ML21133A056

0 to Updated Final Safety Analysis Report, Chapter 6, Figures

ML21133A056
Person / Time
Site:	Limerick
Issue date:	04/29/2021
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
Download: ML21133A056 (88)

Text

21M/4" O.D. II 518" JET TESTP 'l

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ASBY.

~.o I-BARS 1" 111 EQUALLY SPC'D io. SHOP PAINT

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h TO THIS DIA.

LIFTING LUG 21*1/40.0.115/8'"

TEST'l.

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PRIMARY CONTAINMENT I

I., * ".. :, *.: :

DIAPHRAGM SLAB i...;.._-~1,-:~~=. - -,,. '

NOTE:

34" O.D. X,,.;,.. _)

'l.RING

14**0.o. x 1/2"

'I.RING FOR TYPE 1-A ONLY 11.. f *318 WALL PIPE

/

18"fP*150#F. F. FLANGE HOLES STRADDLE VERTICAL Cl.

"" TYPE I ONLY 10"4>-150#

F.F. FLANGE HOLES STRADDLE VERTICALq_

10" f SCH ED 40 PIPE FOR TYPE I 8t 1-A 24* o.o. x all"'

WALL PIPE TYPE I (TYPICAL OF 6)

TYPE IA (TYPICAL OF 4)

TYPE 11 (TYPICAL OF 57)

This UFSAR figure is provided to delineate the primary (typical) structural concepts, arrangements, and elements relied upon to perfonn the safety related functions of the subiect structures. For detail design features, dimensions, and as-built concition of the structures, see design <i'awing number(s):

8031-C-293.

I IEE DETAIL@ON IHEET 2 FOR TEE AND VACUUM RELIEF VALVE MOUNTING FLANGE

.. THIS AREA CTYPE 1A ONLY) i TYPE 111 (TYPICAL OF 20)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DOWNCOMER DESIGN DETAILS (SHEET 1 OF 2)

FIGURE 6.2-1

HBD-715-1 HBD-815-1 NOTE:

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I ELEVATION FOR TYPE IA ONLY DETAIL @

FULL PENET.

---~ Pl-A-LH 100% RTOR UT (TYP)

MOUNTING FLANGE FOR PRIMARY CONTAlt!fMENT VACUUM R-E:LIEF VALVE ASSEMBLIES If EL 231'-0"

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24_": ;.15()11. W.N.R.F.* FLANGE HOLES STRADDLE VERTICLE ct_

---

24.X 24 TEE X 0.375 WAt,.l T.l:H.C K~ ESS LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT This UFSAR figure is provided to delineate the primary (typical) sb'uctural concepts, arrangements, and elements relied upon to perform the safety related functions of the subject sb'Uctures. For detail design features, dimensions, and as-built condlion of the structures, see design crawing number(s):

8031-C-293.

DOWNCOMER DESIGN DETAILS (SHEET 2 OF 2)

FIGURE 6.2-1

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1 TIME hnl The information presented in this figure is historical and is based on the original design basis conditions and does not represent current plant conditions or methodology used to analyze the containment response following a LOCA. Refer to Section 6.2.1.8 for the current analysis results and methooology.

I 8

9 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT EFFECTIVE SLOWDOWN AREA FOR RECIRCULATION LINE BREAK FIGURE 1.2-2 Aev.5, 4/96

20 tO ow C"N -~---=======-

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~*-----'-.....l.--"'-1~fiOO~~'ooo 0.7 10 NOTE:*

TIME lwcl The Information presented in this figure is historical and is based on the original design basis conditions. Refer to Figure 6.2-3A for the recirculation line break results for

• currnnt plant concfh:ions.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT-TERM CONTAINMENT PRESSURE RESPONSE FOLLOWING RECIRCULATION LINE BREAK FIGURE 6.2-3 Rev.5, 4/96

LGS Pt£AATE PRES$URE: RE:SPONS~

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LIMERICK GENERATION STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PRESSURE RESPONSE AS A FUNCTION OF TIME FIGURE 6.2-3A REV. 5, 4/96

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• ORYWELL 200 SIJ>PRESSlON POOL 0 0~.,--........................... ~---'-....l.-'-...U.U.~~:----1.-.J...J..J...U~~--.L-..L....UL..UUJJ 600 000 NOTE:

TIME (He)

The information presented in this figure is historical and is based on the original design basis conditions and to analyZe the CQntainmerU response following a LOCA.

Refer to F"tgure 6.2-4A for the recitcUiation line break results for current plant conditions.

LIME RICI( GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAF£TY ANALYSIS REPORT SHORT-TERM CONTAINMENT TEMPERATURE RESPONSE FOLLOWING RECIRCULATION L1NEBREAK FIG 6.2-4 Rev 08 tv98

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LGS AERATE TaftRAT~ RESP 1>2P/OOF 350.

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ll"f~ICK GENERATION STATION UNITS I AHO 2 UPDATED FINAL SAFETY ANALYSIS REPORT TEHPERATURE RESPONSE AS A FUNCTION Of TJH£ (al Rerele Power Condlllons)

FIGURE 6.2-4A Rev 08 D/98

0

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Tt!\\11£ IV'0 lal 41 lPCI. 2 CS SYSTEM. 2 HX IWITH CONTAINMENT SPRAY I fbl 1 lPCI., CS SYSTEM. I HX IWITM CONTAIN,..ENT SPRAYI lei 2 LPCI, I CS SYSTEM. 1 HX INOCOlllT.AIN~UNT SPRAY!

llnL.....1......J.......1-LJ.l.U. ____..1.. __ j_..l.....Ll..l.J..J.J_ __ ___JL..--1..--1-J.-1...J..J..J..LI~~. ____.i....__.--'_.,-'-....._~1~

1. 101 10.l 10*

NOTE:

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The information presented in this figure is historical and is based on the original design basis conditions. Refer to Figure 6.2-9A for the Case C results for current plant conditions. The results for Cases A, B, and C shown in this figure do not reflect the current containment analysis, but reasonably represent the general characteristics and relative differences between the three cases.

