ML22278A224

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Rev. 21 to Updated Final Safety Analysis Report, Figures
ML22278A224
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: ML22278A224 (152)


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Load Case: AXISYMMETRIC GE CO-ADS ~NVELOPE (WIDENED - 15%)

Node: 154 Direction: VERTICAL Elev: 177'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-320

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Load Case: AXISYMMF.TRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 128 Direction: VERTICAL Elev: 201 '-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-321

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 130 Direction: VERTIC~L Elev: 201'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC fiGURE 3A*322

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Load Case: AXISYMMETRIC GE CO-ADS ~NVELOPE (WIDENED - 15%)

Node: 106 Direction: VERTIC\L Elev: 217'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-323

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 108 Direction: VERTICAL Elev: 217'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*324

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 104 Direction: VERTICAL Elev: 239'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC fiGURE 3A- 325

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Load Case:

AXISYMMETRIC GE CO-ADS ~NVELOPE (WIDENED - 15%)

Node: 81 Direction: VERTIC\L F,lev: 253'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*326

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Load Case: AXISYMMETRIC GE CO-ADS ~NVELOPE (WIDENED - 15%)

Node: 19

-- - - - Direction: VERTIC~ Elev: 253'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VE RTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-327

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 77 Direction: VERTICAL Elev: 269'-0 Dampin~: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A- 328

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Loan Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 58 Direction: VERTICAL Damping: 0.005,0.01,0.02,0.03,0.05


Elev: 283'-0 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-329

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Load Case:

AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 60 Direction: VERTICAL Elev: 283'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-330

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 56 Direction: VERTICAL Elev: 304'-0 Damping:

0.Op5,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-331

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 35 Direction: VERTICAL Elev: 313'-0 Damping:

0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VE RTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-332

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Load Case: AXISYMMETRIC GE CO-ADS ~NVELOPE (WIDENED - 15%)

Node: 43 Direction: VERTIC\L Elev: 313'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-333

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (~lIDENED - 15%)

Node: 21 Direction: VERTICAL Elev: 333'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-334

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Load Case:

AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 33 Direction: VERTICAL Elev: 333'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*335

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

Load Case: AXISYMMETRIC GE CO-ADS ~NVELOPE (WIDENED - 15%)

Node: 9 Direction: VERTIC\L Elev: 352'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-336

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Load Case: AXISYMMETRIC GE CO-ADS ~NVELOPE (WIDENED - 15%)

Node: 13 Direction: VERTIC~L Elev: 352'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-337

PERIOD-SEC.

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Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDRNED - 15%)

Node: 129 Direction: VERTICAL Elev: 201'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*338

PERIOD-SEC.

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

Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 107 Direction: VERTICAL Elev: 217'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC fiGURE 3A-339

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Accelera ticn Spec tra for REACTOR ENCL.

Load Case: AXIS~F.TRIC GE CO-ADS ~NVELOPE" (WIDENED - 15%)

Node: 80 Direction: VERTICAL Elev: 253'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN.ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-340

PERIOD-SEC.

o 'J!

1. 2S L.J I

cr V'

z a

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0.00 O. I 2 5 (3 1 0 2 5 (l 10 0 2 6 8 100 FRfOUENCY-[P',

Accelera tion Spectra for REACTOR ENCL.

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

Loa~ Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 59 Direction: VERTICAL


Elev:

Damping: 0.005,0.01,0.02,0.03,0.05 283'-0 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-341

PERIOD-SEC.

10 'J  : fJ S 1 o G!

,--T-iT-j-r--i--'---,-----,-I,-i~-,----I---,---~ I I i ~--~----i

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Accele ra tion Spec tra for REACTOR ENCL.

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

Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 54 Direction: VERTICAL Elev: 313'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-342

PEAIOD-SEC.

1. 25 U

I cr fJ"t 1. 00 Z

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ca:::

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cr

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Accele~'3 tion Spec tra for REACTOR ENCL.

Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 32 Direction: VERTICAL Elev: 333'-0 Damping:

0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*343

PERIOO-5EC.

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

Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 12 Direction: VERTICAL Elev: 352'-0 Dampin~: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-344

PERIOD-SEC.

IU r;  ! G ~ ~ G ~!

1 1- i T 1 r - I [-----,--- I 1 1 1 I i-T-i----r--------i--f,T,-,--i---,-----r------1 I. 50 -----------

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cr O. 50 1 - - - - - - + - - - - - , - - --- - r-0.25 O. 1 2 I.j (') [S 1 0 2 Accelera tion Spec tra for REACfOR ENCL.

Load Case:

AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 6 Direction: VERTICAL Elev: 410'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO-ADS AXISYMMETRIC FIGURE 3A-345

IO_.O~ . .-.~--r---~____IT07l~'-.--._-r~__- .______C~lrr~-.-.___r -__~__~O.CI

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~REOUENC'-(r~

Acceleration Spectra for CONTROL STRUCTURE Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 7 Direction: VERTICAL Elev: 217' Damping:

0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-346

PERIOD-SEC.

I!) 'J I I) I) , 0 I)'

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Node: 7 Direction: VERTICAL Elev: 239' Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*347

PERIOD-SEC.

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1 "

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c. .?!. ~---- - - --. - --I-+-f-l-t----- - - - t--II--I--I-++-t----I---+--+-..-f--HI-H FREQUENCY-CPS Acceleration Spectra for CONTROL STRUCTURE Load Case:

AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 7 Direction: VERTICAL Elev: 254' Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-348

PERIOD-SEC.

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Node: 7 Direction: VERTIC~ Elev: 269'-0 Dampin~: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-349

PER I OO**SEC.

10.0 1.0 0.1 0.01 I" I I I I I " I I I I I I II I I I I I I I U

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Node: 7 Direction: VERTICAL Elev: 289' Dampin~:

0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-350

PERIOD-SEC.

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Node: 7 Direction: VERTICAL Elev: 304'-0 Damping: 0.005,O.OI,O.02,0.03,O.O~

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-351

PEIUOO-SEC.

10r-.Orr~~-'--T---r-----,I,O~r-T-r-r~~-,------Or*rl~.,..'---~~

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O. I ' II l. 0 ' 6 8 10.0 II 6 II IDO FREOUENCY-CPS Acceleration Spectra for CONTROL STRUCTURE Load Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 7 Direction: VERTIC~L Elev: 332' Dampin~: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-352

co q

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(~3S/1..:I) Al.l~013A.:I0 Sl.N3NOdWO:) 1\tll.N39N\t.L ON\t l\tIO\t~

LIMERICK GENERATING STATION LOAD POINT NO. 1 UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING VELOCITY (SHEET 1 OF 4)

FIGURE 3A-353

co q

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(~3S/1..:j) Al.l~013" .:AO Sl.N3 NOdWO::> 1\tll.N3~N\t1. ON\t l\tIO\t~

LOAD POINT NO. 2 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING VELOCITY (SHEET 2 OF 4)

FIGURE 3A-353

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LIMERICK GENERATING STATION LOAD POINT NO. 3 UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING VELOCITY (SHEET 3 OF 4)

FIGURE 3A-353

CD q

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LIMERICK GENERATING STATION LOAD POINT NO. 4 UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING VELOCITY (SHEET 4 OF 4)

FIGURE 3A-353

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LIMERICK GENERATING STATION UNITS 1 AND 2 LOAD POINT NO. 1 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING ACCELERATION (SHEET 1 OF 4)

FIGURE 3A-354

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LIMERICK GENERATING STATION LOAD POINT NO. 2 UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING ACCELERATION (SHEET 2 OF 4)

FIGURE 3A-354

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LIMERICK GENERATING STATION LOAD POINT NO. 3 UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING ACCELERATION (SHEET 3 OF 4)

FIGURE 3A-354

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LIMERICK GENERATING STATION LOAD POINT NO. 4 UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING ACCELERATION (SHEET 4 OF 4)

FIGURE 3A-354

A SEE FIGURE 3A-356 FOR SCHEMATIC OF SECTI ~ A-A A

RADII FROM CENTERLINE OF CONTAINMENT I I I ARE: 12.8' 15.0' 35.8' o- DOWN COMERS tt -- SUBMERGED STRUCTURE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TOP VIEW OF 36° SECTOR OF A TYPICAL MARK II SUPPRESSION POOL FIGURE 3A-355

~L-

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j 21.8' I DOWNCOMERS

~ SUBMERGED 2 STRUCTURE I-- WITH LOAD 3 POINTS I THROUGH 4 I--

4 1 , I~ L-____________________________________ ~

~12.8'_+t I RADII FROM ~15.0'--+I g~NTERLINEt.....-----24.31------~.

~~AlNMENT I 30.8'--------~ ..

