ML21133A066

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0 to Updated Final Safety Analysis Report, Chapter 5, Figures
ML21133A066
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 04/29/2021
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21138A803 List: ... further results
References
Download: ML21133A066 (40)
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Text

Figure Marked "Historical" Reference Figure 1.2-84, "Reactor System Heat Balance," for current operating conditions Pressure Flow Temperature Enthalpy (psai) (lb/hr) ( ° F) (Btu/lb)

1. Core Inlet 1091 100.0 x 106 535 530.7
2. Core Outlet 1071 100.0 x 106 553 650.0
3. Separator Outlet (Steam Dome) 1060 14.986 x 106 552 1190.7
4. Steam Line (Turbine Inlet) 1005 14.986 x 106 545 1190.7
5. Feedwater Inlet (includes RWCU) 1088 15.087 x 106 425 403.3
6. Recirculation Pump Suction 1066 33.0 x 106 535 530.6
7. Recirculation Pump Discharge 1248 33.0 x 106 536 531.4 CHANNEL BYPASS - NORMALLY 10%

[3458 MWt]

FIGURE 5.1-1 Historical Rev. 16 09/12

STEAM DRYERS STEAM SEPARATORS MAIN FEED FLOW FROM TURBINE

~RIVING FLO'N _ _,_.

  • ~CORE JET PUMP RECIRCULATION PUMP VOLUME OF FLUID ltt 3 1 A LOWER PLENUM 3887 B CORE 2054 c UPPER PLENUM AND SEPARATORS 1321 D DOME (ABOVE NORMAL WATER LEVEL! 7934 E DOWNCOMER REGION 5817 F RECIRC LOOPS ANO JET PUMPS 1411 LIMERICK GENERATING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT (TYPICAL)

COOLANT VOLUMES OF THE REACTOR VESSELS AND RECIRC LOOPS FIGURE 5.1*2 Rev.5, 4/96

LGS UFSAR Figures 5.1-3 and 5.1-4 Deleted

RfFERENCE EQUIPMEN1 DATA RECIRC SYSTEM St'Meo..

REC/RC PUMP sue ION LINE Z8 H

Pl.Jl\i1P DISCMARGE UNE '28" c -~~;i:Ai~~T~l~~T~ f RING HEADER RECIRC RISER LINE (S PER LOOP) f'2" 1'2" Ri-JR/S~UTDOWN SuPPl...Y LINE '20" LOOP A ~x Rl-IR/51-41.JTOOWN i:<ETURN LINE 1'2.

o* HPCI SUPPLY LINE 10 I

KEY MOTOR DIM MAX RPM5 8')°

! t f ~ .-MOTOR OVERALL HEIG~H MAX RPMl 111"

~ MAX RPM'i~

G iKEY MOTOR DIM.

  • MA)( RPM3 (;,(."'

f I

I

+Y 270° _., - tY 2 era KEY IO\.!MP DIM

  • J:\.JMP (I, TO DISCHARGE <t RPS 30**

- PUMP DISCH¢ TO PED FLG FAC.E (MIN) RP.3 so"

- PUMP <t lO SU::TION WELD POINT RPl z4*

KEY PUMP DIM -~MP ct TO DISCHARGE WELD POINT RP4 28" F

KEY SUCTIO"° ~ DrSCl-4 VLV. DIM.- TOTAL VALVE LENGTl-4 RfWL 65"

  • --+-

I KEY Rl--IR/Sl-4UTDOWN RETURN LINE YALV£ LEl'(;TH Pk'CVL 61" 180° KEY ~R/51-lUTDOWN SUCTION LINE VALVE 1..ENGTM S.S"°'L 5-z*

-x STEAM~ FEEDWATER SYSTEMS E MAIN STE AM LINE u,"

D~

~

KEY F."N. VLV DIM -Cl-IECK VLV LENGTH iFWCvL 61"'

KEY F.W. VLV DIM- BLOCK VLV LENGTH FWetfL rol"'

POLL VALVE. 15*

(LINE.t:..' ~*o* ONLY) 0.D OF PENETRATION FOR 5rEAM LIN~S R:NS .4t" DETAIL A 00.0FPeNETRATION FOR F.w. LINES IPeNtFW 47."