LIMER ICIC GENERA TING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG-TERM SUPPRESSION POOL TEMPERATURE RESPONSE FOLLOWING RECIRCULATION LINE OR MAIN STEAM LINE BREAK FIGURE 6.2-9 Rev.5. 4/96

(-SP TEMPI

&&.. 2.00E+Q2 r--------r-------1------~:J---====~...... ~--J fB 0

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~ 1.ooe+02.-~--~--------~t----------~-----l-----------------.l---------~------l 0.00E+OO -r---------.f-----------1---------J.----------1 100 1000 LOG TIME *Sl!C 10000 100000 LIMERICK GENERATION STATION UNITS1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TeRM SUPPRESSION POOL TEMPERATURE RESPONSE* CASE CAT 3528 MWl FIGURE 6.2*9A REV. 13 09f08

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s 4*1 4 LPCI. 2 CS SYSTEM, 2 HX (WITH CONTAINMENT SPAAYI lbl 2 l.PCI. 1 CS SYSTtM, 1 HX fWITH CONTAINMENT SPRAY.I lc:l 2 u*c1.1 CSSYSTEM.1 H)( fNOCONTA.INMENT SPRAYI 1 ~2.-1-~.._..J,,_...t-.l.,.,,l...U.la*l-OJ ____ i.,,_....1......r.....&.-'-.U.*1~~-----'---"'-...i...;._,.....,....,,_1.~-----'---.._....._..._.........._1~

NOTE:

TIME heel The information presented In this figure is historical and is based on the original design basis conditions. Refer to Section 6.2. 1. 1.3, only Case C was reanalyzed for current plant conditions. The results for Cases A. B, and C shown in this figure do not reflect the current containment

analysis, but reasonably represent the general characteristics and relative differences between the three cases.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT RHR HEAT REMOVAL RATE FOLLOWING RECIRCULATION LINE OR MAIN STEAM LINE BREAK FIGURE 6.2*10 Rev.5, 4/96

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A TlllllE 1-1 The information presented in this figure is historical and is based on the original design basis conditions. Refer to Section 6.2.1.8 for the current analysis results and methodology. The results shown here reasonably represent the general characteristics of the event.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT EFFECTIVE BLOWDOWN AREA FOR MAIN STEAM LINE BREAK FIGURE 6.2*11 Rev.5, 4/96

NOTE:<

DflYWILL The information presented in this figure is historical and is based on the original design basis conditions.

As described in Section 6.2.1.1.3, the main steam line break was not reanalyzed for the current conditions; however, the results reasonably represent the general characteristics of the main steam line break.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT-TERM CONTAINMENT PRESSURE RESPONSE FOLLOWING MAIN STEAM LINE BREAK Rev.5, 4/96

DR'l'WfLL SU"'Rf!>SION POOL 100~-----------------------------~

~------.-.----........ ~------....... ----................ i.----...i...--i.--i......i..~...u..i......---..1..--'--~....... ~

• O NOTE:

111 1 flUf '""

The information presented in this figure is historical and is based on the original design basis conditions.

As described in Section 6.2.1.1.3, the main steam line break was not reanalyzed for the current conditions: however, the results reasonably represent the general characteristics of the main steam line break.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT-TERM CONTAINMENT TEMPERATURE RESPONSE FOLLOWING MAIN STEAM LINE BREAK FIGURE 1.2-13 Rev.5, 4/96

JO 20 10 NOTE:

O""IWILL IUf'P"EISION CHAMBER l(lQ TIME twcl The information presented in this figure is historical and is based on the original design basis conditions.

As described in Section 6.2.1.1.3, the main steam line break was not reanalyzed for the current conditions: however.

the results reasonably represent the general characteristics of the main steam line break analysis results.

1000 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT-TERM CONTAINMENT PRESSURE RESPONSE FOLLOWING AN INTERMEDIATE SIZE BREAK (0.1 ft2 LIQUID BREAK)

FIGURE 6.2-14 Rev.5, 4/96 Rev. 15, 09/10 The information presented in this figure is historical and is based on the original design basis conditions. As described in Section 6.2.1.1.3, the pipe break was not reanalyzed for the current conditions; however, the results reasonably represent the general characteristics of the pipe break analysis results.

37!1 JOO 1~

150 225 0:

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150 125 100

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llUPl'IUWIOl'f POOL 10,

NOTE:

101 10' ltMf tv..-l The Information presented in this figure is historical and is based on the original design basis conditions.

As described in Section 6.2.1.1.3, the main steam line break was not reanalyzed for the current conditions; however, the results reasonably represent the general characteristics of the main steam line break analysis results.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT-TERM CONTAINMENT TEMPERATURE RESPONSE FOLLOWING AN INTERMEDIATE SIZE BREAK (0.1 ft2 LIQUID BREAK)

Rev.5, 4/96 Rev. 15, 09/10 The information presented in this figure is historical and is based on the original design basis conditions. As described in Section 6.2.1.1.3, the pipe break was not reanalyzed for the current conditions; however, the results reasonably represent the general characteristics of the pipe break analysis results.