I 35.8'------------c;~

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT SCHEMATIC VIEW OF SECTION A-A OF TYPICAL MARK II SUPPRESSION POOL FIGURE 3A..356

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0.1 1.0 10 e/a LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT MODEUDATA COMPARISONS (SHEET 1 OF 4)

FIGURE 3A-357

F = (1 + CM) Plf a 2

U + pa CL U U Z-1 where a = D/2 000 0.0.-. - - - REFERENCE 3A*42 000 0 MODEL T 00 0 l Z D

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FIGURE 3A*357

U,LJ REFERENCE 3A-44 4

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FIGURE 3A-357

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o .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 ela LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT MODEUDATA COMPARISONS (SHEET 4 OF 4)

FIGURE 3A-357

u FLOW LIFT, L DRAG,D LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CYLINDER LOCATIONS FIGURE 3A-358

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT INTERFERENCE ON STANDARD DRAG:

THREE CYLINDER ARRANGEMENT FIGURE 3A-359

~

C~ d

~

C~: d U ~

FLOW

THREE CYLINDER SIDE-BY-SIDE ARRANGEMENT FIGURE 3A-360

v y

1 u ~----...... x FLOW LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT FLOW AROUND UNEQUAL CYLINDERS FIGURE 3A-361

SECTIONS LOCATIONS

~

1-5 DRVWELL WALL 6-11 WETWELL WALL 12-13 SHIELD WALL 14-20 PEDESTAL AXIS OF SYMMETRY 21-25 DIAPHRAGM SLAB 26-30 BASE SLAB

  • EL. 308'*3"

~---SHIELD WALL OUTSIDE R c 8' R=19' REBAR R=25'"

-j~=27' I I WETWELL WALL

R=42' R= 8' IR=16' R=33' i

-=---+-........

  • EL. 183'-6"

.. ~' \

~

). ~  :

TOP REBAR (INSIDE)

BOTTOM REBAR TRANSVERSE (OUTSIDE) SHEAR TleS(TVP)

LIMERICK GENERATING STATION

-0 seCTION WHERE STRESSES ARE ASSESSED UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT ASSESSMENT SECTION LOCATION FIGURE 3A-362

DRYWELL WALL SECTIONS: 1, 2 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 - - - - - - -

3, 6 - - - - - - -

4, 4a 18.57 31.36 5.82 13.90 11.17 6.50 -0.233 4T, 4aT 7.14 6.83 13.4 19.75 16.83 10.99 -0.967 5, 5a, 7, 7a 25.66 30.66 9.95 13.45 20.82 4.60 -0.257 5T, 5aT, 7T, 11.36 -4.66 16.34 24.41 32.46 11.67 -1.542 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Eq~ations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DRYWELL WALL FIGURE 3A-363 Rev. 12 9/04

DRYWELL WALL SECTIONS: 3 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 -0.46 -0.07 -0.55 -0.04 -0.28 0.12 -0.432 3, 6 11.4 6.26 11.3 4.2 15.7 15.1 -0.200 4, 4a 9.97 43.0 14.8 19.5 17.4 11.4 -0.218 4T, 4aT 3.45 18.7 23.8 28.0 24.5 12.2 -0.926 5, Sa, 7, 7a 21.1 40.2 21.3 17.4 36.9 20.1 -0.460 ST, SaT, 7T, 14.9 15.9 34.5 27.4 52.0 17.6 -1.38 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete ~ompressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DRYWELL WALL FIGURE 3A-364 Rev. 12 9/04

DRYWELL WALL SECTIONS: 4 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 -0.55 -0.02 -0.69 0.06 -0.35 0.15 -0.097 3, 6 13.0 6.44 13.0 4.2 17.1 20.31 -0.230 4, 4a 8.49 41.7 21.8 20.9 23.2 10.8 -0.202 4T, 4aT 4.43 20.3 29.2 30.2 32.4 11.4 -0.822 5, 5a, 7, 7a 26.3 39.3 28.7 17.5 39.7 24.9 -0.522 5T, 5aT, 7T, 16.8 16.3 40.6 28.6 48.0 21.8 -1.431 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DRYWELL WALL FIGURE 3A-36S Rev. 12 9/04

DRYWELL WALL SECTIONS: 5 Max.

MAXIMUM REBAR .sTRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 -0.73 1.04 -0.80 1.0 -0.35 0.16 -0.106 3, 6 15.5 10.3 14.6 5.5 20.0 18.6 -0.294 4, 4a 31.2 33.7 21.6 6.9 14.6 39.8 -0.671 4T, 4aT 22.6 13.2 24.1 24.4 22.7 36.5 -0.671 5, 5a, 7, 7a 43.6 33.2 32.8 9.5 37.6 54.0 -0.931 5T, SaT, 7T, 30.4 9.9 45.5 22.1 47.7 46.2 -1.71 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DRYWELL WALL FIGURE 3A-366 Rev. 12 9/04

DRYWELL WALL SECTIONS: 6 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 -1.2 1.08 -0.76 1.7 0.63 0.161 -0.99 3, 6 16.9 17.7 16.5 4 .8 20.6 0.52 -0.361 4, 4a 31.1 39.6 26.8 9.2 18.6 43.7 -0.582 4T, 4aT 26.0 48.7 26.7 8.1 28.2 35.0 -0.718 5, 5a, 7, 7a 50.1 43.1 36.0 12.9 45.7 44.8 -1.009 5T, 5aT, 7T, 24.9 48.8 53.9 26.7 47.6 27.5 -1.592 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Eq~~tions are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES WETWELL WALL FIGURE 3A-367 Rev. 12 9/04

DRYWELL WALL SECTIONS: 7, 8, 9 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 -1.36 9.7 -1.4 4 .8 2.09 0.89 -0.210 3, 6 25.5 20.3 23.3 6.8 28.4 5.3 -0.427 4, 4a 14.8 38.4 26.8 25.5 26.2 13.6 -0.616 4T, 4aT 12.8 46.2 34.6 33.0 33.8 14.0 -1.31 5, 5a, 7, 7a 37.7 37.0 47.9 21.8 48.6 15.2 -0.819 5T, 5aT, 7T, 33.2 41.0 50.0 46.3 53.9 17.3 -2.12 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES WETWELL WALL FIGURE 3A-368 Rev. 12 9/04

DRYWELL WALL SECTIONS: 10 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 -1.68 15.8 -1.5 7.4 3.35 1.1 -0.254 3, 6 27.5 30.7 25.5 7.58 31.1 0.70 -0.503 4, 4a 16.6 42.4 29.1 35.3 31.4 5.3 -0.744 4T, 4aT 12.2 35.6 38.0 39.7 37.9 8.13 -1.50 5, Sa, 7 , 7a 37.5 40.1 43.6 27.5 50.1 6.7 -1.13 5T, SaT, 7T, 29.4 46.7 53.8 35.6 52.4 7.4 -2.25 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES WETWELL WALL FIGURE 3A-369 Rev. 12 9/04

DRYWELL WALL SECTIONS: 11 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop Diag. (2) (3) 1 -1.57 4.95 -1.5 2.96 1.16 2.81 -0.233 3, 6 29.8 21.2 27.1 8.48 34.3 15.3 -0.527 4, 4a 38.1 35.5 33.2 6.48 20.3 42.9 -0.703 4T, 4aT 36.1 18.5 38.2 11.2 25.1 44.5 -0.990 5, 5a, 7, 7a 53.9 32.9 46.0 9.0 45.0 45.0 -1.04 5T, 5aT, 7T, 47.2 40.6 51.2 17.0 47.4 45.4 -1.69 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES WETWELL WALL FIGURE 3A-370 Rev. 12 9/04

DRYWELL WALL SECTIONS: 12 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER PLATE OUTER PLATE Transverse Stress, Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop (2) (3) 1 0.39 3.6 -0.11 1.2 1.0 -0.071 3, 6 7.1 8.7 2.1 2.9 1.4 -0.293 4, 4a 2.2 9.2 -0.64 3.7 7.5 -0.265 4T, 4aT 2.0 8.8 0.81 3.3 7.5 -0.265 5, 5a, 7, 7a 8.5 12.8 2.7 5.1 9.5 -0.407 5T, 5aT, 7T, 8.3 12.4 2.5 4.7 9.5 -0.407 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES SHIELD WALL FIGURE 3A-371 Rev. 12 9/04

DRYWELL WALL SECTIONS: 13 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER PLATE OUTER PLATE Transverse Stress, Combination Ties KSI Equation (4 ) Vert Hoop Vert Hoop (2) (3) 1 -0.28 0.08 -0.57 -0.10 0.128 -0.077 3, 6 9.7 3.5 2.9 1.1 0.63 -0.404 4, 4a -0.65 0.29 -0.94 -0.15 0.26 -0.128 4T, 4aT -1.45 -1.73 -0.53 1.03 0.26 -0.128 5, Sa, 7, 7a 10.7 3.6 2.9 1.1 2.4 -0.444 5T, SaT, 7T, 9.9 1.9 3.3 2.1 2.4 -0.444 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, SaT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES SHIELD WALL FIGURE 3A-372 Rev. 12 9/04