D F.W. AT VESSEL '6 REQD PER PLANT) rz" FW. l~TINCREASE ~ 2~ INCREASE ~

KEY ISClL. VLV DIM. -LENGTH UPSTREAM (MA)() 5\ILVL1 4s**

' - LENGTH DONNSTREAM (~AK) f>VLVl.2 20*

~~

- SQUARE OPERAIOR DIM (MAX) i5vLV53* zz*

  • AN6LE CF'.)PERATOR ~VD3 45*

- 0PERATOR LENGT~ (MAI\) ISVLVL3 Is..*

KEY 1.$0L VLV DIM - OPERATOR DULL SPACE (~AX) 1S111."'-E l&l" c I I

Xl(TO 5 )-REQD FD>? STD PIPE t Pi.J'A0 5U5PENSION~

f----1._____ _.. ,,.,...___.,,__,__...,.

B

/~ :-J?o--19 I !r ~SRCVL LIMERICK GENERATING STATION

~fil~-- UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT

\

I

\ PIPE ROUTING OF REACTOR A

1' __

COOLANT SYSTEM AND ASSOCIATED SYSTEMS VIEWD-D VIEW(-C FIGURE 5.1-5 8 7 6 5 4 3 2

a*

H r

ll!ECICC PuMP LOOP *A

G

.J_.A LEGEND:

(lv'l-4)

F T.L. INDICATES TANGENT LINE RS RECIRCULATION SYSTEM SUCTION PIPING

~EC!~C Pr.JMP RD RECIRCULATION SYSTEM DISCHARGE PIPING

,,----- LOOP'£!,"

c=) INDICATES PIPE SPOOL NUMBER INDICATES FIELD WELD (DESIGNATIONS ARE TO BE 1*-s* 0 USED FOR NON-DESTRUCTIVE EXAMINATION RECORDS) 11 *IT S EE NOTE 9 L' I 1-- 20** RMR SHUTDOWN j..J SUPPLY 180°

~

E

~

PLAN PLAN 2 D

<Ro-N:.44\

r PLAN 2 t PLAN 2 15'-1~

10 S*H*

c r

PLAN I t PLAtl I

.i.

I z 6'-11 11 B

l t

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR RECIRCULATION A ELEVATION *A-A" ELEVATION 'B-B" SYSTEM LOOP*~* LOOP"e!

SAME AS LOOP *e,' E)(CEPT A':> NOTED FIGURE 5. 1-6 8 7 6 5 4 3 2

SAMPLE CONNECTION K'r--- *------ IB'-9f(TYP.J

  • 17'. 2 ~(TYP.)

---1

~

H LINE C ONLY I --

.~ ~66~ \!~~-,$~AT . l---

5-94 (TYP.)

./ LINEAtD REACTOR VENT I W.P.dlt EL. B'-r;," CON~

ABOVE i!PV INVERT LINE 8U G

_.-W. f: "A"@ {,EL. :;'-6" Al50Vf IZPV INVf~T I

-1!>8~4.,

50*-o~..

(erF.)4 I

I" I 54'.10z (LINE A,B,C(D)

F (i!E>)

RCIC CONN.

LINE "8"0NLY

\ -__ --1 24~9"(LJNfA,B.C~D) 23'-6" (TYP.) 01 15 I

~.

(RE~)

17°0f6(1<U:)

-~

E -1 I :BecJ 1s:6'(l1N£ (l?EF:) I 90°

  • rtl ELEVATION A-A

+ '

D 1

4 -0' TYP

~-----~.j (REF)

~ "'-o'ryp

~ (RE.F) 19 180° PLM c CD 0 - INDICATES FIELD WELD (DESIGNATIONS ARE TO !IE USED FOR NOlll-DESTRUCTIVE EUMINATION RECORDS).

RPV - REACTOR PRESSURE VESSEL.

11.P. - WORK POINT B RPV INVEl<'T J;!EF. LINE LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT (L1~;~t,;

(REF) r'l.P. MAIN STEAM PIPING A J___:__ _ --~ LAYOUT INSIDE PRIMARY ELEJ/ATAJN C-C ELEVATION B-B (Et£ t/1U't0'11  !/'; - 8,1 ~IMl~A.t!)

