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

Pressure (psai)

Flow (lb/hr)

Temperature

( ° F)

Enthalpy (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%
  • BASED ON 100% DRY STEAM IN THE STEAM DOME FIGURE 5.1-1 Historical Rev. 16 09/12 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RATED OPERATING CONDITIONS

[3458 MWt]

Figure Marked "Historical" Reference Figure 1.2-84, "Reactor System Heat Balance," for current operating conditions

STEAM DRYERS STEAM SEPARATORS

~RIVING FLO'N __,_.

  • ~CORE RECIRCULATION PUMP A LOWER PLENUM B CORE c UPPER PLENUM AND SEPARATORS D DOME (ABOVE NORMAL WATER LEVEL!

E DOWNCOMER REGION F RECIRC LOOPS ANO JET PUMPS MAIN FEED FLOW FROM TURBINE JET PUMP VOLUME OF FLUID ltt31 3887 2054 1321 7934 5817 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

H G

F E

D c

B A

8 c

+Y 270° _., -

era 7

180°

-x VIEWD-D

-~~;i:Ai~~T~l~~T~

DETAIL A 6

LOOP A tY 2 POLL VALVE. 15*

(LINE. t:..' ~*o* ONLY)

~x o*

I f----1.____ _

/~

-J?o--19 I !r ~SRCVL
~fil~--

1' __

5 D~

VIEW(-C 4

RfFERENCE EQUIPMEN1 DATA RECIRC SYSTEM St'Meo..

REC/RC PUMP sue ION LINE Z8 Pl.Jl\\i1P DISCMARGE UNE

'28" f

RING HEADER f'2" RECIRC RISER LINE (S PER LOOP) 1'2" Ri-JR/S~UTDOWN SuPPl...Y LINE

'20" Rl-IR/51-41.JTOOWN i:<ETURN LINE 1'2.

HPCI SUPPLY LINE 10 KEY MOTOR DIM MAX RPM5 8')°

! t f

~. -MOTOR OVERALL HEIG~H MAX RPMl 111"

~

MAX RPM'i~

i KEY MOTOR DIM.

MA)( RPM3

(;,(."'

f I

I 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" 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" KEY ~R/51-lUTDOWN SUCTION LINE VALVE 1..ENGTM S.S"°'L 5-z*

STEAM~ FEEDWATER SYSTEMS MAIN STE AM LINE u,"

~

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

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

0.D OF PENETRATION FOR 5rEAM LIN~S R:NS.4t" 00.0FPeNETRATION FOR F.w. LINES IPeNtFW 47."

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" I

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

\\

I

\\

3 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PIPE ROUTING OF REACTOR COOLANT SYSTEM AND ASSOCIATED SYSTEMS FIGURE 5.1-5 2

H G

F E

D c

B A

8 r

ll!ECICC PuMP LOOP *A

S*H*

PLAN ELEVATION *A-A" LOOP*~*

SAME AS LOOP *e,' E)(CEPT A':> NOTED 7

.i.

I l t

6

~EC!~C Pr.JMP LOOP'£!,"

<Ro-N:.44\\

.J_.A (lv'l-4) r PLAN 2 10 r

PLAN I z 6'-11 11 5

a*

1*-s*

11

  • IT SEE NOTE 9 L' I 1-- 20** RMR SHUTDOWN j..J SUPPLY 180°

~

~

PLAN 2 ELEVATION 'B-B" LOOP"e!

4 3

LEGEND:

T.L.

INDICATES TANGENT LINE RS RECIRCULATION SYSTEM SUCTION PIPING RD RECIRCULATION SYSTEM DISCHARGE PIPING c=)

0 INDICATES PIPE SPOOL NUMBER INDICATES FIELD WELD (DESIGNATIONS ARE TO BE USED FOR NON-DESTRUCTIVE EXAMINATION RECORDS) t PLAN 2 15'-1~

t PLAtl I LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR RECIRCULATION SYSTEM FIGURE 5. 1-6 2

H G

F E

D c

B A

8 7

180° PLM CD 6

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

./

LINEAtD W.P.dlt EL. B'-r;,"

ABOVE i!PV INVERT LINE 8U

_.-W. f: "A"@ {,EL. :;'-6" Al50Vf IZPV INVf~T 19 23'-6" (TYP.)

-~ 90° 4

1-0' TYP

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

~ "'-o'ryp

~

(RE.F)

ELEJ/ATAJN C-C 5

r--- IB'-9f(TYP.J *

~

SAMPLE CONNECTION K' *------ 17'. 2 ~(TYP.) ---1 LINE C ONLY I

. l---

5-94 (TYP.)

REACTOR VENT I

CON~

RCIC CONN.

LINE "8"0NLY

-1 I

!>8~4.,

50*-o~..

I (erF.)4 I"

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

(i!E>)

I (RE~)

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1

--1 24~9"(LJNfA,B.C~D) 15

~.

17°0f6(1<U:)

-1 I :

1s:6'(l1N£ BecJ (l?EF:) I

  • rtl

+ '

ELEVATION A-A (L1~;~t,;

(REF) r'l.P.