REACTOR VESSEL SUPPRESSION POOL LIMERICK GENERATING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT SCHEMATIC OF ANALYTICAL MODEL FOR RHR CONTAINMENT COOLING SYSTEM FIGURE 6.2-16

DRYWELL VAPOR REGION M IPl'llY

• TouT RHRHX M spray

@Ts LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT MODEL FOR ANALYSIS OF INADVERTANT DRYWELL SPRAY ACTUATION FIGURE 6.2-17

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T~ION---1 lfilTS 1 ANJ 2 UPDATED FINAL SAFETY ANALYSlS REPORT ORYWELL PRESSURE RESPONSE TO SPRAY ACTUATION FIGURE 6.2-19 Rev. 1 July/cu

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~--~~----...... ------------1 LIMERICK GENERATING STATI~

Lr.I TS 1 AND 2 UPDATED F[NAL SAFETY ANALYSIS REPORT ORYWELL TEMPERATURE RESPONSE TO SPRAY ACTUATION FIGURE 6.2-20 Rev. 1 Julyl'H Z:\\MEO!\\ 0602020.DGN

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a:i 0.2 UNACCEPTABLE NOTE:

BREAK AREA lft2l The Information presented in this figure is historical and is based on the original design basis conditions.

As described in Section 6.2.1.1.3, the main steam line break was not reanalyzed for the current conditions; however, the results reasonably represent the general characteristics of the main steam line break analysis results.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT MAXIMUM ALLOWABLE STEAM BYPASS LEAKAGE FLOW AREA FIGURE 6.2-21 Rev.s, 4/96

NOTE:

LIQUID TIME h""I The information presented in this figure is historical and is based on the original design basis conditions and does not represent current plant conditions or methodology used to analyze the containment response following a LOCA. Refer to Section 6.2.1.B for the current analysis methodology.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL LIQUID BLOWOOWN FLOW RATI; FOLLOWING RECIRCULATION LINE BREAK FIGURE 6.2*22 Rev.5, 4/96

0 oi;-------------..._ __.._.....;. __ i.._..L-..L-~1*~*----1------l..------L---..ll..---L--J.....J m

NOTE:

TIMF f\\,... t The information presented in this figure is historical and Is based on the original design basis conditions and does not represent current plant conditions or methodology used to analyze the containment response following a LOCA. Refer to Section 6.2.1.8 for the current analysis methodology.

LIMERICK GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL STEAM SLOWDOWN FLOW RATE FOLLOWING RECIRCULATION LINE BREAK FIGURE 6.2*23 Rev.5, 4/96

NOTE:

n-..Ehttl The information presented in this figure is historical and is based on the original design basis conditions.

As described in Section 6.2.1.1.3. the main steam line break was not reanalyzed for the current conditions.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL BLOWDOWN FLOW RATE FOLLOWING MAIN STEAM LINE BREAK FIGURE 6.2-24 Rev.5, 4/96

l*I FUEL TEMPERAT~f lhl VESSf.L WALL HMPE.. ATURf; ltl llllTlR... AL STRUCTURE TE"'PERATURf.

JOO 1mi-.. ______......,,....... ______............... w.i.. __

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....-_._..._.,.....,.~

101 NOTE:

TIMF h,.n The information presented in this figure is historical and is based on the original design basis conditions. The current recirculation line break results are discussed in Section 6.2.1.8. The results presented here reasonable represent the general characteristics of the current recirculation line break analysis results.

LIMERICtc GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL TEMPERATURE RESPONSE FOLLOWING RECIRCULATION LINE BREAK FIGURE 8.2*25 Rev.5, 4/96

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10 NOTE:

111*1 TIMf h*..

• tn1*

I Ill The information presented In this figure is historical and Is based on the original design basis conditions. The current recirculation line break results are discussed in Section 6.2.1.8. The results presented here reasonable represent the general characteristics of the current recirculation line break analysis results.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SENSIBLE ENERGY IN REACTOR VESSEL AND INTERNAL STRUCTURE METALS FOLLOWING RECIRCULATION LINE BREAK FIGURE 6.2-26 Rev.5, 4/96

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e PRIMARY CONTAINMENT REFUELING AREA SECONDARY CONTAINMENT 1's1.

UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT s2.

UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT

\\xX)(

• IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT NOTE:

EOUIPMENTLOC.O.TKIN DRAWING U-11e. AEV.1D(FOA lJ'l!T I), AND U-131, REV. 1S iFOA UNIT t)

WERE USED AS l!ACKGROUND FOO TI-llS AGlRE 6.2*JS LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV.177 FEET FIGURE 6.2-27

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~6.2*34 NOTE: EQUIPMENT LOCATION DRAWING M-117, REV. 9(FOR UNIT 1), AND M-132, REV. 9(FOR UNIT 2) WERE USED AS BACKGROUND FOR THIS FIGURE 0 c 0

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_:j LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 201 FEET FIGURE 6.2-28

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I NOTE: EQUIPMENT LOCATION DRAWING M-118, REV.17 (FOR UNIT 1),, AND M-133, REV.12 (FOR UNIT 2) WERE USED AS BACKGROUND FOR THIS FIGURE

• '..P.)

PRIMARY CONTAINMENT RI REFUELING AREA SECONDARY

'.j CONTAINMENT

.*s1 t UNIT l REACTOR ENCLOSURE SECONDARY CONTAINMENT S2 !