DRYWELL WALL SECTIONS: 14 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4 ) Radial Hoop Radial Hoop (2) (3) 1 -1.0 1.0 -1.2 1.2 0.34 -0.157 3, 6 17.2 13.4 29.2 17.4 3.9 -0.352 4, 4a -1.3 2.4 -1.7 2.0 0.31 -0.230 4T, 4aT 7.98 7.0 -2.31 4.97 0.31 -0.230 5, Sa, 7, 7a 17.2 14.7 25.6 17.2 3.3 -0.432 5T, SaT, 7T, 25.7 19.3 25.0 20.2 3.3 -0.432 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE 3A-373 Rev. 12 9/04

DRYWELL WALL SECTIONS: 15 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4 ) Radial Hoop Radial Hoop (2) (3) 1 -1.5 0.94 -2.2 0.32 0.35 -0.290 3, 6 43.9 27.2 52.5 33.6 4.7 -0.649 4, 4a 4.5 32.2 6.1 47.0 21.1 -0.474 4T, 4aT 14.5 -4.8 4.9 -5.9 48.3 -0.910 5, 5a, 7, 7a 52.9 50.1 52.9 51.8 39.4 -0.856 5T, 5aT, 7T, 49.9 8.2 51.9 -4.0 27.4 -1.017 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE 3A-374 Rev. 12 9/04

DRYWELL WALL SECTIONS: 16 Max.

MAXIMUM REBAR -STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4 ) Radial Hoop Radial Hoop (2) (3) 1 -1.5 1.1 -2.0 3.1 0.34 -0.266 3, 6 30.3 13.02 39.4 29.1 0.86 -0.526 4, 4a 6.9 12.6 4.8 30.4 7.9 -0.678 4T, 4aT 13.3 13.3 5.7 28.0 15.0 -1.051 5, Sa, 7, 7a 45.0 26.1 42.7 36.8 19.6 -0.931 5T, SaT, 7T, 37.3 16.0 22.7 15.5 27.9 -1.249 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE 3A-375 Rev. 12 9/04

pF-"

DRYWELL WALL SECTIONS: 17, 18 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4 ) Radial Hoop Radial Hoop (2) (3) 1 -2.1 5.0 -2.7 12.9 9.0 -0.382 3, 6 9.9 8.5 10.5 17.0 12.9 -0.690 4, 4a -4.1 11.9 -4.8 28.3 17.0 -0.681 4T, 4aT 4.13 13.8 -4.3 28.9 26.8 -0.635 5, Sa, 7, 7a 18.6 15.7 20.5 29.8 22.5 -1.017 5T, SaT, 7T, 23.0 22.1 22.0 32.6 38.9 -0.968 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 77, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE 3A-376 Rev. 12 9/04

DRYWELL WALL SECTIONS: 19, 20 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4) Radial Hoop Radial Hoop (2) (3) 1 -2.01 -0.176 -2.95 0.27 0.59 -0.424 3, 6 17.9 5.26 11.8 5.4 4.7 -0.483 4, 4a 4.86 3.69 -5.2 7.1 5.68 -0.744 4T, 4aT 5.2 -6.1 -5.39 -4.8 5.68 -0.744 5, 5a, 7, 7 a 25.9 7.2 32.5 12.8 15.9 -0.851 5T, 5aT, 7T, 26.2 -5.8 32.3 8.2 15.9 -0.851 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE 3A-377 Rev. 12 9/04

DRYWELL WALL SECTIONS: 21 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4 ) Radial Hoop Radial Hoop (2) (3) 1 - - - - - -

3, 6 8.5 8.6 6.9 7.7 1.01 -0.073 4, 4a 38.8 30.2 28.9 22.7 8.8 -0.374 4T, 4aT 32.8 21.6 35.9 27.6 9.5 -1.82 5, Sa, 7, 7a 35.6 30.1 29.3 23.3 8.8 -0.365 5T, SaT, 7T, 31.7 21.5 34.6 28.0 8.9 -1.83 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DIAPHRAGM SLAB FIGURE 3A-378 Rev. 12 9/04

DRYWELL WALL SECTIONS: 22, 23 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4) Radial Hoop Radial Hoop (2) (3) 1 - - - - - -

3, 6 7.9 9.5 10.2 13.0 4.46 -0.370 4, 4 a 14.1 21.5 18.4 24.2 16.1 -0.383 4T, 4aT -11.1 12.3 26.2 29.8 7.0 -1.367 5, Sa, 7, 7 a 16.4 23.1 23.7 27.9 18.0 -0.623 5T, SaT, 7T, -13.1 16.0 25.5 35.9 7.2 -1.727 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DIAPHRAGM SLAB FIGURE 3A-379 Rev. 12 9/04

DRYWELL WALL SECTIONS: 24 Max.

MAXIMUM REBAR STRESSES, KSI (1) (3) Concrete Load INNER OUTER Transverse Stress, Combination Ties KSI Equation (4) Radial Hoop Radial Hoop (2) (3) 1 - - - - - -

3, 6 10.2 9.6 9.1 8.0 3.0 -0.272 4, 4a 22.8 22.6 30.S 21.1 S.9 -0.842 4 T, 4 aT -8.61 -8.29 33.2 29.4 4.2 -1.S9 S, Sa, 7, 7a 27.9 2S.4 33.4 24.4 6.2 -0.931 ST, SaT, 7T, -10.3 12.3 3S.S 30.8 4.9 -1.738 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "-" for Compressive Stress (4) Load Combination Equatlons are taken from Table 3A-14, 4T, 4aT, 5T, 5aT, 7T, 7aT include thermal components.

(5) Values reflect analysis with an initial Drywell air temperature of 135°F. Increasing this temperature to 150°F does not adversely impact the results of this Design Assessment Report.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DIAPHRAGM SLAB FIGURE 3A-380 Rev. 12 9/04

DIAPHRAGM SLAB SECTION: 25 Max.

1 I

I MAXIMUM RF.BAR STRESSES, KSI (1)(3)


~I~N-N-E-R----~----~O~~R--~1~~~~---+ Stress, 1 ______ ~------~-----U_T-E---- Transverse Concrete Load Combination 1 1 Ties KSI Equations (4) Radial Hoop Rania1 Hoop (2)(3) 1 - - - - - -

1 1 3, 6 1 13.0 1 15.5 12.1 14.5 1 0.66 -.157 I

4, 4a 1 26.7 28.0 23.5 30.6 9.9 -.336 4T, 4aT 12.9 24.0 1 26.1 135.4 6.5 1 -2.04 5, Sa, 7, 7a 33.6 38.5 1 28.6 135.9 10.4 1 -.423 ST, SaT, 7T, 19.3 31.8 41.1 142.4 9.5 -2.40 7aT I 1

1 I 1 I 1 NOTES: (1 ) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) tI+tI for Tensile Stress; t I _ tI for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4'r, 4aT, ST, Sa"', 7'r, 7aT include thermal components.

LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DIAPHRAGM SLAB FIGURE 3A-381

BASE SLAB SECTION: 26 Max.

MAXIMUM REBAR STRESSES, KSI (1)(3) Concrete INNER OUTER Transverse Stabs, Load Combination Ties KSI Equations ( 4 ) Radial Hoop Radial Hoop (2)(3) 1 - - - - - -

3, 6 1.7 16.6 5.93 6.22 5.29 -0.318 1

4, 4a 2.72 1.611 7.10 3.291 0.43 -0.213 4T, 4aT -5.21 -5.63 15.2 14.9 3.4 -1.21 1

5, Sa, 7, 7a 10.9 20.7 10.4 9.51 4.03 -0.443 5T, SaT, 7T, 7aT

-6. 36 1 -4.95 18.4 17.3 3.12 1 -1.34 1

1 I I I I I I 1 NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "_" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, SaT, 7T, 7aT include thermal components.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A-382

BASE SLAB SECTION: 27 I I I Max. I MAXIMUM REBAR STRESSES, KSI (1)(3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equations ( 4 ) Radial Hoop Radial Hoop (2)(3>1 1 - - I - - I - I -

3, 6 25.4 26.8 15.5 6.43 24.7 -0.479 4, 4a 10.3 -0.431 11.1 113.3 0.65 23.9 -0.309 4T, 4aT 22.4 -7.3 29.8 33.1 I -1.70 I

5, 5a, 7, 7a 39.8 34.4 29.3 13.9 41.0 -0.540 5T, SaT, 7T, 30.0 20.2 29.0 17.1 39.8 -1.79 7aT NOTES: (I) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "_" for Compressive Stress (4) Load Combination Equations are taken from Table 3A*14 ,

4T, 4aT, 5T, SaT, 7T, 7aT include thermal components.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A*383

BASE SLAB SECTION: 28 Max.