CONTAINMENT FIGURE 5.1-7 8 7 6 5 4 3 2

LGS UFSAR Figure 5.2-1 Deleted

LGS UFSAR

~

a

£ I

I LIMERICK GENERATING STATION UPDATED FINAL SAFETY ANALYSIS REPORT OVERPRESSURE TRANSIENT RESPONSE TO MSIV CLOSURE WITH FLUX WITH SCRAM FLUX SCRAM(ODYN)

(2 SRVS OOS)

FIGURE 5.2-2 Rev.

Rev.161009/12 10/00

140

- - - - 678 CRD IN PERCENT 120 100 50

~

z 0

!/')

0 Cl..

Cl 80 0 40 er

...J 0

er z

0

(..)

60  ;;

30 J.

I-I-

u w

a:

40 ~

20 <

a:

u Vl 20 10 o-..-u-----....

0 ----------------------------------..._

2 3

___________.o 4 5 TIME (sec)

LIMERICK GENERATING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTROL ROD POSITION VERSUS TIME CHARACTERISTICS FIGURE 5.2*3 Rev.5, 4/96

LGS UFSAR Figures 5.2-4 and 5.2-5 Deleted

REACTOR VESSEL LINE RELi EF MAIN STEAM VALVE ISOLATION VALVES

-~FLOW RESTRICTOR SUPPRESSION POOL LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SAFETY/RELIEF VALVE SCHEMATIC ELEVATION FIGURE 5.2-6

MAIN STEAMLINES MAIN STEAM ISOLATION VALVES REACTOR VESSEL LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT MSRV AND STEAMLINE SCHEMATIC FIGURE 5.2-7

DIAPHRAGM TYPE PNEUMATIC ACTUATOR

- - - - BELLOWS

._...--FIRST STAGE

\.......J-~~nu.-----., PILOT DISC SECOND STAGE----1--....L PILOT DISC MAIN DISC

~----t--------------------===:::J]J ¢:::INLET DISCHARGE BODY PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT THREE-STAGE, PILOT ACTUATED, SAFETY RELIEF VALVE (VERTICAL DISCHARGE)

FIGURE 5.2-8 Rev. 10 10/00

STEAM (s)

---'1--, r----

FEEDWATER ~ *~,~~**e I ~:iSSURE GENERATOR I TURBINE I I I TO STEAM JET I AIR EJECTOR I

I CLEANUP COOLING PUMP WATER CONTROL ROD DRIVES REACTOR WATER CLEANUP LIMERICK GENERATING STATION UNITS 1 & 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL BWR FLOW DIAGRAM FIGURE 5.2-9 Rev. 10 10/00

10

~It>

N I-ct E

CJ 0

.J:.

E

.3-w u

z ct I-u 0

z 0

u u

u..

u w

Cl.

en 4 5 6 7 8 9 10 pH (AT 250C)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONDUCTANCE VS pH AS A FUNCTION OF CHLORIDE CONCENTRATION OF AQUEOUS SOLUTION AT 25°C FIGURE 5.2-10

LGS UFSAR Figure 5.2-11 Deleted

800 800 400 200

~

100 80 0

-E 60

~

~

2 w

<(

40

~

IX ~

~

<(

w 20

..J 15 10 8

6 AXIALLY ORIENTED CRACK 4

SATURATED WATER SYSTEM AT 1000 Psig ASTERISKS DENOTE CRACK OPENING OF 0.1 in.

2 0 4 8 12 16 20 24 28 32 CRACK LENGTH (in.)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CALCULATED LEAK RATE AS A FUNCTION OF CRACK LENGTH &

APPLIED HOOP STRESS FIGURE 5.2-12

8 11 9 DATA CORRELATION Qs =CRITICAL CRACK LENGHT (in.)

