ML21133A065

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0 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3A, Figures 3A-320 Through 3A-462
ML21133A065
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 04/29/2021
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21138A803 List: ... further results
References
Download: ML21133A065 (152)


Text

PERIOD-SEC.

1:J 'J ~ G 0 'Jl l'I r -,--,--- ; - -r-----i- - ----------ri .,,-,--,-,--1----r I I I I ,-~---,-- I I I. 50 --- ---------- ~-------

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t-u w

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C./) 0.50 0 t 2 6 !3 I 0 2 6 !l 10 0 FREQUENCY-CPS Acceleration Spectra for REACTOR ENCL.

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

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

Node: 154 Direction: VERTICAL Elev: 177'-0 Damping: o.005,0.01,o.02,o.03,o.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-320

PERIOD-SEC.

iU'J ~r~ J: U'Jl i- ' -i - r-1-- r-- *1- - r - - i - - - - - ' 11 1-TI---,--,- - , - - - - - ,--r--j- 1 ~1--~-- I 1 I. SO - - - - - - - - - - - - - - --- ----------------------~-----, -----~

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a:

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CL V'l a.so 0.2S 1-----+---+-4--+---+---+--+-+-+-------+---+--4--+---+---+--+-+-+------+---+-4---+---+-+--f---+-I 0.00 L___2l__j__j_j_j_ll_Ll __~.l_~j__j_j_j~~Ll!!!!ll!!!!!!!!!!!!!!!!~I!!!!!!~~~~~~~~~~~

0. I 5 !3 I 0 2 ~ S !3 I0 0 2 ~ 6 !3 I 00 F"REOUENCY-CPS Acceleration Spectra for REACTOR ENCL.

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

Lo ad 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-321

1 PERIOD-SEC.

10 s 1 Q 0 Q~

l-,-r-,,--,-r--r--*- - - - - - - - , j , - - j - I -,--,-- I I 1 I 1 I , . r - l - , - - - - j

l. so ~ ------------ - - - - ---- ---* -------- ---------- ~--,---,.-~-.--,......,....,.....,.-------,.----,--~~-

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1.1.J

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(/) 0.50 0.25 0.00 5 !3 l 0 2 5 f3 I0 0 2 6 8 0 1 100 FREOUENCY-CP"i Acceleration Spectra for REACTOR ENCL.

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

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

Node: 130 Direction: VERTIC~L

~~~~~~~~~-

Elev: 201'-0 Damping: o.oos,o.01,o.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-322

PERIOD-SEC.

10 G 1 r, G 1 O IJl

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~~~~~~~~~~~~~~~~~~

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

Node: 106

~~~~~

Direction: VERTIC~

~~~~~~~~~

Elev: 217'-0 Damping: o.005,0.01,o.02,o.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-323

PERIOD-SEC.

10 r, l G '.J 1 O Q!

i-T~-r -i- ,--~--~-r. ---f ---~~~~-~I~r-~,-~,---~,~,~1~ 1 --,~,-1-~,-~,--~.I I. so - - - - - - ----- ----;--,--;--r.--,.-;----,...----:---.-~--:--r-:--r----~--r---~-~~

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Acceleration Spectra for REACTOR ENCL.

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

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

Node: 108 Elev: 217'-0

-- - - - Direction: VERTICAL Damping: o.oos,o.01,0.02,0.03,o.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-324

PE RI OD-SEC.

lGS ?Cl _, 0: 1 ITT~-,- I I - - - , - - - - , - . , - ,--,-,-,-----,~-,-----,~1~r-1---T--i-------,

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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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC f IGURE 3A- 325

PERIOD-SEC.

13  ! 0 c,:

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0. I 5 G I 0 2 fi G I0 0 2 FREQUENCY-CPS Acceleration Spectra for REACTOR ENCL.

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

Node: 81 Direction: VERTIC\L Elev: 253 '-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC f IGURE 3A*326

PERIOD-SEC.

10 ')

I I I I I. 50 -----~--~----11*----~-----..------------ ----~~-~

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__O_R_E_N_C_L_.______________~--~~~

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

Node: 19 Direction: VERTIC.\L Elev: 253'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-327

PERIOD-SEC.

10 G I G 0 O!

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

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

Node: 77