MAXIMUM REBAR STRESSES, KSI (1)(3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equations ( 4 ) Radial Hoop Radial Hoop (2)(3) 1 - - - - - -

3, 6 34.0 17.8 11.1 10.6 17.5 -0.910 4, 4a 21.7 9.15 16.9 8.7 12.5 -0.304 4T, 4aT -8.251 -8.071 17.7 113.4 6.7 -1.59 1 1 1 5, Sa, 7, 7a 5T, SaT, 7T, I 42.1 1 21.2

-8.4 I 18.2 116.1 25.2 18.7

-0.985

-1.72 I

25.4 23.7 19.8 7aT I I NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress: "_" for Compressive Stress (4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, 5T, SaT, 7T, 7aT include thermal components.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A-384

BASE SLAB SECTION: 29 Max.

Load Combination MAXIMUM REBAR STRESSES, KSI (1)(3)

INNER OUTER Concrete Transverse Stress, Ties KSI I

Equations ( 4 ) Radial Hoop Radial Hoop (2)(3) 1 1 - - - - - -

3, 6 12.7 1 15.6 9.01 8.52 11.1 -0.524 1

4, 4a 11.8 1 9.1)1 17.3 7.951 11.0 1 -0.243 4T, 4aT 9.32 -6.4°1 20.6 12.6 12.0 -1.23 5, Sa, 7, 7a 17.7 18.9 19.0 13.3 18.5 -0.508 ST, SaT, 7T, 14.4 -6.22 21.5 16.1 18.9 -1.18 7aT NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress; "_" for Compressive Stress (4) Load Combination Equa tions are taken from Table 3A-14, 4T, 4aT, ST, SaT, 7T, 7aT include thermal components.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A-385

BASE SLAB SECTION: 30 Max.

MAXIMUM REBAR STRESSES, KSI (1)(3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KSI Equations ( 4 ) Radial Hoop Radial Hoop (2)(3) 1 - - - - - -

3, 6 9.32 16.9 9.14 8.54 7.0 -0.414 4, 4a 29.9 33.t; 34.1 10.2 25.6 -0.430 4T, 4aT 29.2 5.5 38.5 12.9 27.4 -0.902 5, Sa, 7, 7a 23.9 36.5 32.9 16 6 28.4 -0.688 5T, 5a%, 7T, 1

  • 1 7aT 22.5 -6.36136.5 19 6 28.9 -0.915 I 1
  • I I NOTES: (1) Allowable Reinforcing Steel Stress = 54 KSI (2) Allowable Concrete Compressive Stress = 3.4 KSI (3) "+" for Tensile Stress: "_" for Compressive Stress (4) Load Combination Equa tions are taken from Table 3A*14, 4T, 4aT, 5T, SaT, 7T, 7aT include Thermal Components.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A*386

I I

MODE 1 MODE 2 MODE 3 f=20 HZ f=53 HZ f=93 HZ (WITH WATER MASS)

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSIENT REPORT SUPPRESSION CHAMBER COLUMNS MODE SHAPES FIGURE 3A-387

SUPPRESSION CHAMBER COLUMNS

!  ! MAXIMUM ALLOWABLE MAXIMUM !ALLOWABLE I COMBINED I

COLUMN AXIAL STRESS AXIAL STRESS FLEXURAL (KSI) (KSI)

I FLEXURAL /STRESS STRESS (KSI) STRESS (KSI) RATIO ISTRESS MARGIN %

42" dia pipe (shell element) 11.7 27.3 8.7 28.0 I 0.74 26 ITop Anchorage 22.6 29.9 I 0.76 24 IBottom Anchorage I 10 I_

NOTE: These stress margins are based on load combination 7 of Table 3A-15 which is the critical load combination.

S C

C C

II o ~!:

m O~ C m

m 3:

~"'tJ w C m W

sa ." !

"'tJ C) z n co co 1::lI z ,.c~

Zm>> r-zG) en en en (I)-m een-

~ "-tz.

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~~'V ~ >>

limo (I) ~

~~ ~ ~ ~

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j( ~ k>. '<Ii". I I

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=

K SOk/in FIGURE 3A-389

M~P. 1 lJ.ct H'Z LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER MODE SHAPES, K = 350k /ln fiGURE 3A-390

I I

I I

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J I

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r-~-

J

k. I~oo. eyt,\. I J

I Meoe ~

96.8 H&

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER MODE SHAPES,

=

K 15000kJin FIGURE 3A-391

DOWNCOMER - STRESS

SUMMARY

AND DESIGN MARGINS I

I I

I LOAD COMBINATION CONDITION IJ ALLOWABLE srrRESS (KSI)

I I

STRESS (KSI)

I DESIGN MARGIN

( %)

I I

I Equation Equation 1 I Upset 28.4 17.5 38.4 I 2 Emerqency I 42.5 19.9 53.2 I I Equation Equation 3

4 Emergency Faultea 42.5 56.7 II 37.4 20.0 12.0 64.7 I I Equation Equation 5 Faulted 56.7 I 37.4 I 34.0 I I 6 Faulted 56.7 37.'5 33.9 I I I

Equation 7 Faulted 56.7 I 24.5 I 56.8 I

NOTE: Equation numbers are based on Tahle 3A-17.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER DESIGN MARGIN FIGURE 3A-392

USAGE FACTOR

SUMMARY

OF DOWNCOMERS NORMA L/UPSET CONDITION EMERGENCY IFAUL TED CONDITIONS SBA IBAORSBA DBA

!. OBE +

- SRV, :t SRV , :t SRV , o PRESSURE o PRESSURE o PRESSURE

+/- SRV, :t SRV 2 +/- SRV 2

o THERMAL TRANSIENT o THERMAL TRANSIENT o THERMAL TRANSIENT

~O LOADS +/-SRV 2

!. CHUG o STEAM FLOW o STEAM FLOW o STEAM FLOW j~

+/- CHUG +/- CHUG +/- CHUG U

~

+/-. SRV,  :!:. SRV,  :!:.SSE

!:. SRV 2

+/- SRV 2

+/-. SSE AT PLATFORM RING 0.001 0.600 0.116 0.080 0.003 0.80 AT 24" x 24" 0.002 0.194 0.160 0.151 0.001 0.51 VACUUM BREAKER TEE

,. c:

'V AT PIPE ATTACHMENT (1) 0.001 0.545 0.078 0.071 0.003 0.70 is C ELEV.221'-O" c:

II CO ~ r-(,,) om c::Ecs m

c im 21

(,,)

co cnz z Z n (1) ORIGINAL LOCATION OF VACUUM BREAKER (ABANDONED)

(,,)

>>0" ~c~

C)O~ (l)zel ms:m >>.,,-tz- m m en m

."m~ ..,.-21

>>::DI: oo(>>>>

o."m z>>z:::!

-f>>~ >>Nel Cz O-f:D m (I)~ en-t

D-C)'"G c:0 en ..,. >>

m~  ::D 0 m

'V z

0::D

STRESS CYCLES FOR FATIGUE EVALUATION OF DOWNCOMERS LOAD TYPE No. OF CYCLES NSRVI 14100 NSRV2 7700 NOBE 50 NCHUG I 3000 NSSE I I

10 II NOBE = Cycles associated with OBE NSRVI = Cycles associated with SRV I (Submerged Structure Load)

NSRV2 = Cycles associated with SRV 2 (Inertia)

NCHUG = Cycles associated with Chugging NSSE = Cycles associated with SSE LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS'REPORT DESIGN' ASSESSMENT REPORT DOWNCOMER FATIGUE CYCLES FIGURE 3A-394

FATIGUE LOAD HISTOGRAM FOR DOWNCOMERS NORMAL/UPSET CONDITION EMERGENCY FAULTED SBA IBA or SBA DBA

-+ OBE \ ~ SRVI/ ~ SRVI/ ~ SRVI/oo Pressure Thermal 1

0 o

Pressure Thermal 1

0 o

Pressure Thermal

+ SRVl! ~ SRV2! ~ SRV2! !o Transient Stearn Flow

! 0 Transient Steam Flow

! 0 Transient Steam Flow

~ SRV2! ~ CHUG! /  !

+ CHUG

- I -+ CHUG I + CHUG

+ SRVI + SRVI + SSE

+ SRV2 .:!: SRV2

! I I I

-+ SSE

,. c:

@ ~

e C

21 m

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n 50 cycles I 3000 I 4650 I 6400! Load s~t pair 9-10 is for one of the cycles! cycles\ cycles! three above events which produce the

~

l> G') Z W Z:J> I!  ! largest combined stress.

co :I: Z l> r- C G')

U'I -0(1) en!m 00(1) :J>~z The cycles associated with oscillatory

-f, m "U)m 0'" (I) m .... ;JJ loads combined with SSE are assumed C)m I

2J ::2J m

~l>l>

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l> ", Z zCz l> -t :J> N G')

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f r i O " . p;p~ or etlu'v.