D = MEAN PIPE DIAMETER Oh= PIPE HOOP STRESS 10 MATERIAL* A1064 10 9

12 8

0 Qc/D = 15,000/0h IO 7

e )( 15 M

b

~ )(

t::>

....... 6 ~

0 5

20 4

25 3

2 D,

(UNFLAWED) 0 0

GE DATA (-6<>°F)

BMI DATA 30 40 50 60 70 0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 Qc/D LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT AXIAL THROUGH-WALL CRACK LENGTH DATA CORRELATION FIGURE 5.2-13

SPARE (TEMPORARY INSTRUMENTATION)

VENT NOZZLE REACTOR VESSEL HEAD VESSEL HEAD STUD DRYER ASSEMBLY VESSEL HEAD NUT LIFTING LUGS STEAM DRYER ASSEMBLY STEAM DRYER AND SHROUD HEAD ALIGNMENT ANO GUIDE BARS STEAM SEPARATOR AND STANDPIPE ASSEMBLY DAYER SEAL SKIRT FEEDWATEA INLET NOZZLE SHROUD HEAD VESSEL WALL CORE SPRAY SUPPLY HEADER FEEOWATER SPARGER CORE SPRAY SUPPLY HEADER SHROUD HEAD HO.LO DOWN BOLTS TOP FUEL GUIDE SHROUD HEAD BOLT--~ ~~- LPCI NOZZLE/COUPLING

.._.._:_:=~-++--- SHROUD HEAD ALIGNMENT PINS SUPPORT LUGS 1 JET PUMP NOZZLE ASSEMBLY ~~~!!!~~ CORE SPRAY SPARGER RISER BRACE -----l_l_Cl,£ rmm---t--14--- FUEL ASSEMBL y