U1lllT 2 REACTOR ENCLOSURE SECONDARY C()NTA1JNMENT

(

X J IDENTIFICATION NUllAB~~:~~ffi~~~NT OPENINGS IN SECONDnn LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 217 FEET FIGURE 6.2*29

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NOTE: EQUIPMENT LOCATION DRAWING M-119, REV. 24 (FOR UNIT 1), AND M-134, REV. 18 (FOR UNIT 2)

WERE USED AS BACKGRCl.JND FOR THIS FIGURE

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PRIMARY CONTAINMENT REFUELING AREA SECONDARY CONTAINMENT

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UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT

's; UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT

( JOO( )

IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 253 FEET FIGURE 6.2-30

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NOTE: EQUIPMENT LOCATION DRAWING M-120, REV. 22 (FOR UNrT 1), AND M-135, REV. 16 (FOR UNrT 2) WERE USED AS BACKGROUND FOR THIS FIGURE I ____ !.,~*.

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:o* s PRIMARY CONTAINMENT REFUELING AREA SECONDARY CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT

~: UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT xi'T IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT i*~c.~ e LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 283 FEET FIGURE 6.2-31

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PmMARY CONTA!NMENT REFUEUNG AREA SECONDARY CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT IDENTIFICATION NUMBER FOO ACCES~ T OPENINGS IN SECONDARY CONTAINM N

-~....._ ___ _

1. *..,.:1*

NOTE: EQUIPMENT LOCATION DRAWING M-121. REV. 17 (FOR UNIT 1), ANO M-1:36, REV. 9 (FOR UNIT 2) WERE USED AS BACKGROUND FOR THIS FIGURE

©

- -- --0 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 313 FEET

I

~

6-2*34 I

t>JLAOIT I

~

............ 11.

I i

i

~li_...,,,.;;;;~;....~~~-..i

~' ~-. ~-'-""~c~o*~~-"'i NOTE: EQUIPMENT LOCATION DRAWING M-122, REV. 1'4 (FOR UNIT 1),ANDU.137, REV.13 (FOR UNIT 2) WERE USED AS BACKGROUND FOR THIS FIGURE

. WliElt;l

~ PRIMARY CONTAINf.ENT fA)

REFUELING AREA SECOND AR y CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT

~

IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT 6.2*35

..!!J LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 352 FEET FIGURE 6.2-33

H r

I\\

i I 1 '------!-"I

• ~*=3*~-~*

r I

._... ___ --t,,

.......;.-----ii r

r M~

.* 6.2-33

~'-22.L:.?'

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6.2-32 6.2*30 iee:i.oS j~.

1~'1 6.2*28 1UMNE'L i: '**~*

~':'"I

.. _..M.:J.jf>. 6.2*27 0

PRIMARY CONTAINMENT REFUELING AREA SECONDARY CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT

~

IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT NOTE; EQUIPMENT LOCATION DRAWING M*123, REV. 6WASUSEDAS BACKGROOND FOR THIS FIGURE LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE NORTH-SOUTH SECTION VIEW (UNIT 1)

FIGURE 6.2-34

IS 11 i r

'"'.. ~

t.~'"'",t *.

~l**'*O'

-..--.***~t:~~~-*1 1

~;;* tiiiiiif=ti 1

1~~;:.~

~QQ~

r II,

~'

I SECTION 8*6 NOTE: EQUIPMENT LOCATION DRAWING M-108, REV. 5 WAS USED AS BACKGROUND FOR THIS FIGURE tSi.lt

'r' PRIMARY CONTAINMENT REFUELING AREA SECONDARY CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT CBEEJ IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT 6.2*33 6.2*32 6.2*31 6.2-30 6.2*29,,

6.Z*28 6.<'*27 LIMERICK GENERATING STATION UNITS 1 1 AND 2 UPDATED FINAL SAF.ETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE EAST-WEST SECTION VIEW FIGURE 6.2-35

RPV CONTAINMENT DETAIL m*

MAIN STEAM LINE AO MAIN STEAM DRAIN DETAIL (2)

SEE SHEET

..,._____ 2 OF 17 DETAIL (3)

RCIC STEAM SUPPLY HPCI STEAM SUPPLY MO - MOTOR OPERATED TC

- TEST CONNECTION AO

- AIR OPERATED FOR DETAIL (2)

MO CUNfT 1)

TC XFC - EXCESS FLOW CHECK VALVE

_.,.... "'.J.tt:* I MO TC (UNIT 2)

AO

..-...-TC MO

~ #

'MO

~--,

I

/~

I I r *---*

MO LIMERICK GENERA Tit<<; STATION lftlTS 1 ANO 2 l.POATED FINAL SAFETY NW.. YSIS REPORT CONTAINMENT PENETRATION DETAILS

<SHEET 1 OF 17J FIGURE 6.2-36 Rev. 1 July/gl Z1\\MECH\\ 06.02-036.Sl

RPV CONTAINMENT DETAIL (2)

MO r-.,

I I

... A: 1 MO r..,

"'J4:1 TC TC FEEOWATER MO-MOTOR OPERATED TC-TEST CONNECTION AO-AIR OPERATED XFC-EXCESS FLOW CHECK VALVE I

I AO TC LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 2OF17)

FIGURE &.2~36

RPV DETAIL (4)

INST. GAS SUCTION DETAIL (5)

DRYWELL PURGE SUPPLY TIP DRIVE DETAIL (6)

SV-SOLENOID VALVE MO-MOTOR OPERATED TC-TEST CONNECTION AO-AIR OPERATED XP-EXPLOSIVE (SHEAR) VALVE CONTAINMENT TC MO AO AO 9.---, ---l

..,..__TC MO MO TC

.9i l £ l LIMERICK GENERATING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 3OF17}

FIGURE 6.2-38

RPV DETAIL (7)

SUPPRESSION POOL PURGE SUPPLY SERVICE AIR DETAIL (8) 1

.. >r..