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. LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER BRACING MATHEMATICAL MODEL FIGURE i3A-396

DOWNCOMER BRACING SYSTEM - STRESS

SUMMARY

BRACING MEMBER DESIGN MARGINS FOR CRITICAL ME~1BERS AND GOVERNING LOAD COMBINATION QUADRANT(2) MEMBER(2) EQUATION(l) MARGIN -  %

1 58 7 5%

2 75 7 6%

3 126 7 5%

4 217 7 4%

Link between 221 7 3%

Quadrants NOTES: (1) Equa tion number is hased on Table 3A*15 (2) Figure 3A*396 gives location reference LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER BRACING SYSTEM DESIGN MARGIN FIGURE 3A*397

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LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE STEEL FRAMING PLAN EL. 289' FIGURE 3A-411

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CONTROL STRUCTURE I -0 " t. PLATFORMS PLANT EL. 350' FIGURE 3A-418

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FIGURE 3A-419

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@ 73.1 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE & CONTROL STRUCTURE VERTICAL AXIAL FORCES (X 10 3 KIPS)

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FIGURE 3A-420

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STRUCTURE N-S OVERTURNING MOMENTS (X1OS"K-FT)

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DBE+LOCA+SRV (5% DAMPlNG)

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DBE+LOCA+SRV (5% DAMPING)

FIGURE 3A*426

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OBE+SRV (2% DAMPING)

FIGURE 3A*427

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r '0' '0'0' LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE & CONTROL STRUCTURE E-W OVERTURNING MOMENTS (X1o&K-FT)

DBE+LOCA+SRV (5% DAMPING)

FIGURE 3A-428

REACTOR ENCLOSURE FLOOR SLABS ELEMENT ELEVATION SLAB GOVERNING REBAR~L.} STRESS NUMBER (FT) THICKNESS EQUATION(I) STRESS MARGIN (FT) (KSI) (% )

I 1 201 1.5 1 13.13 75.7 2 201 2.5 1 30.55 43.4 3 217 1.5 7a 30.90 42.8 4 217 2.0 7a 27.70 48.7 5 253 1.21:) I 7a 51.2fi 5.1 6 I 253 I 2.0 1 20.40 I 62.2 7 283 I 1.25 7a I 42.74 20.9 8 283 2.75 1 28.13 47.9 9 313 1.75 1 30.52 43.5 10 313 2.0 7a 23.83 55.9 11 313 3.0 7a 28.16 47.9 12 333 1.25 1 21.22 60.7 13 333 1.67 1 15.47 71.4 14 352 2.0 7a 36.35 32.7 15 352 3.25 7a 11.18 79.3 NOTES: ( 1 ) Taken from Table 3A-14 as follows:

Load Combination EON 1 = 1.4D + 1.7L + 1.5 SRV Load Combination EON 7a = 1.0D + 1.0L + 1.0 ESS

+ 1.0 SRV + 1.0 LOCA

( 2 ) Allowable Reinforcing Steel Stress = 54 KSI LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE MARGINS FLOOR SLABS FIGURE 3A- 429

REACTOR ENCLOSURE FLOOR STEEL BEAM(l)

ELEMENT ELEVATION GOVERNING BENDINGISTRESS NUMBER (FT) STEEL SIZE EQUATION(2) STRESS MARGIN(3)

(KSI)  %

I I 16 201 W27 x 145 1 23.00 4.2 I 17 201 W24 x 6,8 I 1 20.00 16.7 I 1A 217 W33 x 141 1 21.90 8.6 19 217 W33 x 130 I 7 27.40 15.5 I 20 253 W24 x 76 I 1 22.66 5.6 I 21 253 W27 x 84 1 20.92 12.8 22 283 72" Girder 1 24.00 o.

23 2A3 W33 x 1'12 1 19.27 19.7 24 313 56" Girder 7 30.2A 6.5 25 313 W36 x 300 7 29.44 I C).1 I 26 27 331 331 W36 IW21 x 182 I x 73 7

7 23.58 20.31 I 27.2 37.3 28 352 IW36 x 300 I 7 18.54 I 42.7 29 352 IW24 x 68 I 7 47.7 I I I 16.94 I I NOTES: (1 ) All beams are A-36 steel.

(2) Taken from Table 3A-15 as follows:

Load Combination EON 1 = D + L + SRV Load Combination RON 7 = D + L + E1+ SRV + LOCA (3 ) Allowable Rending Stresses for Governing Equations 1 and 7 are 24.0 KSI and 32.4 KSI, respectively.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE MARGINS FLOOR STEEL BEAM FIGURE 3A-430

REACTOR ENCLOSURE SUPPORTING COLUMNS ELEVATION INTERACTION STRESS RANGE LOCATION(l) MATERIALS(2) EQUATION MARGIN%

177'-201' I 29 & E ISteel I 0.77 I 23 I 177'-201' 30.5 & E I Reinforced Concrete I - 8 I 201'-217' 201'-217' 29 &

30.5 E

& E Steel Reinforced Concrete 0.78 I 22 1

I 217'-253' 30.5 & E Steel 1.02 0 253'-283' 30.5 & F, S-teel 0.88 12 283 '-313' I 30.5 & E ISteel 0.78 22 I 313'-333' 313'-333' 27.5 30.5

& E Steel Steel I 0.97 0.91 3

9 333'-352' 29 &

& E E Steel I 0.65 I 35 NOTES: (1) Figure 3~398 gives location reference (2) For Steel Supports, Load Combination EQN (7) of Tahle 5.3-1 is used: D + L + E + LOCA + SRV + P.

For Reinforced Concrete Supports, Load Combination EQN (7) of Table 3A-14 is used:

D + L + Eo + LOCA + SRV + P B LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE MARGINS SUPPORTING COLUMNS FIGURE 3A-431

REACTOR ENCLOSURE SHEAR WALLS

, , , 'COMBINED AXIAL 'SHEAR ,

WALL , 1 GOVERNING 1& BENDING STR.ESS STRESS 1

ELEVATION (FT)

I WALL MARK(l) EQUATION(2) MARGIN (%) (3) MARGIN

(% ) ( 4 )

177 Line 14.1 7a 67 1 1

177 177 177 I Line 31.9 D

Line 23 1 7a 7a 7a 1

67 48 24 1 1

12 8 1 1 177 I Line 21.5 I 7a I 29 I 9 I NOTES: (1 ) Figure 3A-398 qives location reference (2) Taken from Table 3A-14 as follows:

Load Combination EON 7a = D + L + Ess + SRV + LOCA (3) Allowable Reinforcing Steel Stress = 54 KSI (4 ) Allowable Reinforcing Steel Stress = 51 KSI LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE MARGINS SHEAR WALLS FIGURE 3A-432

CONTROL STRUCTURE FLOOR SLABS I SLAB J REBAR STRESsl ELEMENT/ELEVATION THICKNESslr~VERNING STRESS(2) MARGIN/

NUMBER (FT) (FT) EQUATION(l) KSI ( %)

I

/ 30 200 1.S 1 14.47 73.2 31 200 / 6.0 1 / 37.64 30.3 /

32 217 1.25 1 14.15 73.8 33 237 / 1.0 1 / 31.10 / 42.4 /

34 237 1.0 1 30.89 I 42.8 35 254 1.0 1 27.86 48.4 36 269 1.5 1 12.15 / 77.5 37 289 1.5 1 10.26 81.0 38 304 1.0 1 / 22.95 / 57.5 I 39 332 1.5 1 I 16.92 I 68.7 /

/

40 41 332 350 2.0 1.5 1

1 I 41.4 16.65 I 23.3 69.2 I NOTES: (1 ) Taken from Tahle 3A-14 as follows:

Load Combination EON 1 = 1.4D + 1.7L + 1.5 SRV (2) Allowahle Reinforcing Steel Stress = 54 KSI LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE MARGINS FLOOR SLABS fiGURE 3A-433

CONTROL STRUCTURE FLOOR STEEL BEAM(l)

I BENDING STRESS IELP.MENT ELEVATION GOVERNING STRESS MARGIN(3)

NUMBER (FT) STEEL SIZE EQUATION(2) (KSI)  %

I 42 200 IW24 x 130 1 23.78 0.9 I I 43 217 W30 x 210 I 7 29.90 I 7.7 I I 44 237 W36 x 300 I 7 I 27.60 I 14.8 I 45 254 W36 x 24S I 7 I 28.80 11.1 I I 46 47 269 289 42" W36 Girder x 160 7

7 25.53 27.90 21.2 13.9 48 304 W36 x 194 7 30.00 7.4 49 I 332 38" Girder I 7 24.80 23.5 I 50 I 350 W18 x 105 7 10.30 I 68.2 I NOTES: (1) All beams are A-36 steel.

