ML22278A229

From kanterella
Jump to navigation Jump to search
Rev. 21 to Updated Final Safety Analysis Report, Chapter 6, Figures
ML22278A229
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/19/2022
From:
Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22278A223 List: ... further results
References
Download: ML22278A229 (88)


Text

28*"4" 0.0. III 518" JET TESTP It.

\\

DEFLECTOR]

ASSY.

~D.;,-.-,~--l-.--

I-BARS III EQUALLY SPC'D

i. SHOP,AINT
  • RING'l h TO THIS DIA.

LIFTING LUG 21*1/4 0.0. 11518" TESTIl..

    • ~l**

1'-,: " '. ' II,'

IHOPPAINT

-:',. I

'. :.... >,,<.4':.. :

THISDIA.

f~':"""'" "INO'lTO I

I I.. :.>..... : ::

PRIMARY CONTAINMENT I

I ". " *.,', ',: :

DIAPHRAGM SLAB

~-~I,.:~~=.--'I',

NOTE:

34" 0.0. X,,;.. J

'l.RING

,..... 3/8" WALL "'E

/

'..... 1SO.F. F. FLANGE MO.D. X 1/2"

'lIllING TYPE I (TYPICAL OF 6)

TYPE IA (TYPICAL OF 4)

TYPE II (TYPICAL OF 57)

HOLES STRADDLE VERTICALIl.

"'" TYPE I ONLY

'0"4>*150:1 F.F. FLANGE HOLES STRADDLE VERTICALIl.

,.,.. 4>SCHED 40 'IPE FOR TYPE 18t I*A 24- 0.0. X 111'"

WALL PIPE I This UFSAR figure is provided to delineate the primary (typical) structural concepts, arrangements, and elements relied upon to perform the safety related functions of the subject structures. For detail design features, dimensions, and as-built concition of the structures, see design drawing numoor(s):

8031-C-293.

I lEE DETAIL ~ON SHEET 2 FOR TEE AND VACUUM RELIEf VALVE MOUNTING FLANGE

.. THIS AREA eTYPE 1A ONLY) i TYPE III (TYPICAL OF 20)

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

FIGURE 6.2-1

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

-..: ~

~

\\\\

\\\\

r i

-U-1

--1------

1/ T

/1 I

//

I ELEVATION FOR TYPE IA ONLY DETAIL @

FULL PENET.

-A-----<

PI-A-LH 100% RTOR UT (TVP)

MOUNTING FLANGE FOR PRIMARY CONTAItlMENT VACUUM R'E:LIEF VALVE ASSEMBLIES I[ EL. 231'*0"

<c< _______

~

.~

24.": ;'15(}f. WoN.RoF.* FLANGE HOLES STRADDLE VERTICLE ct

'>------- 24'X 24 TEE X 0.375 WAt"l T.I:H.C K~ ESS LIMERICK GENERATING STATION UNITS' AND 2 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 s1ructures. For detail design features, dimensions. and as-built condition of the structures, see design drawing number(s):

8031-C-293.

DOWNCOMER DESIGN DETAILS (SHEET 2 OF 2)

F IGUR E 6.2-'

12 II",,",

ID """'

9~

lI-N

'7 I-

~

IE C

J 6~

0 ;.

5 ~

4t-3~

lr-It-O t

0 I

NOTE:

I I

I I

I 1

J S

6

'7 TIME "..."

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.

J 8

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

O==========~~--~~~~~~~~IO----~~~~~~~----~~--~~~~

0,'

NOTE:'

TIME lwei 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

'curTentpiant concfltions.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT*TERM CONTAINMENT PRESSURE RESPONSE FOLLOWING RECIRCULATION LINE BREAK F IGUR E 6.2-3 Rev. 5, 4/96

tl

__ 10 _

-.l I

1.

z


J c==

1---.------

LGS AERATE PRES$URE: AE:SPON$

I lI;o,,1 1 mil I' *'hillHt:il. pm. SSlbiE i HfI Hfi I PilE SSt klE

.. ~--~ ~--

.-~.

I~~ ~',u~

O. 1~J......L.1_LI.J... _LLL-I-... o-.-. _~_.,. __ --._-.......... _.0._.... -.- 0._.....

O.

10.
20.

311.

lin.

11 ME

'SECONrIS)

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

E

~

... 5

~

soor------------------------------------------------------

400 300 200 NOTE:

'ORYWELL SLPPRESSlON POOL The information presented in this figure is historical and is based on the original design basis conditions and to analyZe the eontaint'nerU response following a LOCA.

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

LIMERICK GENERA TING STATION UNITS 1 AND 2 UPDATED FINAl. SAF£TY ANALYSIS REPORT SHORT.. TERM CONTAINMENT TEMPERATURE RESPONSE FOLLOWING RECIRCULATION L1NEBREAK FIG 6.2-4 Rev 08 lV98

~I.

LGS RERATE 1aftRA l.UII£ RESP "2P/1MlF 350.

, ORVIW. TaftRATlft£ Z IETIELL TaftRA lURE 1

1 I

. I G: 250. y-r

.V)

W

(!)

LaJ e UJ I

~ 150. ~

2 2

oc(

2 ffi 2

rtIfIIIIII'-

  • 2~
n.

=---'.

~

f..

50. 1-**** 1.....

o..

D.

  • 20.*
30.
40.

TIME (SECONDS)

LI"£~ICK GENERATION STATION UHITS I AND 2 UPDATED fiNAL SAFETY ANALYSIS REPORT TEMPERATURE RESPONSE AS A fUNCTION Of TIH£ (al R8'.'. Power Condillons, fiGURE 6.2-4A Rev 08 8/98

),

~

~

10 cr:

~

... f S

o

-S NOTE:

TII'"I£,,,,0 NOTE:

1.1 4IVCI. 2 CS SYSTEM. 2101)( IWITH CONTAINMENT SPRAYI fbi "1VCI. I CS SYSTEM. 1101)( tWITH CONTAI~"'e~T SPRAY I lei 2 VCI, I CS SYSTEM. 1101)( INO CONT.AINMe~T SPRAYI 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.