DETAIL

x~

(9)

RECIRC LOOP SAMPLE MAIN STEAM SAMPLE MO-MOTOR OPERATED SV-SOLENOID VALVE TC-TEST CONNECTION AO-AIR OPERATED TCK-TESTABLE CHECK VALVE MLC-MANUAL LOCKED CLOSED TC TC CONTAINMENT AO TC TC AO LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 4 OF 17 )

FIGURE 6.2*36 AO AO (Unit 1)

ONLY TC Rev. 19 09/18 (Unit 2)

ONLY AO AO TC

(1)

RPV DETAIL i-----i (10)

STANDBY LIQUID CONTROL DETAIL

~,,)

TC AHR SHUTDOWN COOLING RETURN CS DISCHARGE LPCI INJECTION DETAIL

{12)

WETWELLSAMPLERETUR DRYWELLSAMPLERETURN

& PURGE SUPPLY MO-MOTOR OPERATED SV-SOLENOID VALVE TC-TEST CONNECTION GCK-GLOBESTOPCHECK TCK-TESTABLE CHECK VALVE AO-AIR OPERATED THIS IS A GLOBE VALVE FOR AHR SHUTDOWN COOLING RETURN AND A SPRING LOADED PISTON ACTUATED CHECK VALVE FOR CS LOOP B.

l TC TCK CONTAINMENT MO T

RHR SHUTDOWN COOLING RETURN (ONLY)

TC SV SV LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 5 OF17)

FIGURE 1.2*36 REV. 15, 09/10

RPV CONTAINMENT TC DETAIL

'"x 1;.--___.. _

(13) [x ~ T RECIRC PUMP CW SUPPL V I RETURN DRYWELL CHILLED WATER SUPPL V & RETURN MLC DETAIL.,_ _ __,,,.,"'llC"..,__...,.

(14)

AL TERNA TE RWCU RETURN DETAIL (15)

IUPPRElllON POOL PURGE EXHAUST MO-MOTOR OPERATED AO-AIR OPERATED TC-TEST CONNECTION MLC-MANUAL LOCKED CLOSED SV-SOLENOID VALVE PSV-PRESSURE SAFETY VALVE TC MLC sv TC TC AO MO 9

MO ~t-(

TC l' £h MO li11 TC MO l_l!H f

TC (UNIT 1)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 60F 17)

FIGURE 1.2-31

RPV CONTAINMENT DETAIL

{16)

SUPP POOL AHR PUMP SUCTION DETAIL (17)

HPCI VACUUM RELIEF RCIC VACUUM RELIEF DETAIL (18)

SUPP POOL RHR RELIEF VALVE DISCHARGE PSV-PRESSURE SAFETY VALVE MO-MOTOR OPERATED TC-TEST CONNECTION CK-CHECK VALVE MO MO TC PSV PSV CK CK TC I,,,...

MO i,.

I TC CK CK

' 1,./ I I

MO LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 7OF17)

FIGURE 6.2*36 Rev. 6, 12/96 Rev. 15, 09/10 Note: Unit 1 valve MOs are electrically disconnected and valves locked closed.

Blind Flanges

RPV DETAIL (19)

SUPP POOL RHR RELIEF VALVE DISCHARGE DETAIL (20)

RWCU SUPPLY RHR SHUTDOWN COOLING SUPPLY MO TC CONTAINMENT SPOOL PIECE BLANK~~

MO 1" THICK WELDED PLATE DETAIL 1----A_BA_N_D_O_N_E_D ___ --.--------i (21A)

RPV HEAD SPRAY (UNIT 1 ONLY)

MO - MOTOR OPERA TED TC - TEST CONNECTION PSV - PRESSURE SAFETY VALVE (2) THIS IS A GATE VALVE FOR RHR SHUTDOWN COOLING SUPPLY LIMERICK GENERATING STATION UNITS 1 AND2 UPOA TED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET B of 17)

FIGURE 6.2-36 Rev. 11 9102 Rev. 15, 09/10

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (Sheet 8a of 17)

FIGURE 6.2-36 Rev. 15, 09/10 RPV CONTAINMENT RHR SHUTDOWN COOLING SUPPLY PSV TC MO MO DETAIL (21)

MO - MOTOR OPERATED TC - TEST CONNECTION PSV - PRESSURE SAFETY VALVE

RPV CONTAINMENT DETAIL (22)

INSTRUMENT GAS SUPPLY DETAIL (231 DRYWELL SAMPLE WETWELL SAMPLE DETAIL (241 HPCI TURBINE EXHAUST HPCI PUMP FLUSH HPCI PUMP MIN FLOW CS PUMP MIN FLOW CS PUMP TEST & FLUSH RCIC TUR Bf NE EXHAUST RCIC MIN FLOW RHR PUMP MIN FLOW AO-AIR OPERATED MO-MOTOR OPERATED SY-SOLENOID VALVE TC-TEST CONNECTION SUPP POOL TC TC AO sv sv MO LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 9OF17)

FIGURE 6.2*36

DETAIL (25)

CONTAINMENT SPRAY DETAIL (21)

RPV SUPPRESSION POOL CLEANUP PUMP SUCTION ANO LEVEL INSTRUMENTATION DETAIL (27)

DRYWELL PURGE EXHAUST MO-MOTOR OPERA TED AO-AIR OPERATED SUflP POOL TC-TEST CONNECTION PSV-PRESSURE SAFETY VALVE SV-SOLENOID VALVE CONTAINMENT MO MO MO MO PSV TC

'~

TC MO sv AO TC MO LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 10OF17)

FIGURE 6.2-36

---

..-----------------------------------... ----...,..--~----..---------............