(2) Taken from Table 3A-15 as follows:

Load Combination EON 1 = D + L + SRV Load Combination EQN 7 = D + L + E' + SRV + LOCA (3) Allowable bending stresses for qoverning equations 1 and 7 are 24.0 KSI and 32.4 KSI, respectively.

LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE MARGINS FLOOR STEEL BEAM FIGURE 3A-434

CONTROL STRUCTURE SHEAR WALLS WALL COMBINED AXIAL SHEAR ELEVATION GOVERNING & BENDING STRESS STRESS MARGIN (FT) WALL MARK EQUATION( 2) MA RG I N (%) ( 3 ) (%)(4)

I 177 Mh 7a 2 I 12 200 269 Mh J

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I I

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24 I

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NOTES: (1) Figure 3A-398 gives location reference.

(2) Taken from Table 3A-14 as follows:

Load Combination EON 1 = 1.4D + 1.7L + 1.5 SRV Load Combination EON 7a = 1.0D + 1.nL + 1.0 ESS

+ 1.0 SRV + 1.n LOCA (3) Allowable Reinforcing Steel Stress = 54 KSI Allowable Concrete Compressive Stress = 2.8 KSI (4) Allowable Reinforcing Steel Stress = 51 KSI LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE MARGINS SHEAR WALLS FIGURE 3A-435

CONTROL STRUCTURE STEEL PLATFORM (1)

ELEMENT ELEVATION STEEL GOVERNING BENDING STRESS J MARGIN\3)

I NUMBER (FT) GRADE EQUATION(2) STRESS I (KSI) ( %)

I 51 313 WIOx21 2 14.7 38.8 I

52 313 W12x27 2 lR.9 21.3 I I 53 322 W12x27 2 10.7 55.4 54 340 W8x24 2 10.0 58.3 I

I 55 350 W8x24 2 17.6 26.7 I 56 350 WIOx54 2 10.6 55.8 NOTES: (1) All beams are A-36 steel.

(2) Allowable bending stress = 24 KSI (3 ) Taken from Table 3A-15 as follows:

Load Combination EON 2 = D + L + To + SRV LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE MARGINS STEEL PLATFORM FIGURE 3A-436

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'N/ Ilz* .... !'lrG' ~1It:~TINGr "V l't' ...... GfUoT'NG ~,.~ DESIGN ASSESSMENT REPORT SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM SENSOR LOCATIONS FIGURE 3A-437

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FIGURE 3A-438

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FIGURE 3A-439

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LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT SECTION VIEW OF MESH SYSTEM MODELING OF SUPPRESSION POOL FOR SRV-H LOW REACTOR PRESSURE BLOWDOWN (WITH SPTMS SENSOR LOCATIONS)

FIGURE 3A-440

~ (DEGREES)

CI ::

10i -s

" J -0

(,~

")0 J ACTUAL &

MODELED COLUMtf LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT PLAN VIEW OF MESH SYSTEM MODELING OF SUPPRESSION POOL FOR SRV-L HIGH REACTOR PRESSURE BLOWDOWN (WITH SPTMS SENSOR LOCATIONS)

FIGURE 3A-441

VIEW A-A OF FIGURE 3A-441

~I). C*!:'

(1 i J 23.3.17 (1 ~) \l I~ITIAl PI Ol WATH HEIGHT 20."~3 (9) 17.9~&

TE101B TE103B TE101A TE103A (8)

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(6)

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LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT SEcnON VIEW OF MESH SYSTEM MODELING OF SUPPRESSION POOL FOR SRV-L HIGH REACTOR BLOWDOWN (WITH SPTMS SENSOR LOCAnONS)

FIGURE 3A-442

oo 1ft o

SENSOR TE-IOI B a

o o

oo 6

+

TE-IOI 0 TE-IOI F x TE-IOI H N

1ft BULK POOL TEMPERATURE o

o o

lL~

(!)

lIJ 00 o

1ft lIJ-0:::-

J

~

<<0 0 0:::

lIJ' Q..~

z:-

lIJ

~

o o

1ft o

o o

c o

90.00 l80.00 270.00 360.00 450.00 540.00 630.00 720.00 810.00 900.00 TIME SEC LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF COLUMN MOUNTED SPTMS SENSORS (TE-101 B, 0, F & H) FOR SRV-H HIGH REACTOR PRESSURE BLOWDOWN FIGURE 3A-443

a0 VI SENSOR a e) TE-IOI A

~

,.,a

+

TE-IOI C TE-IOI E a

~ )( TE-IOI G

-VI N

BULK POOL TEMPERATURE a0 0

LL~

0 W

00

~

VI W-0:::-

l a:o 0:::0 W"

Q.,.g Response z:- Time W

0

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0

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0 0

o o

UJ . . . . . .~------.------,------~-----,--_ _--~~~~r------r------~----~

~.OO 90.00 lBO.OO 270.00 360.00 450.00 540.00 630.00 720.00 elO.OO 900.00 TIME SEC LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF CONTAINMENT WALL MOUNTED SPTMS SENSORS (TE-101 A, C, E & G) FOR SRV-H HIGH REACTOR PRESSURE BLOWDOWN FIGURE 3A-444

a

~

In III SENSOR a e TE-101 B a

aIII 6 TE-101 0

+ TE-101 F a

~ )( TE-101 H BULK POOL TEMPERATURE a

a a

lL~

o w

Co o

In w-Q::-

)

t-a:O Q::O w*

Q..~

2:-

~ Response o Time 0 ......._ _........