LlMER let<: GENERA TlNG STATION UNITS 1 AND 2 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

I'"'-sp TEMP I

~ 2*00E+021

= I 4L2 W

o *

~

=-i

~

&AI

... 1*00E+021 O.OOE+OO La ---------l---------I-------_4-_____ -~~

100000 100 1000 10000 LOG nME... SEC UMERICK GENERATION~8TATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANAL VSIS REPORT LONG TeRM SUPPRESSION POOL TEMPERATURE RESPONSE* CASE CAT 3528 MWl FIGURE 6.2-SA REV. 13 09f08

.. a.

I !...

~

a::

~

9----------------------------------------------------------------------,

I I

s NOTE:

4_,4 VCI, 2 CS SYSTEM. 2 Hl( (WITH CONTAINMENT spRAYI IbI2I.PCI.l CS SYSTtM ** Hl( tWITH CONTAINMENT SPRAY,'

lei 2 U*CI,1 CSSYSTtM.l Hl( tNOCONTAINMENT SPRAYI TIUE 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, 6, 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 1 AND 2 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

5....

NOTE:

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 1 AND 2 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 stearn line break was not reanalyzed for the current conditions; however.

the results reasonably represent the general characteristiCS of the main stearn line break.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYStS REPORT SHORT-TERM CONTAINMENT PRESSURE RESPONSE FOLLOWING MAIN STEAM LINE BREAK Rev. 5. 4/96

DR'tWfLL SU",Rf!>SION POOL l00~ ______________________ --------

~~----~~~..

~~--~~~~..

~~--~~~~~~~--~--~~~~

'0 '

NOTE:

If" rlu. I.. "

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 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT-TERM CONTAINMENT TEMPERATURE RESPONSE FOLLOWING MAIN STEAM LINE BREAK FIGURE 1.2-13 Rev. 5, 4/96

50,--------------------------------.

JO 20

.0 NOTE:

O"'IWILL lUf'P"EDlON CHAM.R nUE fwel 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.

'000 FIGURE 6.2-14 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT-TERM CONTAINMENT PRESSURE RESPONSE FOLLOWING AN INTERMEDIATE SIZE BREAK (0.1 ft2 LIQUID BREAK)

Rev.5. 4/96

~r---------------------------------------------------------------~

JO 20

.0 NOTE:

O"'IWILL lUf'P"EDlON CHAMBER nUE 'wel 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 1 AND 2 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.

us JOO 1~

150 125 0:

,00

~..

I....

175 10' 1tMf tv..-'

10'

'0 l~ L...J....J...wUJ.w.._J....U..u.LJJJL......L..L.LLJJJJJ..._.l.-W.J..L.L.W~-J.....L...w..wJJ-_r......JI-L...I..IJ~

NOTE:

TheInformationpresented Inthis 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 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT*TERM CONTAINMENT TEMPERATURE RESPONSE FOLLOWING AN INTERMEDIATE SIZE BREAK (0.1 ft2 LIQUID BREAK)

Rev.5, 4/96 0:

~..

I..

J~~---------------------------------------------------------------,

150 115

,00 17~

10 '

NOTE:

10' 1tMf tv..-'

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 1 AND 2 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 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SCHEMATIC OF ANALYTICAL MODEL FOR RHR CONTAINMENT COOLING SYSTEM FIGURE 6.2*16

DRYWELL VAPOR REGION M IPI'IIY

IU..

(,J Z w -

LL LL W

c(

a::

A1.

en 1.0 0.9 0.8

~

0.7 0.0

~

~

~

0.2

...... =ar V-

~

J V I

j I

) If J V

~ V

/ V

~

'tI' 0.4 0.6 0.8 1.0 1.2 ATMOSPHERE STEAM/AIR MASS RATIO LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT THERMAL HEAT REMOVAL EFFICIENCY OF DRYWELL SPRAY FIGURE 6.2-18

(..j -

CJ')

e::

lJJ ex::

=>

CJ')

(./)

lJJ 0::

a..

lJJ 3:

0::

C) 25.00 ----~-----,r---_r_-__,__-__,_-___r--r__-_,__-__r-__,

20.00........ ----I---+----:.-+----t----t---t----I----+--t----t 15.00 \\ \\

~

UJ.00 I

~

I, \\

I VRV BEGINS 5.00 10 \\

OPEN 8.00

'~ '\\

~ "-~

DR~ WELL PRI SSURE = -4.85 p~ IG MIN.

-5.00

-10.00 -'----f..--+----+----+-----t~-+----+----+---+------I 1.00 30.00 60.00 Cl0.00 120.00 150.00 180.00 210.00 240.00 270.00 300.00 TIME (SECONDS)

,......-.l~IME~RI~CK~GE~NE~AA~T~ING~S~TAI!I"'!!!!!T~ION....----I lfilTS 1 At() 2 UPDATED FINAL. SAFETY ANAlYSIS REPORT DRY WELL PRESSURE RESPONSE TO SPRAY ACTUATION FIGURE 6.2-19 Rev. 1 July/en

L.I...

t-W c::

I-

<J:

0::

W 0-

~

W I-

~

.....J w

3t 0:::

0 280.00 I

260.00 1\\

240.00

\\

~

220.00

\\

200.00 180.00

\\ \\

160.00

\\

140.00

~

120.00

\\

100.00

\\

I 80.00

\\

ORYWE ~L TEMPI RATURE

~ 4Q.S*F MIN.

60.00 40.00 20.00 -I----+---I-----t----+--+----+----+---+-----+----I 0.00 -I-----4--+----f-----r---t----f----t--+---+-----I 0.00 30.00 60.00 q0.00 120.00 150.00 180.00 210.00 240.00 270.00 300.00 TIME (SECONDS)

~~LI~ME!:"!:!R~ICK~GE~N~E~RA~T~IN~G~S~TA~T"'!"!I~~--I

~ITS 1 AND 2 UPDATED F[NAL SAFETY ANAlYSIS REPORT ORYWELL TEMPERATURE RESPONSE TO SPRAY ACTUATION FIGURE 6.2-20 Rev. 1 July/en z:\\t.£O!\\ OG02020.DGN

0.8----------------------------------------------------------------__

0.6 w a: <<

3: o

..J U. ('1-W ::

<.:)

<< t..:;

0.4

~ --

<< 01(

w

..J

~

Q. >

en 0.2 UNACCEPTABLE NOTE:

2 3

4 s

6 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.