~~~~~

Direction: VERTICAL

~~~~~~~~~-

Elev: 269'-0 Dampin~: o.oos,0.01,0.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A- 328

PERIOD-SEC.

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~~~~~~~~~~~~~~~~~~~

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

Node: 58

~~~~~

Direction: VERTICAL

~~~~~~~~~~

Elev: 283'-0 Damping: o.005,o.01,o.02,o.03,o.05 LIMERICK GENERATING STATION UNITS 1AND2 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: o.oos,0.01,0.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-330

PERIOD-SEC.

10 'J I D 0 Q!

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~~~~~~~~~~~~~~~~~~

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

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

~~~~~~~~-

Dampin~: o.op5,o.01,o.02,o.03,o.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-331

PE RI OD-SEC.

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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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VE RT I CAL, CO - ADS AXISYMMETRIC FIGURE 3A-332

PERIOD-SEC.

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___CTO~-R~E_N_C_L_. ____________________~-

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

Norle: 43 Direction: VERTIC\L Elev: 313'-0 Damping: o.oos,o.01,o.02,0.03,o.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-333

PERIOD-SEC.

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

Node: ~~~~~

21 Direction: VERTICAL

~~~~~~~~~

Elev: 333'-0 Damping: o.oos,0.01,0.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-334

PERIOD-SEC.

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Acceleration Spectra for REAC'TOR ENCL. ~~~~~~~~~~~~~~~~~~

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

Node: 33 Direction: VERTICAL Elev: 333'-0 Dampin~: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*335

PERIOD-SEC.

10 G 1 Q S l 0 01 j-r-1--r--1--r-,--,----

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Acceleration Spectra for REACI'OR ENCL.

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

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

Node: 9 Direction: VERTIC\L

~~~~~~~~~

Elev: 352'-0 Damping: o.oos,o.01,o.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-336

PERIOD-SEC.

1Q S 1 G G 1 C G!

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

Node: 13 Direction: VERTIC~L

~~~~~~~~~-

Elev: 352'-0 Damping: 0.005,0.0l,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-337

PERIOD-SEC.

JQ *_, i r; 1

1-r* r--

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1


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0. I 2 6 G I 0 2 5 G 10. 0 2 i.j 6 !3 100

"'REOUENCY-CPS Acceleration Spectra for REACTOR ENCL. ~~~~~~~~~~~~~~~~~~-

Lo ad Case: AXISYMMETRIC GE CO-ADS ENVELOPE (WIDF.NED - 15%)

Node: 129

~~~~~

Direction: VERTICAL

~~~~~~~~~-

Elev: 201'-0 Damping: 0.005,0.01,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*338

PERIOD-SEC.

10 ,, 1 (~ 0 c. !

1 1 1~1~1 ~1~-~1---

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

Lo ad 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC f IGURE 3A-339

PERIOD-SEC.

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0. I 2 6 !3 I 0 2 6 !3 I 0. 0 2 6 8 100 FR[QUENCY-(P<;

Acceleration Spectra for REACTOR ENCL.

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

Load Case: AXISY'm-fETRIC GE CO-ADS ~NVELOPE" (WIDENED - 15%)

Node: 80 Direction: VERTICAL

~~~~~~~~~~

Elev: 253'-0 Dampin~: O.OOS,0.01,0.02,0.03,0.0S LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN.ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISVMMETRIC FIGURE 3A-340

PERIOD-SEC.

I. 25 L.J I

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z 0

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0. I 2 5 ~ I 0 2 5 G 10 0 2 6 O I 00 FRfOUENCY-[P',

Acceleration Spectra for REACTOR ENCL.