~-1-...-.;...JI CONTROL ROD IN CORE FLUX MONITOR FL.;~l.. SUPPORT PIECE JET PUMP BODY -----<~~

~~~~:!~+---FLOW INLET INTO FUEL BUNDLE RECIRCULATING WATER INLET NOZZLE CORE SHROUD JET PUMP INLET RISER CORE PLATE ASSEMBLY CORE PLATE SUPPORT JET PUMP DIFFUSER--___;....;..._-

r--n-::;:;...-+-- VELOCITY LIMITER CORE DIFFERENTIAL DIFFUSER SEAL RING PRESSURE TAP & LIQUID ANO SHROUD SUPPORT PLATE CONTROL INLET NOZZLE RECIRCULATING WATER OUTLET NOZZLE VESSEL SUPPORT SKIRT CONTROL ROD GUIDE TUBE INCORE FLUX MON ITOA HOUSING SUPPORT STRUCTURE CONTROL ROD DRIVE HOUSING LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL CUTAWAY DIAGRAM FIGUR.E 5.3-1 Rev 08 11/98

HIGHWATER LEVEL ALARM 566.5 (L7) ~

HIGH WATER LEVEL TRIP 581.5 (LS)

NORMAL WATER LEVEL 562.0 ( L5)

LOW WATER LEVEL SCRAM 540.0 ( L3)

LOW WATER LEVEL ALARM 557.5 (L4)

LOW WATER LEVEL TRIP 489.5 ( L2)

SHIELD WALL TOP ACTIVE ,- ECCS INITIATION FUEL 366.31 __/ LEVEL 398.5 ( L 1)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT NOMINAL REACTOR VESSEL W~IERJ~~-VELTRIP_Al\lj)

ALARM ELEVATION SETTlNGS FIGURE 5.3-2

UPPER MOUNTING BRACKET POSITIVE SPRING LOADED I I LOCKING DEVICE l-_-d ENLARGED VIEW B-B DETAIL "C" SHROUD VESSEL WALL CORE MIDPLANE LOWER MOUNTING BRACKET ENLARGED VIEW A-A LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SURVEILLANCE CAPSULE FIGURE 5.3-3

1400 A12A B

, c J

1300 1200 j J '

1100 ia..

0 1000

c 900 CL 0

=

~

800

~ +----+--+---+---+-+-+--+-+---+...,_-+---4 A, 8 1 C - CORE BELTUNE AFTER

~ 700 ASSUMED 69°F SHIFT FROM AN INITIAL PLATE RTNOT OF 209F m 600

~ A* SYSTEM HYDROTEST t: WITH FUEL IN THE VESSEL

!i 500 B - NON-NUCLEAR w

~ HEATUP/COOLDOWN LIMIT

=

)

w 0::

400 C - NUCLEAR (CORE CRITICAL)

A. J312PSIG LIMIT 300 200 A ' c/

,.._--+--+---+-.-.i~-~--+---+--+--tTO CURVES A, B, CARE VALID UP 32 EFPY OF OPERATION I jv

/ CURVE An IS VALID UP TO 100 ~ e~P,~._l/-iofL---+---~-t---+--t22 EFPY OF OPERATION 0

0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ( °F)

LIMERICK GENERA TING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT MINIMUM TEMPERATURE REQUIRED VERSUS REACTOR PRESSURE (UNIT 1)

FIGURE 5.3-4 Rev. 11 9/02

1400 1300 1200 1100 CJ 0

E; c 1000

~

I:

~ 900 -~----~4--.-..;.-----1-1~-!l~..,--1-T~--~--_._---~---=~------1 0

..J w

~ ~o  ;

~ i------------------------.1

~

t;

~

o 7 0 I

A, B. C - CORE BELTUNE AFTER ASSUMED s2*F SHIFT FROM~ INITIAL PLATE RTi.oT a:: 600 OF 40*F

~

t= IA -SYSTEM HYDROTEST

~ 500 I WITH FUEL IN THE VESSEL a: l1 B - NON.NUCLEAR

~ 400 HEATUPJCOOlOOWN LIMIT 0  !

W I ff J12 PSJG  : C - NUCLEAR (CORE CRITICAL) 300 -t====~==-~::.._,:.=::..;._---..i* LIMIT 200 ...._____..,l-".l,..,_--1---....---~; CURVES A 8. CARE VALID UP

~ TO 32 EFPY OF OPERATION 100 0

0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 MINIMUM REACTOR VESSEL METAL TEMPERATURE ( °F)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT MINIMUM TEMPERATURE REQUIRED VERSUS REACTOR PRESSURE (UNIT 2)

Sheet 1of1 FIGURE 5.3-5 Rev.11 9/02

LGS UFSAR Figures 5.3.5 Sheet 2 of 2 Deleted

LGS UFSAR Figure 5.3-6 Deleted

15° 135° 255° 400.Y2"

~------ - ---- + 366.31" HEAT NO. HEAT NO. HEAT NO.

C7677-l C7689-1 c C7698-l cc BELTLINE

> ACTIVE FUEL ZONE 77 .3° 197. 3° 317. 3° AB

-- - - - - - - - - - -* - - -- - _...., - ...... +- 216.31 11 HEAT NO. HEAT NO. HEAT NO.

C7688-2 C7698-2 C7688-l 126 1/2 11. . __ _ _ _ _ ____.,._ _ _ _ _ _ _ _ _ _ _ _ _ ____,a.________________...___---'

SHOP w'ELDS: SEAMS BA, BB, BC, BO, BE, BF FIELD WELDS: SEAM AB LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT BELTLINE PLATE AND WELD SEAM LOCATIONS (UNIT 1)

SHEET 1OF2 FIGURE 5.3-7

15° 135° 255° 400.}'2" HEAT NO. HEAT NO. HEAT NO.

C9526-1 LL.

C9526-2 c C9569-2 UJ cc co co BELTLINE ACTIVE FUEL ZCNE I 77 .3° t

AB 197. 3° 317.3°

- ---- - - -- - - - - - - --- ~ 216.31 11 HEAT NO. HEAT NO. HEAT ~O.

83312-1 83416-1 C9621-2 co ~

co ~ co 126 l /~"