7 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT MAXIMUM ALLOWABLE STEAM BYPASS LEAKAGE FLOW AREA FIGURE 6.2*21 Rev. 5, 4/96

"2.

! g

~

g

~

a: *

~~-----------------------------------------------------------

.~

("OUOD J~

7~

n-I I

I I II I

I I

I I I III I

II I I I I,I I

t I

I I I II

~~'--~~~~l----~--~~~~~l~O--~'Q--~JO~~O~~~I~OO----~~~~LL~I000 NOTE:

TIME h.d 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 GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL LIQUID BLOWDOWN FLOW RATt; FOLLOWING RECIRCULATION LINE BREAK FIGURE 6.2*22 Rev. 5, 4/96

o

°7-----~----~--~~--~~~~I.~'----L------L------L---~---L--J-J m

NOTE:

tlMf h.....

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 GENERATING STA nON UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL STEAM BLOWDOWN FLOW RATE FOLLOWING RECIRCULATION LINE BREAK F IGUR E 6.2*23 Rev. 5, 4/96

NOTE:

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 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL BLOWDOWN FLOW RATE FOLLOWING MAIN STEAM LINE BREAK FIGUR E 6.2-24 Rev.S, 4/96

600~------------------------------------------------------------------_

1.1 FUEL TEMPER"T~f Ihl vESSf.l W"ll TEMPER"TURf; It' 'IliTERIIIAl STRUCTURE TEMPERATURf.

,m~----~~~------~~~----~~~~~~~"~~----~~~------~~~

10' NOTE:

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.

LIMERletc GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL TEMPERATURE RESPONSE FOLLOWING RECIRCULATION LINE BREAK Rev. 5, 4/96

~.

'i 10-Q It

~

=

n __ ------------------------------------------------------------~

IS 10 NOTE:

1",1 T.U, h....

t.. -'

,nt*

I" 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 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SENSIBLE ENERGY IN REACTOR VESSEL AND INTERNAL STRUCTURE METALS FOLLOWING RECIRCULATION LINE BREAK F IGUR E 6.2*26 Rev. 5. 4/96

I

.~-----

8 L:.1.i.l'34 I

-- I~

'YII~'" "'DC JlI.--QO_OII...

~),".. _e

.~i PRlhAARY CONTAINMEf04T

. R~

~g,~~~~~~EASECONDAAY 1'5,*

UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT

52.

UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT

()(Xj(, IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONT AINMENT NOTE:

EOUlf'lolENTLoc.o.TKIN DRAwING U-lle. AEV.1D(FOA lJ'IlT I). MID U-131. REV. 'S IFOA UNIT t) weAE USED AS 8ACl<GROUND FOR lJ.IlS AGI..RE I

V 6.2*35 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 177 FEET FIGURE 6.2-27

~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 o

PRIMARY CONTAINMENT REFUELING AREA SECONDARY CONtAINMENT UNrr 1 REACTOR,ENCLOSURE SECONDARY CONTAINMENT

(§l UNIT 2 REACTOO ENCLOSURE SECONDARY CONTAINMENT

, XXX'" IDENTIFICATION NUIMBE'R FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT orB

~I i

I

--- f-(~)

sl I

i +0 i

~1

~;

, -'---(D) )

6,2,35

--.:1 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV.201 FEET FIGURE 6.2-28

I

~I EJt tl

V~'-----"'--- -'_.I!IloI!o'"

l:.. 62-34 1:;)\\.Iljlllll;lt,.,

.. j.LO-t...

I I

"~tGD NOTE: EaulPMENT 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

\\R.~\\

REFUELING AREA SECONDARY CONTAINMENT

.*S1 t UNIT I REACTOR ENCLOSURE SECONDARY CONTAINMENT 52!

UIIIIT:2 REACTOR ENCLOSURE SECONDARY CONTAIINMENT

( XXX) IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 217 FEET FIGURE 6.2*29

IJ-.---__

bl

~'

~II i

I

-----i~ ___ _+__--c.;"'---~---"'-=---~ --il:-~__l__--~

e Ii 6.2-34 21-0' NOTE: eQUIPMENT LOCATION DRAWING M-119, REV. 24 (FOR UNIT 1), AND M-134. REV. 18 (FOR UNIT 2)

WERE USED AS BACKGRWND FOR THIS FIGURE

.""p.... ;

PRIMARY CONTAINMENT R)

REFUELING AREA SECONDARY CONTAINMENT

.~~\\

UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT

'5; UNIT:2 REACTOR ENCLOSURE SECONDARY CONTAINMENT

( XX)() ~:~~T~~NE~~g~~;~:;;'~~~NT

1

,-~

i

.1

  • 1

~I 6.2-35

,...:1 1IIiiiIiI1I..

_...... ~

___ - _L@

i I

I I

--.... 1_. _~z,:z:_~_

.-+--___

_.L~~

(;';)

~~

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 253 FEET FIGURE 6.2-30

!-----~-----+----=------+-~'-""~" --j." e 1.:.6"2"30 NOTE: EQUIPMENT LOCATION DRAWING M-120, REV. 22 (FOR UNIT 1), AND ""'135, REV. 16 (FOR UNIT 2) WERE USED AS BACKGROUND FOR THIS FIGURE "Pj PRIMARY CONTAINMENT

"R'"",

REFUELING AREA SECONDARY CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT

~: UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT xxT IDENTIFICATION NUMBER FOR ACCESS OPENINGS IN SECONDARY CONTAINMENT 6.2,35

...!1 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 283 FEET FIGURE 6.2-31

~~ 1 0--:

,I 11

~I I

o t - -----11_

P.