In o

o o

o o

o o

~~~"~~----~----~~----~------r------r------~----~------T-----~

<7b .00 60.00 120.00 180.00 240.00 300.00 360.00 420.00 480.00 540.00 600.00 TIME SEC LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF COLUMN MOUNTED SPTMS SENSORS (TE-101 B, D, F & H) FOR SRV-L HIGH REACTOR PRESSURE BLOWDOWN FIGURE 3A-445

0 C?

In SENSOR a e) TE-IOI A

~

a .. TE-IOl C

+ TE-IOl E 0

a In x TE-lOl G N

... BULK POOL TEMPERATURE a

~

c lL~

0 W

ca W-II)~

0:::'"

J I-a:o 0:::0 W*

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0

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o o

II)~~~~------~----~------~----~~----~------~------------~----~

Olj.oo 60.00 120.00 lBO.OO 240.00 300.00 360.00 420.00 480.00 540.00 600.00 TIME SEC LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF CONTAINMENT WAl.L MOUNTED SPTMS SENSORS (TE-101 A, C, E & G) FOR SRV*L HIGH REACTOR PRESSURE SLOWDOWN FIGURE 3A-446

oo o SENSOR N

TE-lOl B o

~

a N

TE-lOl 0

+ TE-lOl F o

o x TE-lOl H 1ft a

N BULK POOL TEMPERATURE ao lL~

  • !:!Qll§.

oUJ

1. ENLARGED SCALE co 2. ELEVATED POOL TEMPERATURE o

REFLECTS RHR SYSTEM INOPERATION III UJo o:N

)

t-a:a 0:0 UJ*

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2:N UJ t-o o

Response

o N Time ao a

o N

o CJ CJ)

CJ)~~~~-------r------~----~-------r------r-----~------~------r------'

-0.00 18.00 36.00 5'.00 72.00 90.00 198.00 126.00 lH.OO 162.00 180.00 TIME SEC -10 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF COLUMN MOUNTED SPTMS SENSORS (TE-101 S, D, F & H) FOR SRV-H LOW REACTOR PRESSURE SLOWDOWN FIGURE 3A-447

o o

r-- SENSOR o

('I o

o TE-IOI A fa o

TE-IOI C N

+ TE-IOI E o

o x TE-IOI G II) e N BULK POOL TEMPERATURE o

o lL~

f:iQlli o

w lOr 1. ENLARGED SCALE co o 2. ELEVATED POOL TEMPERATURE

19) REFLECTS RHR SYSTEM INOPERATION we o:::N
l

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R~5ponse g Time e

N o

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o o

18.00 36.00 5'.00 72.00 90.00 1~8.00 126.00 lU.OO 162.00 180.00 TIME SEC *10 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF CONTAINMENT WALL MOUNTED SPTMS SENSORS (TE-101 A, C, E & G) FOR SRV-H LOW REACTOR PRESSURE BLOWDOWN FIGURE 3A-448

a o

II) o CI a

.c a

o II)

N OVERALL AVERAGE TEMP.

a o BULK POOL TEMPERATURE o

LL~

o W

Co o

II) w-0::-

=:J t-a:o 0::0 w'

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W t-o CI II) o o

o CI o

90.00 180.00 270.00 360.00 630.00 720.00 810.00 900.00 TIME LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT BULK TEMPERATURE VERSUS AVERAGE TEMPERATURE FROM SPTMS DIVISION 1 (TE 101A***TE-101H) FOR SRV-H HIGH REACTOR PRESSURE SLOWDOWN FIGURE 3A-449

0

~

a

~

ij 0

~

N 0

~

0 LL ...

0 lLJ 00 BULK POOL C? TEMP .

lLJ-

~- OVERALL

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CI:o

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W 0

C?

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0 0

C?

60.00 l20.00 l80.00 240.00 300.00 360.00 420.00 480.00 540.00 600.00 T[ME SEC LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT BULK TEMPERATURE VERSUS AVERAGE TEMPERATURE FROM SPTMS DIVISION 1 (TE 101A***TE-101H) FOR SRV-L HIGH REACTOR PRESSURE BLOWDOWN FIGURE 3A-450

o o

~

o N

o o

CD o

N o

o II) o N

~

1. ENLARGED SCALE o

o 2. ELEVATED POOL TEMPERATURE REFLECTS RHR SYSTEM INOPERATION LLg o

W BULK POOL TEMPERATURE Co o

(r)

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~

a:O SPTMS AVERAGE TEMPERATURE 0:::: 0 _OVERAll. AVERAGE TEMPERATURE W*

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o

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o o

N

Response

g Time o

o N

o o

IB.OO 36.00 5(.00 72.00 90.00 I~B.OO 126.00 IU.OO 162.00 IBO.OO TIME SEC -to LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT BULK TEMPERATURE VERSUS AVERAGE TEMPERATURE FROM SPTMS DIVISION 1 (TE 101A***TE-l01H) FOR SRV-H LOW REACTOR PRESSURE BLOWDOWN FIGURE 3A-451

SUPPRESSION POOL BULK TEMPERATURE LlMI,T )

(APPLYING VERIFIED LOCAL-TO-BULK ll.T:10';F; -

7 220 --'-~~"T'T"~-I- --.--- - r-r- . ..- - - -

- -- -. - - - - . l-' t/ 1300 210 "-4-+-4-+-1-i- ! - - --J.--t-.-!-i- - . - *

  • 1 - - - - - - -I- - f- - - - ,1/ 1200 205 200 ~

1100 190 "-

- -  ! - 1000 180 . --I--If- - - - 1- - - -f- 900 170 1---1-- 1- - -I"- -

u..

. - --1--+--+-+ - t-- - -f- 800

<{

(/)

0 a..

a.. 160

E w

- w 700 a:

J

~ (/)

(/)

-I 150 0 600 w a:

0 Q.

a.. ~

~ 140 . - w

-I I -I- 500 Ul

> (/)

W CD

- I-- - I -I- 400 >

- f-- - - 1- 300 200 100

._L--

10 4 2x104 Sx 104 0

TIME AFTER SCRAM - SECONDS NOTE: The information presented in this figure is based on the original design basis conditions. The LIMERICK GENERATING STATION current suppression pool temperature response UNITS 1 AND 2 results are discussed in Section 3A. 15.2. The results reasonably represent the general UPDATED FINAL SAFETY ANALYSIS REPORT characteristics of the suppression pool DESIGN ASSESSMENT REPORT temperature response.

SUPPRESSION POOL TEMPERATURE TRANSIENT CASE 1.8 FIGURE 3A-452 Rev. 5, 4/96

SUPPRESSION POOL BULK TEMPERATURE LIMIT /

(APPLYING VERIFIED LOCAL*TO*BULK 6T=10° F) /

J---+--+-+-+++-H--+-t-+--t--iH-H-iI+~-+--t-----*"I*--~ ~I: - .e-. -~-C -~1,.". J-+/-+__ ::~ I--4--4 205 ~

_ ~V 200 J.-4--+-+-+-t- 1..y.c::=:!~I-~--+-+~/~:t:-t-it--~1 ~-~I---+I--+-+-++~ I-~~I---+--+,/-i/&+.+-~

1100 i sc ~:;:~-=+-"""+~~++--'-+-+~-4~4-+4-t44r------+1'--..~~t-~~~t-4-4-4~ _~ ..

~!"

1000 180 ,--,,-t.-4-H-+Hf-I--+-...-II--iI- - f- *~"'-I--I-.~-'I-I---+--4--~--r-t- _ , 900

~ 170 ~-~~"'-'--+-+-+-~-+-+-+-+-I-f-~I+--+-+-+--t-t~\1 _. . .7~~~. - -*t-t--t-~ 800 ~

~~ 160 J-4-4-++-H-H---+-t--t--t-H-H-H---t-t-t-t-t-~ ~k 1--~~/-I---+--.-4~

V

- 700 ~~

8 150 t--~~~I-+H *!---+--+---+--+--I--+-t--f-+JI---+--+--+-+-+-H-* V -~. 600 ~

~

m 140 I----I--+-II-I-I-t- ~~--4--+-I-II-I-i-~I---4-+--~-t--+~~J~ K,,~~~~~~

-. -~-t-I I -.... '-- 500 ~

130 ~--~ - -I-H-+--t--t--t--t--t-I- V:..r .. f - -

---+-+-1--11/'- - f\~I--t- I'

- ~--+--+---t--+-1 400 120 +---+--+-*I-+--H-i~--i-'--t--t-1*- -

VV \

r--V-"J'-~""'- - \ -- 300 I--~I-I- _~

~f--

11 0 J--+--+-~H1f4-::==+=-I----HH'-H-H1~-t--t--t--t--t-t+t-H--t-t-t-M '\ +---~-+--+--+-i 200 100 ~~~++++~~~-+-+-~+rH--+-+-r-~~H+r-~~-1-t-trt-NI'* 100 ooL-~LJ~iU--~L-~~~~~L-L-~~~Lll__~L-~~_~~~__~~~~ 0 2 4 10 20 40 100 200 400 4 104 2xl04 5xl0 TIME AFTER SCRAM* SECONDS NOTE: The information presented in this figure is LIMERICK GENERATING STATION UNITS 1 AND 2 based on the original design basis conditions. The UPDATED FINAL SAFETY ANALYSIS REPORT current suppression poof temperature response results are discussed in Section 3A.1S.2. The DESIGN ASSESSMENT REPORT results reasonably represent the general SUPPRESSION POOL characteristics of the suppression pool temperature response.

TEMPERATURE TRANSIENT CASE 1.b FIGURE 3A-453 Rev. 5, 4/96

SUPPRESSION POOL BULK TEMPERATURE LIMIT (APPLYING VERIFIED LOCAL*TO*BULK ~T=10o F) 220 . -, - 1300 210 t--t--t--H~I+t-t-*t--+--+-4-I~~-I-+---f*--f.- -~- - r .. ~ -- - - V 1200 205 f- ~

200 ~-I-r-I

~~

-f- ~. ...- 1100

...---+-....,1,...00-, ~

190 "- IJ II - 1000 180 t---+--+--+-1I-f-l- - --I--t--~-I--f-+-I-.f-H--I--+--_I --t--t- _ ..

-~- - - - .V ~

900 r\. --

I u.. 170 t---I---I-I- - -

0, t---I--f--+~---I-~-.J.-It--~-~-t--t--f-f- - - I-- - -- ~ .. - ~ - I - t- U) 800 c...

~

E 160 w w

t-I--+--+--t--I-t-I- -t--t--I---+-+......f-+++-l I--t-t--+--+--H - - - .

V 700 a:

=>

Iv U)

..J U) 0 w

'\ ---

0

~

150 t---t--t--I~I-t-H' . - 1-

- 600 a:

c...

~ ..J

..J

> 140 t--..... -~--I-f- - f--!---- - / W V-

~,

U) cc 500 U) w 130 )

~-I- - -- --~*.--4--f-I- f- .. I - - + - - + - - ' I - t - ~-+-i -

  • l7 - 400 120 ~ -. 1- - -. *1- - t--+--+--I~'- -fo- _ .

V

/ ~.i\ _. - - f- 300

,....~

~

110 J--4-+--+--f-+-4-+-H t---+--+-~---*"""~H- - . -~ 200

~V

~I- 1\

100 .f--- ~ I-~-b-+-+-+-f"-l --"'-f-i-+-+-H-4--+---I-- ~ - -

100 90 ---- a 2 4 10 20 40 100 200 400 TIME AFTER SCRAM* SECONDS NOTE: The information presented in this figure is based on the original design basis conditions. The LIMERICK GENERATING STATION current suppression pool temperature response UNITS 1 AND 2 results are discussed in Section 3A.1S.2. The UPDATED FINAL SAFETY ANALYSIS REPORT results reasonably represent the general DESIGN ASSESSMENT REPORT characteristics of the suppression pool temperature response. SUPPRESSION POOL TEMPERATURE TRANSIENT CASE2.a FIGURE 3A-454 Rev. 5, 4/96

SUPPRESSION POOL BULK TEMPERATURE LlMIT )7 (APPLYING VERIFIED LOCAL-TO-BULK 6T=10 0 ' F/

220

---~--- --- -- -- - --- V 1300 210 J.-+-+-+-+"'++H--4-I-+-~~-~-H. >-- -~ -_.- - -. - ~-i-~--4-~-I_ _ _ I( / 1200 205 ~

200 ~

-  ; ~ - 1100

~

190

--- ~ V *-- -- - 1000 LL.

180 170 I -i -

--- ~ --I-I-1\

- - - ... -- ~

-. -I-900

<t:

(J) 800 a..

0. "\ '/

~

w a.

~

w 160 ~~- 1I I- f-- a::

700 (J)

~ ~ [7 (J)

..J w 0 / a::

0 a.

150

~~. ~"'"--+--~-+--4-4-I~-+4--4-4--+--+-+-~ ~ '"'\-\-+-/-v'~- 600 a..

..J

~ w (J)

..J 140 J-~-~4 "'++"++-~-I-4-4-J.-I-++~ 1--4-......J--~~-~1-f4 ~I--""f-I----f~-H- (J) 500 w

/f\~ >

CD 130 --~-4-~--i--f-l.....J..4 ~-4-4-~-+-I-+-H I..I"-~.J.~-+--+- - ...

400

