G36
  • FV SET AT 150 PSIG A-13 H-12 SET AT 150 PSIG FC G36-VF059 PCV 117 G36-PI RO18A G36-LE N012A G36-FG D007A DO11 3

G36

  • DEMIN 3

FC FC CLEANUP FILTER DEMINERALIZER 3

G36-G36-FG D006A FC G36 N006A CES-PNL4

  • AOV FO11A
  • AOV FO12A
  • AOV FO09A
  • AOV FO10A
  • AOV FO14A G36
  • AOV F013A G36
  • AOV FO15A G36

-FT N002A G36 G36 G36 G36 G36 FC G36-PI RO10 G36

  • VF075 V143 V132 3

PE 10"X8"RED FC

  • EJ2A(A-)

T G36-PNLP001 G36

-RV FO86 4"X2 1/2" 3

AOV 171 FC AOV 101 SET AT 150 PSIG V195 SOV 171 SOV 101 3/4" TUBING V

D 7'-6" MINIMUM V196 V197 3

DER-V301 DER-V300 9.2-21c(M-19) 9.3-7h(N-19)

DWG NO.

9.3-7h(J-6) 5.4-15a(C-20) 9.3-7a(J-18) 5.4-15a(A-19)

REACTOR BLDG FL EL 141'-0" 11.2-1d(N-7) 9.3-7g(D-15) 9.3-7h(N-20) 5.4-15a(B-19) 9.3-7a(J-18) 9.3-7b(N-5) 5.4-15a(D-20) 9.3-2c(L-13) 9.4-7b(L-20) 9.3-7a(J-20)

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.

F011B G36 G36 G36 G36 1410 PSIG SET AT FO03B

  • FV G36 FO01B
  • AOV G36 FO02B
  • AOV G36 FO12B
  • AOV
  • AOV FO10B
  • AOV FO09B
  • AOV DEMINERALIZER CLEANUP FILTER
  • DEMN G36 NO16B PDT G36-G36*STRTDO09B
  • V53
  • V54
  • V96
  • V100
  • V98 FC FC FC FC 6"X3" RM RM NO17B PDT G36-DO07B FG G36-FO81B
  • RV G36 RM 3

3 DO12 6"X3" PNL4 CES-

  • V110 KO01B I/P G36-NO02B
  • FT G36
  • V108 NO01B
  • FE G36
  • VFO32B G36 V3020B G36*VFO31B DO13B
  • STR G36
  • V102
  • V104
  • V106
  • VFO34B G36 NO15B PT G36-RM RM NO13B PT G36-NO04B PDT G36-NO12B LE G36-NO06B ZS 3

FO04B

  • AOV G36 T

G36*PC001B HOLDING PUMP F008B

  • AOV G36 FO16B
  • AOV G36 F007B
  • AOV G36 F005B
  • AOV G36 G36*VFO30B G36*VFO38B G36*VFO35B FC
  • VFO37B G36 3

RM RM FC DO05B FG G36-INLET OUTLET 3

  • V114
  • VFO33B G36 G36*STRT2B 3
  • V116 G36*VFO69B FC T

PE

  • V112 G36*VFO17B G36*VFO18B
  • VFO29B G36 RM RM T

PE PE 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.

G36-PS N019 G36-FIC N020 FLUSH CONNECTION 9.3-1d(N-2)

-ZS 3

3 FIGURE SYSTEM P&ID REVISION 22 UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATION 5.4-15b 601 REACTOR WATER CLNUP & FILTER 26-03B AIR-INSTRUMENT 122 INTERNALS TO CHECK VALVE 1G36-VF073 HAVE BEEN REMOVED.

7.

SEE NOTE 7 V3015 9.2-21 9.3-1 9.3-2 9.4-7 11.2-1 9.3-6

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 G36-AOV VALVE IS DESIGNED TO FAIL CLOSE. HOWEVER ON LOSS OF AIR VALVE MAY NOT MAINTAIN PRESSURE BOUNDARY ISOLATION REQUIRED FOR MAINTENANCE.

VALVE SHOULD NOT BE UTILIZED AS A MAINTENANCE BOUNDARY WITHOUT 8.

GAGGING OR ENSURING AIR IS MAINTAINED TO THE ACTUATOR. REFERENCE NOTE 8 NOTE 8

NOTE 8 NOTE 8

NOTE 8 NOTE 8 G36 NOTE 8 NOTE 8 NOTE 8 NOTE 8 NOTE 8 NOTE 8 NOTE 8 NOTE 8 CR97-2119 AND CR97-0540.

STRT 3 RM RM RM RM VF074 V3020A

Retrieved from "https://kanterella.com/w/index.php?title=ML17226A131&oldid=5118809"