PR'IMARY CONTAINMENT REFUELING AREA SECONDARY CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT UNIT 2 REACTOR ENCLOSURE SECONDARY CONTAINMENT

-xxx.., IDENTIFICATION NUMBER FOR ACCES~NT OP,ENINGS IN SECONDARY CONTAIN'"

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


0 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 313 FEET

I! 6-2-34 NOTE: EOUIPMENT LOCATION DRAWING.... 122, REV. 1.. (FOR UNrr 1), AND U-137, REV. 13 (FOR UNrr 2) WERE USED AS BACKGROUND FOR THIS FIGURE

._--+ ___ -,':.:..",.::.,0'_ I

".0' I""

~@;

.~

~ PRIMARY CONTAINf.ENT IA)

REFUELING AREA SECONDAR Y CONTAINMENT UNIT 1 REACTOR ENCLOSURE SECONDARY CONTAINMENT Cit; UNIT 2 REACTOR ENCLOS LIRE SECONDARY CONTAINMENT QED ~~:~~i~os~~~g~=~2~~;;~~~NT


r-0 6.2-35

..!!J LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE, PLAN AT ELEV. 352 FEET FIGURE 6.2-33

r rk:::,--------j ~'-22l.:.?'

t.I~

-.. 6.2-32 r

~~

.. 6.2-31 r

.. ~

6.2*30 r

M~

-" p~e$Su~~

.. 6.2*29 A~LlEF f~LL-----",,"I-'-- __

Fl"'~~=-EL!~

SECTION A*A o

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

"'-123, REV. 6 WAS USED AS BACKGROOND FOR THIS FIGURE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SECONDARY CONTAIN MENT BOUNDARY OUTLINE NORTH-SOUTH SECTION VIEW (UNIT 1)

FIGURE 6.2-34

r r

~'

I SECTION 8-6 NOTE: EQUIPMENT LOCATION DRAWING M-108. REV. 5 WAS USED AS BACKGROUND FOR THIS FIGURE 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*]0

.. 6.2*29,,

6.2*28 6.<'*27 LIMERICK GENERATING STATION UNITS 11 AND 2 UPDATED FINAL SAF.ETY ANALYSIS REPORT SECONDARY CONTAINMENT BOUNDARY OUTLINE EAST*WEST SECTION VIEW FIGURE 6.2-35

RPV CONTAINMENT DETAIL (1).

MAIN STEAM LINE AD MAIN STEAM DRAIN DETAIL (2)

SEE SHEET 1"---- 2 OF 17 DETAIL (3)

RCIC STEAM SUPPLY HPCI STEAM SUPPLY MO - MOTOR OPERATED Te - TEST CONNECTION AD - AIR OPERATED FOR DETAIL (2)

MO (UNfT 1)

Te XFC - EXCESS FLOW CHECK VALVE

.-..- TC

...-...- TC MO Te (UNIT 2)

AD

"-"'-TC

~ -

~ #

,- ~--

t MO

~_~,

I

/~

I I

t----'

MO LIMERICK GENERATIt<<; STATION lftlTS 1 AND 2 lPDATED FINAL SAFETY PIW... YSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 1 OF 17)

FIGURE 6.2-36 Rev. 1 July/gl ZI\\t.lECH\\ 06.02036.51

RPV CONTAINMENT DETAIL (2)

MO r-.,

I

"'A: 1 TC FEEOWATER MO-MOTOR OPERATED TC-TEST CONNECTION AO-AIR OPERATED XFC-EXCESS FLOW CHECK VALVE TC LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 2 OF 17)

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 9t--1 --It AO TC MO

....------.-...-..9 rL-,~t-l

.......--TC MO MO TC I~ 1 £ l LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 3 OF 17 )

F IGUR E 6.2-38

RPV DETAIL (7)

SUPPRESSION POOL PURGE SUPPLY SERVICE AIR DETAIL (8) 1

-,,)It..

DETAIL

)C~

(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 CONTAINMENT TC TC AO TC TC AO LIMERICK GENERATING STATION UNITS 1 AND 2 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-----'

(10)

TC STANDBY LIQUID CONTROL DETAIL

~,,)

AO 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 TCl<-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.

I TC TCK CONTAINMENT MO T

RHR SHUTDOWN COOLING RETURN (ONLY)

TC SV SV

.- *L~-.;i 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 DET AI L "x "':-----.10--1 (13) [x ~~-.I RECIRC PUMP CW SUPPL V

  • RETURN DRYWELL CHILLED WATER SUPPL V & RETURN MLC DETAI L 1---.......,"'lIC" Jooo--00001 (14)

ALTERNATE RWCU RETURN DETAIL (15)

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

MO ~t-(

TC J' £h MO li, TC MO,.:tH f

TC (UNIT 1)

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 60F 17)

F IGUR E 1.2-31

RPV CONTAINMENT PSV DETAil (16)

SUPP POOL RHR PUMP SUCTION MO TC CK CK TC MO r "",_

MO I

Lo-I DETAil TC (17)

CK CK I

I HPCI VACUUM RELIEF RCIC VACUUM RELIEF PSV MO DETAil (181 SUpp POOL RHR ReliEF VALVE DISCHARGE PSV-PRESSURE SAFETY VALVE MO-MOTbR OPERATED TC-TEST CONNECTION CK-CHECK VALVE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 7 OF 17)

FIGURE 6.2-36 Rev. 6,12/96 RPV CONTAINMENT DETAil (16)

SUPP POOL RHR 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 r "","

MO L,..

TC CK CK

........ I I

MO LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 7 OF 17)

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 CONTAINMENT DETAIL (19)

SPOOL PIECE BLANK~t{

A SUPP POOL RHR RELIEF VALVE DISCHARGE MO MO DETAIL (20)

TC RWCU SUPPLY RHR SHUTDOWN COOLING SUPPLY 1

ft THICK WELDED PLATE ABANDONED DETAIL I-----------r--------t (21A)

TC ---~

RPV HEAD SPRAY (UNIT 1 ONLY)

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

FIGURE 6.2-36 Rev. 11 9/02 RPV DETAIL (19)

SUPP POOL RHR RELIEF VALVE DISCHARGE DETAIL (20)

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

MO 1ft THICK WELDED PLATE DETAIL I--__

A_B_A_N_D_O_N_E_D ___ -.-____ -t (21A)

RPV HEAD SPRAY (UNIT 1 ONLY)

MO - MOTOR OPERATED TC - TEST CONNECTION PSV - PRESSURE SAFETY VALVE (2) THIS IS A GATE VALVE FOR RHR SHUTDOWN COOLING SUPPLY TC ---..