RPV DETAIL (281 CONTAINMENT ORYWELL DRAIN SUMP TC DRYWELL DRAIN SUMP DISCHARGE DETAIL (291 DRYWELL SAMPLE WETWELL SAMPLE DETAIL (301 RHR VACUUM RELIEF MO-MOTOR OPERATED TC-TEST CONNECTION SY-SOLENOID VALVE SUPP POOL AO TC sv SV LIMERICK GENERATING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PEN ET RATION DETAILS (SHEET 11 OF 17)

FIGURE 6.2-36 Rev. 6, 12/96 Rev. 15, 09/10 UNIT 1 ONLY UNIT 2 ONLY BLANK SUPP POOL DETAIL (30A)

RPV CONTAINMENT DETAIL (31)

ILRT DETAIL (31A)

FO DETAIL (32)

~9,

~1 SUMP TANK LEVEL SUMP TANK FLOW INSTRUMNETATION DETAIL (32A)

DEACTIVATED SUMP TANK LEVEL INSTRUMENTATION DETAIL (33)

PRIMARY STEAM DRAIN TC= TEST CONNECTION MO=MOTOR OPERA TED MLC=MANUALL Y LOCKED CLOSED FO=FLOW ORIFICE BLO=BREAKER LOCKED OPEN MO 2

TC TC MLC MLC MO/BLO MLC MO LIMERICK GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 12 OF 17)

FIGURE 6.2-36 Rev. 12 9/04

DETAIL (34)

RPV SUPP POOL RCIC VACUUM PUMP DISCHARGE DETAIL (35)

SUPP POOL RHR MIN RECIRC DETAIL

{36)

SUPP POOL RHR PUMP TEST LINE

&. CONTAINMENT COOLING

& RHR MIN RECIRC MO-MOTOR OPERATED TC - TEST CONNECTION GCK-GLOBE STOP CHECK CONTAINMENT MO MO TC GCK MO TC MO t,,..

.1:

(

....... 'J MO Jl 2

MO

.J1

(

MO t

cir--(

TC

...... I MO

1.

~..

LIMERICK GENERATING STATION UNITS 1 AND 2

(

UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 13OF17)

FIGURE 6.2*36

RPV DETAIL (37)

INSTRUMENTATION CONNECTED TO RPV DETAIL

<38>

SUPPRESSION POOL LEVEL INSTRUMENTATION DETAIL (38Al (UNIT 1 ONL Yl SUPPRESSION POOL LEVEL INSTRUMENTATION DETAIL (3g)

SUPPRESSION POOL PRESS.

INSTRUMENTATION FO r SUPPRESSION POOL SUPPRESSION POOL XFC - EXCESS FLOW CHECK VALVE FD - FLOW ORIFICE MO - MOTOR OPERATED TC

- TEST CONNECTION SV - SOLENOID VALVE CONTAINMENT TC XFC

~.. -~..

TC NOTE: TEST CONNECTIONS ARE INSTALLED UPSTREAM AND DOWNSTREAM OF THE EXCESS FLOW CHECK VALVES AS SHOWN ON THE APPUCABLE P&IO FIGURES.

MO MO MO sv LIMERICK GENERATING STATION UNITS 1 ANJ 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTA[NMENT PENETRATION DETAILS

<SHEET 14 OF 17)

FIGURE 6.2-36 lt-..MECH\\ 06020 36.DGN

DETAIL (40)

RPV INSTRUMENTATION CONNECTED TO RCPB DETAIL (41)

DRYWELL AIR PRESS.

INSTRUMENTATION DETAIL (42)

HPCI & RCIC PUMP SUCTION FO - FLOW ORIFICE MO - MOTOR OPERA TED TC - TEST CONNECTION SUPPRESSION POOL XFC - EXCESS FLOW CHECK VALVE CONTAINMENT MO TC NOTE: TEST CONNECTIONS ARE INSTALLED UPSTREAM AND DOWNSTREAM OF THE EXCESS FLOW CHECK VALVES AS SHOWN ON THE APPLICABLE P&ID FIGURES.

DETAIL (42A)

SUPPRESSION POOL CORE SPRAY PUMP SUCTION PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 15 OF 17)

FIGURE 6.2-36 Rev. 09 11/99 Rev. 15, 09/10 MO

DETAIL (43)

RPV SUPPRESSION POOL SUPPRESSION POOL SPRAY DETAIL (44)

RECIRC PUMP MOTOR AIR COOLER FLOW INSTRUMENTATION DETAIL (45)

RECIRC PUMP SEAL CAVITY PRESSURE ANO PURGE RECIRC PUMP MOTOR AIR COOLER SEAL CAVITY XFC - EXCESS FLOW CHECK VAL VE FE - FLOW ELEMENT TC - TEST CONNECTION MO

- MOTOR OPERATED FO

- FLOW ORIFICE CONTAINMENT TC XFC TC MO NOTE:

TEST CONNECTIONS DO NOT APPLY TO UNIT 1 VALVES XV-87-156A AND XV-87-157A.