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

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

Node: 59 Direction: VERTICAL Elev: 283'-0

~~~~~~~~~~

Damping: o.005,0.01,o.02,o.03,o.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTORENCLOSUREGLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-341

PERIOD-SEC.

10 'J  : r..: ':J 1 G G!

1--T-jT_j_l--l---,---1-----,-,,-,-r-i-_,----1---,_---~ I 1 i--r---~----j I. SO - --- - ------- -- - - - --- -*------- -

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

Node: 54 Direction: VERTICAL Elev: 313 '-0 Damping: o.005,o.01,o.02,o.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-342

PERIOD-SEC.

I 0 IJ I r, c ':; ~

i'~-,-----, -,-----i-------rj--.-i - '1--r--,---,--- ---.-,---,

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0. I 2 5 !J I 0 2 5 !J I0 0 2 6 0 100 FREOUENCY-(P------ ~-- ~- ~- .. ----4--~---'--11-----+---+---+---+--+--t-+-+--t----l---+-+--+--+-t-+-+--I z

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0. I 2 5 [l ID 0 2 F R E: 0 UE NC Y [_ P <J Acceleration Spectra for REACTOR ENCL. ~~~~~~~~~~~~~~~~~~-

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

Node: 6

~~~~~

Direction: VERTICAL ~~~~~~~~~~

Elev: 410'~0 Damping: O.OOS,0.01,0.02,0.03,0.0S LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE GLOBAL RESPONSE SPECTRA, VERTICAL, CO-ADS AXISYMMETRIC FIGURE 3A-345

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~REOUENCY-CP!i Acceleration Spectra for CONTROL STRUCTURE


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

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

Node: 7 Direction: VERTICAL Elev: 217'


~

Damping: o.oos,0.01,0.02,0.03,0.os

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

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A*346

PERIOD-SEC.

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-r ;*-...-i--1--;-*-**1*---*r* ***--**1**i*-*i*--r--1-**i----*-r ------i.-.,-.---,- 1- . . - - 1
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AXISYMf.fETRIC GE CO-ADS ENVELOPE (WIDENED - 15%)

Node: 7 Direction: VERTICAL Elev: 239' Damping: O.OOS,O.Ol,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 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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~-

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

Node: 7 Direction: VERTIC.\L Elev: 254' Damping: 0.005,0.0l,0.02,0.03,0.05 LIMERICK GENERATING STATION UNITS 1AND2 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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~~~~~~~~~~~~~~~~~~~~~~~~

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

Node: ~~~~~

7 Direction: VERTIC~

~~~~~~~~~

Elev: 269'-0 Dampin~: o.oos,o.01,o.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-349

PER I OD** SEC.

10.0 I. 0 0.1 0.01 11 i i I I I I II I I I I I I ii I i i I I I I u

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FREOUENCY-CP5 Acceleration Spectra for CONTROL STRUCTURE

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

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

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

o.oos,0.01,0.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 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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~~~~~~~~~~~~~~~~~~~~~~~~

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

Node: 7