PSV UMERICK GENERATING STATION UNITS 1 AND 2 UPDATED 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 TC TC AO DETAIL (22)

INSTRUMENT GAS SUPPLY DETAIL (231 DRYWELL SAMPLE WETWELL SAMPLE SV SV MO DETAIL (241 HPCI TURBINE EXHAUST HPCI PUMP FLUSH HPCI PUMP MIN FLOW CS PUMP MIN FLOW CS PUMP TEST & FLUSH RCIC TURBfNE EXHAUST RCIC MIN FLOW RHR PUMP MIN FLOW AO-AIR OPERATED MO-MOTOR OPERATED SV-SOLENOID VALVE TC-TEST CONNECTION SUPP POOL LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 9 OF 17)

FIGURE 6.2-36 RPV CONT AINMENT DETAIL (22)

INSTRUMENT GAS SUPPLY DETAIL (231 DRYWELL SAMPLE WETWELL SAMPLE DETAIL (24)

HPCI TURBINE EXHAUST HPCI PUMP FLUSH HPCI PUMP MIN FLOW CS PUMP MIN FLOW CS PUMP TEST & FLUSH RCIC TURB'NE EXHAUST RCIC MIN FLOW RHR PUMP MIN FLOW AO-AIR OPERATED MO-MOTOR OPERATED SV-SOLENOID VALVE TC-TEST CONNECTION SUPP POOL TC TC AO SV SV MO LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 9 OF 17)

FIGURE 6.2-36

RPV CONTAINMENT MO MO DETAIL (25)

CONTAINMENT SPRAY TC DETAil (21)

SUfIP POOL MO MO PlV


--J TC MO SV SUPPRESSION POOL CLEANUP PUMP SUCTION AND lEVEL INSTRUMENTATION TC MO TC AO DETAIL (27)

DRYWELL PURGE EXHAUST MO-MOTOR OPERATED AO-AIR OPERATED TC-TEST CONNECTION PSV-PRESSURE SAFETY VALVE SV-SOLENOID VALVE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 10 OF 17)

FIGURE 6.2-36 DETAIL (25)

CONTAINMENT SPRAY DETAil (21)

RPV SUPPRESSION POOL CLEANUP PUMP SUCTION AND lEVEL INSTRUMENT ATION DETAIL (27)

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

'IV TC

,~

TC MO SV AO TC TC MO LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 10 OF 17)

FIGURE 6.2-36


~----~.. ~--------------.. ~.

RPV CONTAINMENT AO

"'w,j..-r---:---QQ----OIlG-------I DRYWELL DRAIN SUMP DETAIL (281 TC DRYWELL DRAIN SUMP DISCHARGE SV DETAIL (291 DRYWELL SAMPLE WETWELL SAMPLE TC sv DETAIL (301 SUPP POOL RHR VACUUM RELIEF Me-MOTOR OPERATED TC-TEST CONNECTION SV-SOLENOIO VALVE LIMERICK GENERATING STATtON UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET" OF 17)

FIGURE 6.2-36 Rev. 6,12/96 RPV CONTAINMENT DRYWELL DRAIN SUMP AO DETAIL (281

~_~1--r-~ ____ ~~

______ ~~

________ --I DRYWELL DRAIN SUMP DISCHARGE DETAIL (291 DRYWELL SAMPLE WETWELL SAMPLE DETAIL (301 RHR VACUUM RELIEF Me-MOTOR OPERATED TC-TEST CONNECTION SV-SOLENOIO VALVE SUPP POOL TC TC SV sv LIMERICK GENERATING STATtON UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PEN ETRATION DETAILS (SHEET" 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 TC (31)

(UNIT 1)

MLC MLC ILRT TC TC DETAIL (31A)

MLC MLC DETAIL (32)

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

FO

~91

~1 MO/BLO MLC DEACTIVATED SUMP TANK LEVEL INSTRUMENTATION MO MO DETAIL (33)

PRIMARY STEAM DRAIN LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 12 OF 17)

TC=TEST CONNECTION MO=MOTOR OPERATED MLC=MANUALLY LOCKED CLOSED FO=FLOW ORIFICE BLO=BREAKER LOCKED OPEN FIGURE 6.2-36 Rev. 12 9/04 RPV CONTAINMENT DETAIL (31)

ILRT DETAIL (31A)

FO DETAIL (32)

~91

~1 SUMP TANK LEVEL SUMP TANK FLOW I NSTRUMNETATION DETAIL (32A)

DEACTIVATED SUMP TANK LEVEL INSTRUMENTATION DETAIL (33)

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

~.4 t ~.~ '* ~.4 2 (UNIT 1)

MLC MLC TC TC

--r:-:l.. tI.4 *

~*4 C MLC MLC MLC MO/BLO MLC MO LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 12 OF 17)

FIGURE 6.2-36 Rev. 12 9/04

RPV CONTAINMENT MO TC DETAIL (34)

SUPP POOL RCIC VACUUM PUMP DISCHARGE MO-MOTOR OPERATED TC -TEST CONNECTION GCK-GLOBE STOP CHECK GCK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 13 OF 17)

FIGURE 6.2-36 DETAIL (34)

RPV SUPP POOL RCIC VACUUM PUMP DISCHARGE DETAIL (35)

SUPP POOL RHR MIN RECIRC DETAIL (36)

SUPP POOL RHR PUMP TEST LINE lit CONTAINMENT COOLING

& RHR MIN RECIRC MO-MOTOR OPERATED TC -TEST CONNECTION GCK-GLOBE STOP CHECK CONTAINMENT MO MO TC GCK MO TC MO t '.......

t1:.

(

,~

MO Jl 2

MO

-11

(

MO t

err-(

TC MO 1-~..

LIMERICK GENERATING STATION UNITS 1 AND 2

(

UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 13 OF 17)

FIGURE 6.2-36

RPV CONTAINMENT FO TC r

DETAIL XFC (37)

~... ~..

INSTRUMENTAnON CONNECTED TO RPV DETAIL

<38>

SUPPRESSION POOL LEVEL INSTRUMENTAnON DETAIL 08Al (UNIT1ONLY)

SUPPRESSION POOL LEVEL INSTRUMENTATION DETAIL (3'1)

SUPPRESSION POOL SUPPRESSION POOL 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 SUPPRESSION POOL PRESS.