TC TC LIMERICK GENERAT[NG STATI~

UNITS 1 AND 2 lPOATED FlNAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION C3>oELE TEO DETAILS (41CHECK VALVE INSTEAD OF FO FOR PURGE LINES ISHEET IS OF l?I FIGURE 6.2-36 Rev. 1 July/91

DETAIL (46>

RPV TIP PURGE CRD INSERT AND WITHDRAWAL LINES DETAIL (48)

RPV r-r" INDEXING I I MECHANISM I

._._.~..-.--

INSTRUMENT GAS SUPPLY TC=TEST CONNECTION MO= MOTOR OPERATED AO= AIR OPERATED SV=SOLENom VALVE MO AO LIMS12.DGN LIMERICK GENERATING STATION llfITS 1 AND 2 l.PDATm FDW.. SAFETY ANALYSIS REPORT FlGURE 6.2-36 Rev. 3 Nov./93

DETAIL (47)

RPV CRD INSERT AND WITHDRAWAL LINES TC=TEST CONNECTION MO= MOTOR OPERATED AO= AIR OPERATED SV=SOLENOID VALVE

/------------,

CONTAINMEN~ /

f I

I I

I WITHDRAWAL I

I I

I I

I I

I I

/

/

I ACCUMULATOR I

l __ Ji.CU_ - - - - -

J FROM OTHER HCU'S SCRAM DISCHARGE LINES FROM OTHER HCU'S SCRAM DISCHARGE VOLUME LlMS 12a.OGN LIMERICK GENERATING STATION llflTS t AND 2 LIPDA TED FINAL SAFETY ANAL YSJS REPORT CONTADMNT PDETRATJON DETAILS (StEET na OF IT>

FJG~E 6.2-36 Rev. 3 NOV./93

LGS UFSAR Figure 6.2-37 Deleted

WATER INLET CONTROL VALVE WATER-SPRAY GAS COOLER WATER SEPARATOR GAS SAMPLE PURGE FITTING REACTION CHAMBER ELECTRIC HEAT ER ELEMENTS STRUCTURA L SUPPORT GAS RECIRC VALVE OP STARTER CERATOR ASINET ULA TION VALVE CONTAIN RECOMBINER~i~6 HYDROGEN

, CUTAWAY V IEW

1020

...,... ---..,..***** ******* ~

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SPILLED COOLANT

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i I

10 4 TIME AFTER LOCA (SECONDS)

GAMMA ENERGY ABSORBED

~BY COOLANT AROUND CORE

./

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ENERGY FROM IODINE ISOTOPES ABSORBED IN t* **

SPILLED COOLANT A

~- Iii. ~ ~. *~

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r-**

LIMERICK GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT RATE OF ENERGY ABSORPTION BY LOCA WATER AS A FUNCTION OF TIME AFTER LOCA FIGURE 6.2*39

1025 10*24

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104 10 5 10 6 TIME AFTER LOCA (SECONDS) 107 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT INTEGRATED ENERGY ABSORPTION BY LOCA WATER AS A FUNCTION OF TIME AFTER LOCA FIGURE 6.2-40

---Corrosion

• Dryr.-ell

---

corrosion

• Watweb

_.,_ UetaJ...Water Reaction

~

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200

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10 15 Tlme{days) 20 25 30 LIMERICK GENERA TING STATION UNITS 1 &2 UPDATED FINAL SAFETY ANALYSIS REPORT INTIGRA TED HYDROGEN PRODUCTION AS A FUNCTION OF TIME AFTER LOCA FIGURE 6.2-41 Rev. 11 9/02

t=" z w

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NO CONTROL 150 SCFM RECOMBINER V(SUPPRESSION CHAMBER)

/.(SUPPRESSION CHAMBER)

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2 3

4 TIME AFTER LOCA (DAYS)

-*-** **-*-5 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT TERM CONTAINMENT HYDROGEN CONCENTRATION AFTER LOCA FIGURE '6.2-42

t='

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I NOTE: 150 SCFM RECOMBINER WILL KEEP H2 CONCENTRATION BELOW 0.08 V% IN' THE SUPPRESSION CHAMBER.

150 SCFM_ PUft_GE Wl_b_~ KEEP H2 CONCENTRATION BELOW 0.0_!_ V%

IN THE SUPPRESSION CHAMBER.

-~

0-

~- -----.. ----*;

10 15 20 25 30 TIME AFTERLOCA (DAYS)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM CONTAINMENT HYDROGEN CONCENTRATION AFTER LOCA FIGUR.E 6.2-43

7 6

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2 3

4 TIME AFTER LOCA (DAYS)

I -

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5 LIMERICK GENERATING STATION:

UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT TERM CONTAINMENT OXYGEN CONCENTRATION AFTER LOCA FIGURE 6.2-44

15 I-z w

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60 SCFM PURGE 20 25 I

-*-~ ---...

I 30 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM DRYWELL OXYGEN CONCENTRATION AFTER LOCA FIGURE 6.2-45

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60 SCFM PURGE 11--.. :-...-........,...........................__i....... ~

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~ -*....

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25 I

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30 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM SUPPRESSION CHAMBER OXYGEN CONCENTRATION AFTER LOCA FIGURE 6.2-46

LGS UFSAR Figure 6.2-47 Deleted

I SEE FIG. 6.2-48 I==

SHEET2 SEE FIG. 6.2-481 SHEET 3

J I PLAN VIEW OF PERSONNEL LOCK LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCK PENETRATIONS (SHEET 1 OF-3)

FIGURE 6.2-48

2" DIA.ELECTRICAL PENETRATIONS-----

3" DIA.

EQUALIZING VALVE PENETRATION LOCK

~

I I

I I

I I

- - ---+ ---

I I

I I

I ELEVATION VIEW OF EXTERIOR BULKHEAD

~-LOCK 1" DIA. PRESSURE

-~!---TEST PENETRATIONS FOR AIR LOCK LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCK DOOR PENETRATIONS (SHEET 2 OF 3)

FIGURE 6.2~48

LOCK I 't I

I I

I I

-*-+-*-

I I

I.