SHOP w'ELDS: SEAMS eA, BB, BC, PD, BE, BF FIELD WELDS: SEAM AB LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT BELTLINE PLATE AND WELD SEAM LOCATIONS (UNIT 2)

SHEET2 OF 2 FIGURE 5.3-7

GROOVES Submerged Arc - Flat SMA - Flat &Vertical

\ KJ rn The spacer bar shall be of the same material as the base material.

) VJ ~n

~ x~ DO WELD BUILDUP LJjJ )JjJ LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT GENERAL WELDING TECHNIQUES FIGURE 5.3-8

RECIRCULATION INLET

'\.'<<.~~L-- RECIRCULATION OUTLET MANIFOLD RECIRCULATION SHUTOFF VALVE PUMP SHUTOFF VALVE ISOMETRIC DRIVING FLOW ~

ELEVATION LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT RECIRCULATION SYSTEM ELEVATION AND ISOMETRIC (SHEET 1 OF 2)

FIGURE 5.4-1

H =HEAD (ft)

N = NPSH (ft) x ............... _ __ x 10)

E =EFFICIENCY(%

~ X =RATED CONDITIONS 800 x

u z

w 600

~

LI.

LI.

w

c f

z Q

ct w

c 400 200 N---------------------

oa....______...._________.._________.________..________..._______..._________..________.

0 10 20 30 40 50 60 70 80 PUMP FLOW (gpm)(thousands)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT RECIRCULATION PU~P HEAD, NPSH, AND EFFICIENCY CURVES FIGURE 5.4*3

THROAT OR MIXING SECTION Q. . . . . ~_ __.,,,,___.~

---......... --- --=

[

SUCTIO.N-............. .,L

~---

FLOW~ <S ----

DRIVING FLOW__.,. -

DRIVING NOZZLES w

IC en en

r DRIVING FLOW DRIVING w FLOW ~p IC D..

SUCTION

______________ l FLOW ~p SUCTION FLOW LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT OPERATING PRINCIPLE OF JET PUMP FIGURE 5.4-4

NO AMAL STEAM WATER SEPARATORS LEVEL

.. . .. A ... ...

_ ~- ~

,E~:~:~ION STRIBUTION

I PLENUM r--- --------- WATER LEVEL AFTER BREAK IN 1

., ...., RECIRCULATION LOOP I

I ACTIVE CORE I

I r l I I I

t. _~_)

~ ---

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CORE FLOODING CAPABILITY OF RECIRCULATION SYSTEM FIGURE 5. 4-5

DOWN STA EAM TAP (1OF2)

UPSTREAM TAP WELD (1OF2)

MAIN STREAMLINE PIPE LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT MAIN STEAMLINE FLOW RESTRICTOR FIGURE 5.4-6

AIR CYLINDER HYDRAULIC DASH POT SPRING GUIDE ACTUATOR SUPPORT AND SPRING GUIDE SHAFT SPRING SEAT MEMBER LEAK OFF CONNECTION CLEARANCE PILOT SPRING PILOT BODY POPPET (PLUG, MAIN DISK)

PILOT SEAT LIMERICK GENERATING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT MAIN STEAM ISOLATION VALVE FIGURE 5.4-7

LGS UFSAR Figures 5.4-8 through 5.4-10 Deleted

ASSUMED FLUSH TIME 300 I 200 100 ooi....-----.li....------1....------1....------1....------,,._------*,----------------------~,

HOURI AFTER CONTROL ROOl INIERTED NOTE: This curve is based on original plant design conditions. Actual cooldown rate will vary depending on system flowrates, coollng water LIMERICK GENERATING STATION temperature, and AHR heat exchanger fouling.

UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT VESSEL COOLANT TEMPERATURE VERSUS TIME (TWO HEAT EXCHANGERS AVAILABLE)

FIGURE 5.4-11 REV. 13 09/06

500 t 400

's

~

~

§ 300 ASSUMED FLUSH TIME

§ I 200 100 o._._______________,,,________..._______..._______......____....,_..________.._______~

0 3 6 8 HOURI AnER CONTROL RODS INIERTED ttQil.:. This curve Is based on original plant design conditions. Actual cooldown rate will vary depending on system flowrates, cooling water temperature, and RHR heat exchanger fouling.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT VESSEL COOLANT TEMPERATURE VERSUS TIME (ONE HEAT EXCHANGER AVAILABLE)

FIGURE 5.4-12 REV. 13 09/06

LGS UFSAR Figures 5.4-13 thru 5.4-14 Deleted

12 11 14 m

BHP 13 ,.,..

lJ 10 12 m 11 z

0 lJ C/I 9 10 m

"'Cll 0

9 ~

m lJ 8 8

"'/.

~ 0 0

'-J 0 6 c

Ill z

~

c 5

~

e 4 40 3 30 z

2 20 ~

NPSHR AT CL SUCTION NOZZLE 10 0 0 0 2 4 5 6 8 9 10 11 12 13 14 15 16 17 GALLONS PER MINUTE (11 10001 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT RHR PUMP CHARACTERISTIC CURVES FIGURE 5.4-15 Rev. 6, 12/96

LGS UFSAR Figures 5.4-16 through 5.4-18 Deleted

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