INSTRUMENTAnON XFC - EXCESS FLOW CHECK VALVE FO

- FLOW ORIFICE MO

- MOTOR OPERATED TC

- TEST CONNECTION sv

- SOLENOID VALVE LIMERICK GENERATING STATION UNITS 1AN) 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 14 OF 17)

FIGURE 6.2-36 Rev. 1 Jul~/ql RPV DETAIL (37)

INSTRUMENTA nON CONNECTED TO RPV DETAIL (38)

SUPPRESSION POOL LEVEL INSTRUMENT A nON DETAIL (38A)

(UNI T 1 ONL Y)

SUPPRESSION POOL LEVEL INSTRUMENTATION DETAIL (3'1)

SUPPRESSION POOL PRESS.

INS TRUMENTA nON FO r SUPPRESSION POOL SUPPRESSION POOL XFC - EXCESS FLOW CHECK VALVE FO - 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 AN) 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTA[NMENT PENETRATION DETAILS (SHEET 14 OF 17)

FIGURE 6.2-36

RPV DETAIL (40)

INSTRUMENTATION CONNECTED TO RCPS DETAIL (41)

DRYWELL AIR PRESS.

INSTRUMENTATION CONTAINMENT TC XFC TC NOTE:

TEST CONNECTIONS ARE INSTALLED UPSTREAM AND DOWNSTREAM OF THE EXCESS FLOW CHECK VALVES AS SHOWN ON THE APPLICABLE P&ID FIGURES.

MO DETAIL (42)

SUPPRESSION POOL DETAIL (42A)

SUPPRESSION POOL HPCI & RCIC PUMP SUCTION CORE SPRAY PUMP SUCTION FO - FLOW ORIFICE MO - MOTOR OPERATED TC - TEST CONNECTION XFC - EXCESS FLOW CHECK VALVE PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PENETRATION DETAILS (SHEET 15 OF 17)

FIGURE 6.2-36 Rev. 09 11/99 DETAIL (40)

RPV INSTRUMENTATION CONNECTED TO RCPS DETAIL (41)

DRYWELL AIR PRESS.

INSTRUMENTATION DETAIL (42)

HPCI & RCIC PUMP SUCTION FO - FLOW ORIFICE MO - MOTOR OPERATED TC - TEST CONNECTION SUPPRESSION POOL XFC - EXCESS FLOW CHECK VALVE CONTAINMENT MO TC XFC 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 1 AND 2 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 INS T RUMENTATION DETAIL (45)

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

- MOTOR OPERATED FO

- FLOW ORIFICE CONTA[NMENT Te XFC MO NOTE:

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

Te LIMERICK GENERAT[NG STATI~

UNITS 1 AND 2 lPOATED F[NAl SAfETY ANALYSIS REPORT CONTAINMENT PENETRATION (3)OElE TEO OETAILS (4ICHECK VALVE INSTEAD OF FO FOR PURGE LINES (SHEET 16 OF 171 FIGURE 6.2-36 Rev.l July/91

DETAIL (46)

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

RPV r-I" INDEXING I I MECHANISM I

"-- --~.... --

INSTRUMENT GAS SUPPLY TC=TEST CONNECnON YO= MOTOR OPERA TED AO= AIR OPERATED SV=SOLENOm VALVE MO AO LIMS12.DGH UUERICK GENERATING STATION lIfITS 1 AND 2 LPDATm FDW.. SAFETY ANAL. YSIS REPORT aJNT ADIENT PEJtE'TRA TJON DETAD.S CSIEET n OF t n FlGURE 6.2-36 Rev. 3 Nov./93

DETAIL (41)

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

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

/

I CONT AINUEN~ /

I f

I I

I I

WITHDRAWAL I:

I I

I I

I I

/

/

FROM OTHER HCU'S

FROt.l I OTHER I J H~U'S,.

I ACCUt.rulATOR 0. r-----~

l __ JtCU ______ J SCRAM DISCHARGE LINES FROU OTHER HCU'S SCRAM DISCHARGE VOLUME LlMS 12a.OGN LIMERICK GENERATING STATION lIfITS t AND 2 UPDATED FINAL SAFETY ANAL YSJS REPORT CONTAItMNT PEf£TRATJON DETAILS (StEET na OF' In FJG~E 6.2-36 Rev.3 NOV.l93

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 CERA TOR ASINET ULA nON VALVE CONTAIN RECOMBINER~i~6 HYDROGEN

, CUTAWAY V lEW

1020

....... ~--.... ~...... ~

~

~

r-... ~ ~~

~

I 1019

....~-..

~

GAMMA AND BETA

~t..

w

~ ENERGY ABSORBED IN

~

~

t-

~~

    • r-I--

~

SPILLED COOLANT

~!II!I GAMMA ENERGY ABSORBED a::

,+ **

~

,., BY COOLANT AROUND CORE

.~-

./

z

-4~.

~

0

--... r--

~

-~

~

~

.... I,

~

as

"'""~

I--~

j+.

"'""P-- ~~

a::

~

I r"',

~ '"

~

~

ENERGY FROM IODINE r--...

ISOTOPES ABSORBED IN CJ t* **

a:

-~

SPILLED COOLANT LLI 1018 1--__.

+ **

Z IIiI!IIo. ---

~

"II...

~.

~

+.... ".-.., "-

+.

~,

4>..

~.,

~

I 1017 10 2 10 3 10 4 10 5 10 6 10 7 TIME AFTER LOCA (SECONDS)

LIME RICK GENERA TING STA nON UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT RATE OF ENERGY ABSORPTION BY LOCA WATER AS A FUNCTION OF TIME AFTER LOCA FIGURE 6.2 w39

1025

~

~

~

L, 1023

"""P;+

h

~,..

A+

~ ~."

.. +

+.

p-9

!#+

/'"

~

.+

~~.+..

t.~. i

~

~.,l

/'

~ *

/~

2

~ **

~

"I.'"

~

11" ***

.~

/'.

.I~

z**

/

/

.. 9

+..

'I" h**

~'"

  • +

~

~

/

/ V 1

/

Ii

/

V

/'

GAMMA ENERGY

/'

ABSORBED BY -. ~

~~

COR E COO LANT

........ t'-t ~

~

~

ENERGY ABSORBED FROM l/

IODINE ISOTOPES IN SPILLED COOLANT V

V V

.. ".. ' V

~.......

/

..... ~..

/

i I

~,..,......

~

I~.,.~.

~

~."

.JI1 ~

.~ ",..

.,~

/"

./ ~

/~

L-',

~.