J___:_ __ --~

4 ELEVATION B-B (Et£ t/1U't0'11 !/'; -8,1 ~IMl~A.t!)

3 0

RPV INDICATES FIELD WELD (DESIGNATIONS ARE TO !IE USED FOR NOlll-DESTRUCTIVE EUMINATION RECORDS).

REACTOR PRESSURE VESSEL.

11.P. -

WORK POINT RPV INVEl<'T J;!EF. LINE LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT MAIN STEAM PIPING LAYOUT INSIDE PRIMARY CONTAINMENT FIGURE 5.1-7 2

LGS UFSAR Figure 5.2-1 Deleted

~...

a ; -

£ LGS UFSAR I I --;

FIGURE 5.2-2 Rev. 10 10/00 Rev. 16 09/12 WITH FLUX SCRAM (ODYN)

~

z 0

!/')

0 Cl..

Cl 0 er

...J 0 er

..... z 0

(..)

140

678 CRD IN PERCENT 120 100 50 80 40 60 30 J.

I-I-u <

w a:

40

~

20 a: u Vl 20 10 o-..-u-----.... ----------------------------------..._ ________ ___.o 0

2 3

TIME (sec) 4 5

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

MAIN STEAM ISOLATION VALVES RELi EF VALVE REACTOR VESSEL LINE

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

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

SECOND STAGE----1--....L PILOT DISC MAIN DISC DIAPHRAGM TYPE PNEUMATIC ACTUATOR

BELLOWS

._...--FIRST STAGE

\\.......J-~~nu.-----.,

PILOT 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

CLEANUP PUMP STEAM (s)

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

~

I I

I I

I CONTROL ROD DRIVES TO STEAM JET AIR EJECTOR COOLING WATER 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 pH (AT 250C) 8 9

10 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

-E

~

w

<(

IX

~

<(

w

..J 800 800 400 200 100 80 60 40 20 15 10 8

6 4

2

~

2

~

~

0 4

~

0 -

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

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

11 10 9

8 IO 7

e

)(

~

t::>

6 5

4 3

2 0

8 DATA CORRELATION 9

Qs =CRITICAL CRACK LENGHT (in.)

D = MEAN PIPE DIAMETER Oh= PIPE HOOP STRESS MATERIAL* A1064 D,

(UNFLAWED) 0.2 0.4 0.6 0.8 10 12 0

Qc/D = 15,000/0h M

15 b

)(

~

0 20 25 0 GE DATA (-6<>°F) 30 0 BMI DATA 1.0 Qc/D 1.2 40 50 60 70 1.4 1.6 1.8 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 DRYER ASSEMBLY LIFTING LUGS STEAM DRYER ASSEMBLY DAYER SEAL SKIRT SHROUD HEAD CORE SPRAY SUPPLY HEADER SHROUD HEAD HO.LO DOWN BOLTS SHROUD HEAD BOLT--~

SUPPORT LUGS JET PUMP NOZZLE ASSEMBLY RISER BRACE -----l_l_Cl,£ IN CORE FLUX MONITOR JET PUMP BODY -----<~~

RECIRCULATING WATER INLET NOZZLE JET PUMP INLET RISER JET PUMP DIFFUSER--___;....;..._-

DIFFUSER SEAL RING ANO SHROUD SUPPORT PLATE VESSEL SUPPORT SKIRT INCORE FLUX MON ITOA HOUSING REACTOR VESSEL HEAD VESSEL HEAD STUD VESSEL HEAD NUT STEAM DRYER AND SHROUD HEAD ALIGNMENT ANO GUIDE BARS STEAM SEPARATOR AND STANDPIPE ASSEMBLY FEEDWATEA INLET NOZZLE VESSEL WALL FEEOWATER SPARGER CORE SPRAY SUPPLY HEADER TOP FUEL GUIDE

~~- LPCI NOZZLE/COUPLING

.._.._:_:=1~-++--- SHROUD HEAD ALIGNMENT PINS

~~~!!!~~

CORE SPRAY SPARGER rmm---t--14--- FUEL ASSEMBL y

~-1-...-.;...JI CONTROL ROD FL.;~l.. SUPPORT PIECE

~~~~:!~+---FLOW INLET INTO FUEL BUNDLE CORE SHROUD CORE PLATE ASSEMBLY CORE PLATE SUPPORT r--n-::;:;...-+-- VELOCITY LIMITER CORE DIFFERENTIAL PRESSURE TAP & LIQUID CONTROL INLET NOZZLE RECIRCULATING WATER OUTLET NOZZLE CONTROL ROD GUIDE TUBE 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) ~

NORMAL WATER LEVEL 562.0 ( L5)

LOW WATER LEVEL ALARM 557.5 (L4)

SHIELD WALL TOP ACTIVE FUEL 366.31 __/

HIGH WATER LEVEL TRIP 581.5 (LS)

LOW WATER LEVEL SCRAM 540.0 ( L3)

LOW WATER LEVEL TRIP 489.5 ( L2)

ECCS INITIATION 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

I I

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

1400 1300 1200 1100 i

a.. 0 1000

c CL 900 0...