I I

--- 2" DIA. ELECTRICAL PENETRATION 3u DIA.EQUALIZING VALVE PENETRATION

--- --- * -i---c:t-LOCK ELEVATION VIEW OF INTERIOR BULKHEAD LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCK PENETRATIONS (SHEET 3 OF 3)

FIGURE6.2-48

PRESSURE TEST CONNECTION\\

- -- - -;:::.:.--\\

~

(

A LOCK I

<t.

I I

I I

I

---+ ---

-i!

Al.

I

<E_- LOCK ELEVATION VIEW OF INTERIOR OR EXTERIOR BULKHEAD LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCK DOOR SEALS (SHEET 1 OF 2)

FIGURE 6.2-49

SECTION A-A DOOR ASS'Y (TYPICAL BOTH ENDS)

--- PRESSURE TEST CONNECTION LIMERICK GENERATlNG STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCK DOOR SEALS (SHEET 2 OF 2)

FIGURE 6.2M41

INTERIOR DOOR ---

--- INTERIOR BULKHEAD

---

INSIDE LOCK LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCt< INNER DOOR TIEDOWNS FIGURE 6.2-50

QUANTITY 4

4 A

NPS 6

16 3/s x (BAR ROLLED A

LENGTH 3

14 116 30 J/4 FLANGE NO.OF DIA.OF BOLT c

0.0. 1.0. THK.

HOLES HOLES CIRCLE DIA.

11" - 6.07" - ~,8.

71a*

1 2

112*

8 9 12*

23 1

12 -15 \\* -

1 12

16 1

1 la" 21 \\(

NOTES:

(1)

THERE ARE TWO LONGITUDINAL ARC WELDS ON THE PERFORATED PLATE.

(2)

THERE IS ONE LONGITUDINAL RESISTANCE WELD ON THE 12 MESH CLOTH.

(3)

MATERIAL OF CON-STRUCTION JS STAINLESS STEEL; 304L FOR THE MESH.

PERF. _3/a" THK.

5/a"' DIA. HOLES ON 1 !a., CENTERS 4*

~

RCIC AND HPCI STRAINER ARRANGEMENT 12 x12 MESH 0.023 WI RE DIA.

PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SUPPRESSION POOL SUCTION STRAINERS (SHEET 1 OF 2)

FIGURE 6.2-51 Rev. 09 11/99

PLAN TOC EL 181'-11" ELEVATION CS STRAINER ARRANCE ME NT sc..=.E:M snn-EN~

SU~~:",\\ 1 1 r.. N

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S----,1 cu-=>o* :>-

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- *r*T*-:*"'"

\\

/

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. la

- c ELEVATION RHR STRAINER ARRANGEMENT

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I~

Iii..

IQP' t...

TOC EL lSi'-11"

.0.0 o 0 o **

• 0 "V

• 0 o *

• o<l ~*

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00

.0. q 0

~~\\~~~~':;\\

~*... '7

..13\\~,...?.'..,;.

• I*

f"_;.:~C:'.

/~~~ ;x*

Pl.Ai:: $'J?P~T

~,.

r**

Ei'~O sc~:::::n '-:

\\r:?Z:.:.ii"ACnME:Ni PECO ENERGY COMPANY

~.!."'

PLA~

LIMERICK GENERATING STATION uoou:.!

UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT SUPPRESSION POOL SUCTION STRAINERS (SHEET 2 OF 2)

FIGURE 6.2-51 Rev. 09 11/99

§ l

§

~

B u

=

§ !

~....

~

J...

fl

=

~

! Ii: -

1--

8 L~

0 i

R R

0

~

0 A

R

~

0 d

d d

q q

q q

(J9J9M.,.. *..-.....

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR ENCLOSURE DRAWDOWN FIGURE 6.2-52 REV. 7 12/97

INTENTIONALLY LEFT BLANK LIMERICK GENERA Tit<<; STATION

~ITS I AND 2 UPDATED f [Nfl.. SAFETY ANALYSIS REPORT EVENT TREE FOR TIP SYSTEM LINE ISOLATION FIGURE 6.2-53 Rev. 1 July/C}l

LGS UFSAR Figures 6.3-1 through 6.3-10 Deleted

oa m

~om1na1 Oecav 1'1Ht :..irvt o

Aooenasx-1( Oecay Heat C:Jrvt 10 100 1000 10000 Ttme Arter ereak cseecnas>

LIMERICK GENERATING STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT NORMALIZED POWER VS TIME AFTER BREAK (SAFER/GESTR METHODOLOGY)

FIGURE 6.3-11 Rev. 07 12/97

OB a:

w

~

0

~

0.6

({

u w

0 0.4 0.2 0.1 1.0 10 100 1.000 10.000 100.000 1.000.000 TIME AFTER BREAK lsec)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT NORMAL POWER VS TIME AFTER BREAK (ORIGINAL 6.3-1 METHOD)

FIGURE 6.3-11A Rev. 07 12/97

LGS UFSAR Figures 6.3-12 through 6.3-74 Deleted

\\.

... [

1.

.__ __ ---JI I I I ____ __.

OFFICE-

""\\,TOILET CJ UTILITY LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTROL ROOM ARRANGEMENT FIGURE 6.4-1 REV. 13 09/06

COOLING TOWE,.

UNIT* t TU.. BINI ENCL.

UNtT*t COOLING TOWEFI UNIT*2

/

l"A.. KING AREA LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT PLANT LAYOUT WITH RESPECT TO CONTROL ROOM INTAKE FIGURE 6.4-2

LGS UFSAR Figures 6.7-1 through 6.7-5 Deleted