1/

-........ ~

GAMMA AND BETA

~~

~

~~

t"'- ENERGY ABSORBED IN

~

SPILLED COOLANT

~

~

~",.

~'

/"

~~

t+

104 10 5 TIME AFTER LOCA (SECONDS)

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT INTEGRATED ENERGY ABSORPTION BY LOCA WATER AS A FUNCTION OF TIME AFTER LOCA FIGURE 6.2-40

WI ILl

....... Corrosion

  • Dryr.-ell

"",,-CorrtlSion

  • Watweb

~

UetaJ.Water Reaction

~

Radr:):y,;~

200

---Tolar.. Drywel

~ '50+--------4--------+-------~--~----~~----~r_------~

~

~

  • r:.-

CJ i

ED 2 100+--------4----~--~------~--------~------_4--------~

-0

~

c 5O+-~~~_4--------+_------~--------~------~r_------~

o~~~~~~~~~~~~~==~~~~

o 5

10 15 TIme (days) 20 25 30 LIMERICK GENERATING 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

1 6

5 t= z w

0 a:

w c..

w

~ 4

..J 0

~

~

z V

/

/

/

2... <<

a:... 3 z

w 0

Z 0

0 V

/

(

z w

(.7 0 a: c 2 l:

I 1

1

~

~~

~V ~

~-.(~

,O\\-.\\\\)

~"'\\~

~o~o V

L V

v

" V

~

-ro- __

~................

150SCFMP~.....

~.IIIt ******........

URGE (ORYWEU) -

'so.*****

SCf:M*****-..

RECO******

418/ ****

IVER*........

(DFt

'YW ELL) 1 NO CONTROL 150 SCFM RECOMBINER V(SUPPRESSION CHAMBER)

V-(SUPPRESSION CHAMBER)

~---'---l---... --

.... --111 ------t---

--- ~--

--........ t... *-=:.-=- -----

I

.-.~

~.-.~.-. ----.----

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

  • ..L~
  • 2 3

4 TIME AFTER LOCA (DAYS) iII ___

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

5 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT TERM CONTAINMENT HYDROGEN CONCENTRATION AFTER LoeA FIGURE '6.2-42

t=

z W

20

(.)

a::

W Go. w18

~

...I

~ 16

~

~ 14 a::

~ 12

(.)

~

u 10 z

W

~ 8 0,

z::

6.

4 2

I 150 SCFM RECOMBINER WILL KEEP H2 NOTE:

I CONCENTRATION BELOW 0.08 V% IN' I

THE SUPPRESSION CHAMBER.

150 SCFM, PU!tGE WI~~ KEEP H2 CONCENTRATION BELOW O.O~ V%

I IN THE SUPPRESSION CHAMBER.

I I

I I

~

I

~

R"l'J'JE\\"\\..\\ ---~

r-l'TRO\\" ~~

NO CO


~

I

~

~

~

~

I I

~

~

~

.~

~

~

~

~/

V

/' /'

150 SC NO CONTROL

~.':":'...,

/

.!M.!..URGE(DRYWELL)

(SUPPRESSIONCH~~~~; __.""_- __.... --

... ~ -~--

I

.~

        • ~......

-10

  • ...... J.~.~~~ RECOMBINER (DRYWELL)

_ -.. _ -:'1-r-

___ -*+':~:*.:::f*::1::.:*.:;: ~'_~_.. n rn-**~.... "::......................,

.. r*.. *.. -r...... *..........................................................,........

- ---.... --.----.1-25 3

o 5

10 15 o

20 TIME AFTERlOCA (DAYS)

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM CONTAINMENT HYDROGEN CONCENTRATION AFTER LOCA FIGUR.E 6.2-43

7 6

j:" 5 z

w

(.)

a:

w

~

a..

w

~

l

..J 4 0 >

Z 0

a:

~

/

~V

~ -----./'

.... z 3 w

u Z

0,

(.),

Il \\

Z w

~........

X 2

0 1

I o

1

'I{'fIE,\\..L)

CON"l'O\\" \\OR NO

~

~

~

~

60 SCFMI RECOMBINER (DRYWELL)

. _1. *****.. _..., - '1-,, - ~ -, l' -,.. ' -"

.. I_I

..........,~I.

60 SCFIVI P I

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

~ ~... ~.~_~~GE(DRYWE III

... -~.,.....,,"'...... -....

NO C~NTROL (SUPPRESSION CHAMBER)

.-' ~I_'_I- _I_'_'_I_'.~'_

I I

,I

~,,,,..

  • It-
  • _
  • _ I _ 1_
  • _

I.

I i __

60 SCFMI RECOMBINER (SUPPRESSION CHAMBER

"" ~"""

60 SJF

-,..".",~~ PURG

,_,. E (SUPp

'_"':-' RESSION

--.,~_ CHAMBeR)

-11~,_

'~.---

2 3

4 TIME AFTER LOCA (DAYS)

~......

1_'

  • 1' __,

5 LIMERICK GENERATING STATION, UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT SHORT TERM CONTAINMENT OXYGEN CONCENTRATION AFTER LOCA FIGURE 6.2-44

15 I-Z w (J

1:1:

W CL.

W

~

I

)

..J 0

~

z 0 j: 10

<C 1:1:

I-Z w (J

~

(J

~

~

Z w

0 >

)(

0 5

I

~

I

~

~

~

~.:

,-1 _ 1- -,

~-- 1 ___ -

~

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

l __

V

-~' ~-,

o 5

I I

~

      • *'------1.. ---------.-~'-

~-

-,-'" ~,.~ ~,.,.

I 10 15 TIME AFTER LOCA (DAYS)

I I

NO CONTROL I

60 SCFM RECOMBINER

-. ~ If' -; 1_ i -*.* I *

~ '-

60 SCFM PURGE

~.......... _-..........,......,.. "'... ---

20 25 I

~_I_II ~.-

........, ~.....

I 3 o LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM DRYWELL OXYGEN CONCENTRATION AFTER LOCA FIGURE 6.2-45

9 8 I I

7 i=

z w

(J a: 6 w

A.

W

E

~

I I

0 5

2-I i

z 0

j:::

~ 4 NO CONTROL a:

I z

w (J

Z 0

60 SCFM RECOMBINER (J 3 I

Z

~

r-. * -"

~.-

1._*---,1 ***. _----... -..- -.*..*. _I. _.1_..