"' = 800

~

~

~ 700 m 600

~

t: !i 500 w

~

) = 400 w

0::

A.

300 200 100 0

A12A B

c J

j J

+----+--+---+---+-+-+--+-+---+...,_-+---4 A, 8 1 C - CORE BELTUNE AFTER ASSUMED 69°F SHIFT FROM AN J312PSIG A

INITIAL PLATE RT NOT OF 209F A* SYSTEM HYDROTEST WITH FUEL IN THE VESSEL B - NON-NUCLEAR HEA TUP/COOLDOWN LIMIT C - NUCLEAR (CORE CRITICAL)

LIMIT

' c/

CURVES A, B, CARE VALID UP

,.._--+--+---+-.-.i~-~--+---+--+--tTO 32 EFPY OF OPERATION I

jv

/

CURVE An IS VALID UP TO

~

e~P,~._l/-iofL---+---~-t---+--t22 EFPY OF OPERATION 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

CJ 0

E; 1400 1300 1200 1100 c

1000

~

I:

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

..J w

~

~o

~

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

~

o

A, B. C - CORE BELTUNE t;

7 0 I

AFTER ASSUMED s2*F SHIFT

~

FROM~ INITIAL PLATE RT i.oT a::

600 OF 40*F

~

I t=

A -SYSTEM HYDROTEST

~ 500 I WITH FUEL IN THE VESSEL a:

l B - NON.NUCLEAR

~ 400 1 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.

C7677-l 77.3° AB HEAT NO.

C7689-1 197. 3° c

cc HEAT NO.

C7698-l 317. 3° BELTLINE

> ACTIVE FUEL ZONE

+-

216.31 11 HEAT NO.

C7688-2 HEAT NO.

C7698-2 HEAT NO.

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" - - - - - - - -* - - -

126 HEAT NO.

UJ C9526-1 LL.

cc co I

77.3° t

AB HEAT NO.

HEAT NO.

83312-1 83416-1 co co l /~"

SHOP w'ELDS: SEAMS eA, BB, BC, PD, BE, BF FIELD WELDS: SEAM AB HEAT NO.

C9526-2 197. 3°

~

c co HEAT

~O.

C9621-2 HEAT NO.

C9569-2 BELTLINE ACTIVE FUEL ZCNE 317.3°

~ 216.31 11

~

co 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

\\ KJ

) VJ

~ x ~

LJjJ GROOVES Submerged Arc - Flat SMA - Flat & Vertical rn

~n DO

)JjJ The spacer bar shall be of the same material as the base material.

WELD BUILDUP LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT GENERAL WELDING TECHNIQUES FIGURE 5.3-8

RECIRCULATION INLET MANIFOLD SHUTOFF VALVE DRIVING FLOW ~

'\\.'<<.~~L-- RECIRCULATION ISOMETRIC ELEVATION OUTLET RECIRCULATION PUMP SHUTOFF VALVE LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT RECIRCULATION SYSTEM ELEVATION AND ISOMETRIC (SHEET 1 OF 2)

FIGURE 5.4-1

u z w

~

LI.

LI.

w -

c f z -

Q ct w

c 800 600 400 200 N---------------------

H =HEAD (ft)

N = NPSH (ft)

E =EFFICIENCY(% x 10) x...............

~

X =RATED CONDITIONS x

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 SUCTIO.N-............. Q

..........,L ____ ~

_ __.,,,,___.~

--=

~---

DRIVING FLOW__.,.

FLOW~ <S DRIVING NOZZLES w

IC en en w

IC D..

r DRIVING FLOW SUCTION FLOW DRIVING FLOW ~p SUCTION FLOW ~p

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

NO AMAL WATER LEVEL r---

1 I

I I I r

l I

I I

t.. _~_)

STEAM SEPARATORS A

~

STRIBUTION

_ ~ -

,E~:~:~ION

I PLENUM WATER LEVEL AFTER BREAK IN RECIRCULATION LOOP

~ ---

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

MAIN STREAMLINE PIPE UPSTREAM TAP (1OF2)

DOWN STA EAM TAP (1OF2)

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

CLEARANCE PILOT SPRING PILOT AIR CYLINDER HYDRAULIC DASH POT SPRING GUIDE ACTUATOR SUPPORT AND SPRING GUIDE SHAFT SPRING SEAT MEMBER LEAK OFF CONNECTION 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

I ASSUMED FLUSH TIME 300 200 100 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 temperature, and AHR heat exchanger fouling.

LIMERICK GENERATING STATION 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

~

ASSUMED FLUSH TIME s

~

300

§

§

... 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 10 9

8

~

0 6

c Ill z

~

c 5

~ e 4

3 2

0 0

2 4

5 6

BHP 8

9 10 GALLONS PER MINUTE (11 10001 11 14 m

13 lJ,.

12,..

m 11 z 0

lJ 10 C/I m

"'Cll 0

9

~

m 8

lJ

'/.

0 0

'-J 40 30 z

20 ~

NPSHR AT CL SUCTION NOZZLE 10 0

12 13 14 15 16 17 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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