~~~~~~v \~~~~~~_

120 ~-~-~..~-... H~-+--I--4-4-+-.J.+~H-+-+--f--i-Vl(~1 ~-LI-4-0---f~\-\ -- ..... .J 300 110

~~~~~~~--4--~~~~~~-u_~-+;? ~~~4_~~4-+-~~ ___ ~. __ I/ V f--~

200

___ V 1\

100 ~......J---t--~f~-f---"'-~--~~~~~~---+-+-~~+4-H"'I+---~~~-rH;~ 100

~-+--+-+-+-++++---~ ~I-90 0 2 4 10 20 40 100 200 400 5x10 4 TIME AFTER SCRAM - SECONDS NOTE: The information presented in this figure is based on the original design basis conditions. The current suppression pool temperature response LIMERICK GENERATING STATION UNITS 1 AND 2 results are discussed in Section 3A.15.2. The UPDATED FINAL SAFETY ANALYSIS REPORT results reasonably represent the general characteristics of the suppression pool DESIGN ASSESSMENT REPORT temperature response.

SUPPRESSION POOL TEMPERATURE TRANSIENT CASE2.b FIGURE 3A-455 Rev. 5, 4/96

220 210 t--~-4-~~+ __ _ __

SUPPRESSION POOL BULK TEMPERATURE LIMIT

~~ :=~~ IA~r:~ ~ll~I-ErOCAL-T~~B_U_L~_ L>T=10' :i 1300 1200 205 200 190

~

___ -'--"'rC-i.-L/~ r--~i---V 1'\,-;; - - J r\

\

l V

~"""'t-4-"-1

--t*-~I-1100 1000 180 I---J-~......j- - - - --t---t--I--I--f-f-. -I-t---i-+--I- - -f- - 'I--i~-~-- _ _ _ . II --I--~ 900

\ ~ <<

U- 170 t---I--I--t-f- - -I'- -I'_~~~_ - _I---+--+-~_II_L-L._ ~ II 800 ~

1_4-_~~'-I_It---+_I t--t--f-+-H-I+_+-~_~-4-I-_~r-...Jr-_U- --~V 0,

0...

__ _'--- \ - - - -I-I- w

~ a::

w

~

-I 0

0 0...

160 150 1

v-_-_ - 1-"-

700 (/)

600

(/)

w g:

/Ir~

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> 140 1---4--'+ - - - f - o - - - . 1--1--1--4---1,-1 --1---11- - ! - f - 500 ~

al

~-"--r-:-:-.."..,-:--~~I/ >

130 _1 ___ _

-f.- 1- - --11--+--+-- - - I----tJ,.r-/I-~ ._1\ .~ - - 400 120 f - - - ---~f--0-- f--+--+-- f-- - - -

~~

V- -~

\

-*---i- 300 110 t---+--+-~~-II-lt--I--~-"-~-~"-'-I- +--t--+---i*~,LI- .. t--t---1----I---I- '- _ 200 V

V. "

100 t---I--+-4-.'~ -f.- --+--bo-~++-1'"1~f--+~-+-~- -I-f- - - 1\ - + - - ! f - i_ 100 90 '--.... _-'--..1-J...L..1. ~~----"~--J_~..J_.L-L.1...l.J _.J_-'_--'-_L._L...L...J.JJ ......-'~_...J_: ~J I~r-_J_~.J..-' a 2 4 10 20 40 100 200 400 TIME AFTER SCRAM* SECONDS NOTE: The information presented in this figure is LIMERICK GENERATING STATION based on the original design basis conditions. The UNITS 1 AND 2 current suppression pool temperature response UPDATED FINAL SAFETY ANALYSIS REPORT results are discussed in Section 3A.1S.2 and DESIGN ASSESSMENT REPORT Table 3A-30. The results reasonably represent the general characteristics of the suppression SUPPRESSION POOL pool temperature response. TEMPERATURE TRANSIENT CASE 3.8 FIGURE 3A-456 Rev. 5, 4/96

SUPPRESSION POOL BULK TEMPERATURE LIMIT /

220 r---r--r--r-""r""~~~--r-rT'TTr- --r--I .. -

(APPLYING VERIFIED LOCAL*TO*BULK 6T=10o FI __

.. -1*- - -- -- y1 1300 210 - - - - - -. . -~ _ . _____ . 1-~,I---I_-+--I-1 1200 205 ~ I~

200 1-- - ~-I-p~1- -p~. . - -~-- -- --J[ . t - - - - - - 1100

~~ ,".,___ i--" ,'" \ IJ

""'--+--1L.,....or- ., _\ j 190

- ---1--- 1000 180 t--+-"""""-t- - *I-~--i-- r-- - -I- - - -- - -- - -. - -I~ - ---.- ~~- 1 - -r- 900

<t:

u. 170 I---t--I-I- _. - - ! - - -t--t---t-1--t- I_~_-+-_, __ ,- _..... _"--+--111 1 - ' " 1 - __ .~iI 800 ~

\

0, - - -of-t--

--1---+-_,, ___ . j ~

0..

~

UJ 160 1--t--t--t-1-t- - '~-+--I--I-t-1-t1-t-H 1--t--1--I-- ex:

~ 1----:- 700 :J V)

I--I-t--t-t-t-I-*t-i-+~-~ _H_~V . ---1--

...J V) g 150 0..

t---t--t--t- IH- -- -t-f- . - .

UJ 600 ~

~

S 140 CD I- -~ - - - - . - - - - '1- - t - I

  • t - - - - - t - - t - - t - - t - _ _ I__ '_~ _. ~ -1---

...J UJ V) 500 ~

130 - - - - . - .. -f- -f----t---~.-,~l1 1-\ 400 120 -f--I--- - .1 - - - r- f-- - -- ~ -+--+---1---i- f-.. / r- " ,\.;. . . ~_t-+-,-==~_~I __ 1_ 300

~~ V i\

110 ~-+--+-~H"H+-+-+--t---t--t--t-H- -~-+--+-__f---l""'-I V./

V~

. -, . ioo 100 '---I--+-*~t-'H-t-'--+-I.-t--iv-::::ot-r-r""'1 r--V ~t- _

- ~ I- r-- - - - - -

1\

"'--of-~ ---I---t---1 100 90 L-._ ~I ~'--'L---'"

"'~ a 2 4 10 20 40 100 200 400 2x10 3 4x10 3 TIME AFTE R SCRAM - SECONDS NOTE: The information presented In this figure is LIMERICK GENERATING STATION based on the original design basis conditions. The UNITS 1 AND 2 current suppression pool temperature response UPDATED FINAL SAFETY ANALYSIS REPORT results are discussed In Section 3A. 15.2. The DESIGN ASSESSMENT REPORT results reasonably represent the general characteristics of the suppression pool SUPPRESSION POOL temperature response. TEMPERATURE TRANSIENT CASE 3.b FIGURE 3A-457 Rev. 5, 4/96

8 TIlE ttSTORY PLOT OF' LOCAl.. TEMPERATURE i

I / n-

/~

I 6 T = 8.6( F

~ -~~ 1

,\<j V -L 8

2 _c~~ ~ , /'" '" ""

~~~

Y )<c. ~~

<v~~/ i-'

iii / ~

.(~~"""

, /

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TRACE FOR SRV-H BLOWDOWN UNDER HIGH REACTOR PRESSURE FIGURE 3A-458

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LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCATION OF CAPPED 180-DOWNCOMERS WITH VACUUM BREAKERS FIGURE 3A-461

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