  • I
  • 1-., ~ -.. _._- _,

w V"

X 0

r_

2

...,,-I,

--...~

1 l....

~,

~"'"

i

~'- -~.,,-,

~-.

60 SCFM PURGE I

'I

"--,. -. ;-.... !Ia-...... Ia-.............................. 'w...... ~

~

~.....,......... ~

l __

0 5

10 15 20 25 30 TIME AfTER LOCA (DAYS)

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM SUPPRESSION CHAMBER OXYGEN I

CONCENTRATION AFTER LOCA FIGURE 6.2-46

LGS UFSAR Figure 6.2-47 Deleted

I SEE FIG. 6.2-48 I==

SHEET 2

,.. OIA. PRESSURE

~,. TEST PENETRATIONS

~FOR DOOR SEAL SEE FIG. 6.2-48, SHEET 3

J I PLAN VIEW OF PERSONNEL LOCK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCK PENETRATIONS (SHEET 1 OF3)

FIGURE 6.2-48

2" DIA.ELECTRICAL PENETRATIONS ----.....

3" DIA.

EQUALIZING VALVE PENETRATION LOCK

~

I I

I I

I I

- - ---t ---

I I

I I

I r--

ELEVATION VIEW OF EXTERIOR BULKHEAD

~-LOCK 1" DIA. PRESSURE

---!-{o-- TEST PENETRATIONS FOR AIR LOCK LIMERICK GENERATING STATION UNITS 1 AND 2 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

r--. -+ -_.-

I I.

I I

_-- 2" DIA. ELECTRICAL PENETRA TION 3

U DIA.. EQUALIZING VALVE PENETRATION


. --+1t--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)

FIGURE 6.2-48

PRESSURE TEST CONNECTION,

--- --;:=.--'\\

~

=t A

LOCK I

<t.

I I

I I

I

---+ ---

~!

AI.

I f-f--

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

FIGURE 6.2-49

DOOR SEAL -----t--.

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

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

FIGURE 6.2 M 4I

INTERIOR DOOR ---..J TIEDOWN -----......

---INTERIOR BULKHEAD


INSIDE LOCK LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PERSONNEL LOCK INNER DOOR TIEDOWNS FIGURE 6.2-SO

QUANTITY 4

4 A

NPS 6

15 3/S x (BAR ROLLED A

LENGTH 14 3'16 30 3'4 FLANGE NO. OF OIA.OF BOLT C

0.0. 1.0. THK.

HOLES HOLES CIRCLE DIA.

11".6.07" - 3'8" 8

7'8-9 1'2-2 "2-23 "2" -15 1'4". 1,2" 16 1 "8" 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 IS STAINLESS STEEL; 304L FOR THE MESH.

PERF. _3/S" THK.

5/S"' DIA. HOLES ON 7/S" CENTE RS 4-

~

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

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

FIGURE 6.2-51 Rev. 09 11/99

PLAN t PEN I

~

~I

-Ijl[ 1 £'j,~l r-It I I* -

!' \\ I 11 I

i Toe EL 181'*1'"

ELEVATION CS STRAINER ARRANCEMENT Sc..='::::f'1 SilnEN~

SU~~:" '\\;f iC.~"N

'r;'.

~

~ '.

5----'1 cU-~o*:>-

'\\.~.;.Z

~~~!~.

  • \\ 1-... /

~"""~=-".

/'\\.

PLAN ELEVATION RHR STRAINER ARRANGEMENT TOC EL 18,'-11"

.0.0 0

0 0 **

  • o'V
  • 0 o ** 0<3 ~.

0.0.

00

.0. q 0

~~\\~~~~'1;\\

~..... 7

,.1 ~~,..'?:,,;..

I' f"~:~C::

/~~~ lX" PLAi:: $'J?P~T

~,.

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

\\;::?Z ':'ii"ACnMENi PECO ENERGY COMPANY

~.:.-'

PLA~

LIMERICK GENERATING STATION uoou:"::

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

FIGURE 6.2-51 Rev. 09 11/99

i R

R 0

d d

§

'l II

~....

l-

~

~i B

Fa

~

U t;

§ !

.I ~

~

r.

J..

fI

~

'1.; -

}-

s l1:

r 0

0

~

0 A

R

~

d q

q q

q

'~"UI."-"'"

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR ENCLOSURE DRAWDOWN FIGURE 6.2-52 REV. 7 12/97

INTENTIONALLY LEFT BLANK LIMERICK GENERAT[tIj STATION

~ITS I AND 2 UPDATED FlNfl.. SAFETY ANAlYSIS REPORT EVENT TREE FOR TIP SYSTEM LINE ISOLA T ION FIGURE 6.2-53 Rev. 1 July/c)l

LGS UFSAR Figures 6.3-1 through 6.3-10 Deleted

1 2 I

-I I

'f

~

C!1

~omlnal Decav l'1eat :.Jrve J ~ E-Go -

Aoo~nalx-p( Oecay Heat C~rve 08 c:

);

0

~.6..

Q..

~

U 1.1.1

.:l

> 4..
l.:..

. ~--'.-

.J

l-O

.1 01 I

1 10 100 1000 10000 TIme Arter ereal (seccnas)

UMERICK GENERATING STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT NORMAUZED POWER VS TIME AFTER BREAK (SAFER/GESTR METHODOLOGy)

FIGURE 6.3-11 Rev. 07 12/97

a:

w

~

0

~

oc{

u w

0 1.2~------------------________________________________________________

~

1.0t--___

OB 0.6 0.4 1.0 10 100 1,000 10.000 100.000 1.000,000 TIME AFTER BREAK lsec)

LIMERICK GENERATING STATION UNITS 1 AND 2 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

" \\.

,

  • r [

.1.

'--__ ---JI I I.... 1 ___

---I OFFiCe-

"'. TOILET UTILITY LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT CONTROL ROOM ARRANGEMENT FIGURE 6.4-1 REV. 13 09/06

COOLING TOWE..

UNIT-'

TU... INE ENCL.

UNIT-'

COOLING TOWER UNIT-'

/'

I"A.. KING AREA LIMERICK GENERATING STATION UNITS 1 AND 2 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