~~~~~

Direction: VERTICAL

~~~~~~~~~-

F.lev: 304'-0

-~~~~~~~~~-

Damping: o.oos,0.01,0.02,n.03,o.o~

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-351

PEIUOO-SEC.

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Node: 7 Direction: VERTIC~L Elev: 332' Dampin~: o.oos,o.01,o.02,0.03,0.os LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE LOCAL RESPONSE SPECTRA, VERTICAL, CO - ADS AXISYMMETRIC FIGURE 3A-352

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LIMERICK GENERATING STATION LOAD POINT NO. 1 UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING VELOCITY (SHEET 1 OF 4)

FIGURE 3A-353

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FIGURE 3A-353

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LIMERICK GENERATING STATION LOAD POINT NO. 3 UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING VELOCITY (SHEET 3 OF 4)

FIGURE 3A-353

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{SHEET 4 OF 4)

FIGURE 3A-353

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LIMERICK GENERATING STATION LOAD POINT NO. 2 UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCA AIR CLEARING ACCELERATION (SHEET 2 OF 4)

FIGURE 3A-354

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FIGURE 3A-354

A SEE FIGURE 3A-356 FOR SCHEMATIC OF SE CTI~ A-A 12° A

RADII FROM CENTERLINE OF CONTAINMENT I I I ARE: 12.81 15.01 35.8 1

0 - DOWNCOMERS e - SUBMERGED STRUCTURE LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TOP VIEW OF 36° SECTOR OF A TYPICAL MARK 11 SUPPRESSION POOL FIGURE 3A-355

DRYWELL FLOOR 21.e' Je' r 7.8 1

2 3

SUBMERGED STRUCTURE WITH LOAD POINTS I THROUGH 4 4

LIMERICK GENERATING STATION UNITS 1AND2 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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FIGURE 3A-357

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{SHEET 2 OF 4)

FIGURE 3A-357

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FIGURE 3A-357

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FIGURE 3A-357

u FLOW LIFT, L DRAG,D LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CYLINDER LOCATIONS FIGURE 3A-358

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT INTERFERENCE ON STANDARD DRAG:

THREE CYLINDER ARRANGEMENT FIGURE 3A-359

u FLOW LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT INTERFERENCE ON STANDARD DRAG:

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

y y

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FLOW LIMERICK GENERATING STATION UNITS 1ANO2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT FLOW AROUND UNEQUAL CYLINDERS FIGURE 3A-361

SECTIONS LOCATIONS

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TOP REBAR (INSIDE)

BOTTOM REBAR TRANSVERSE (OUTSIDE) SHEAR Tl ES(TYP)

LIMERICK GENERATING STATION

-0 SECTION WHERE STRESSES ARE ASSESSED UNITS 1AND2 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. 4 6 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:..iations 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 GENERA TING STATION UNITS 1AND2 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. 4 6 -0.07 -0.SS -0.04 -0.28 0.12 -0.432 3, 6 11. 4 6.26 11. 3 4. 2 lS.7 lS.l -0.200 4' 4a 9.97 43.0 14.8 19.S 17.4 11. 4 -0.218 4T, 4aT 3.4S 18.7 23.8 28.0 24.S 12.2 -0.926 s, Sa, 7, 7a 21.1 40.2 21. 3 17.4 36.9 20.1 -0.460 ST, SaT, 7T, 14.9 lS.9 34.S 27.4 S2.0 17.6 -1. 38 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 GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DRYWELL WALL FIGURE JA-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.SS -0.02 -0.69 0.06 -0.3S 0.lS -0.097 3, 6 13.0 6.44 13.0 4. 2 17.1 20.31 -0.230 4' 4a 8. 4 9 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 S, Sa, 7, 7a 26.3 39.3 28.7 17.S 39.7 24.9 -0.S22 ST, SaT, 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, ST, 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 JA-365 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 -0.3S 0.16 -0.106 3, 6 lS.S 10.3 14. 6 s.s 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.S -0.671 S, Sa, 7, 7a 43.6 33.2 32.8 9.S 37.6 S4.0 -0.931 ST, SaT, 7T, 30.4 9. 9 4S.S 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 GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DRYWELL WALL FIGURE JA-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.S 4. 8 20.6 O.S2 -0.361 4' 4a 31.1 39.6 26.8 9.2 18.6 43.7 -0.S82 4T, 4aT 26.0 48.7 26.7 8 .1 28.2 3S.O -0.718 S, Sa, 7, 7a SO.l 43.l 36.0 12.9 4S.7 4 4. 8 -1. 009 ST, SaT, 7T, 24.9 48.8 S3.9 2 6. 7 47.6 27.S -1. S92 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~<ltions are taken from Table 3A-14, 4T, 4aT, ST, 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES WETWELL WALL FIGURE JA-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 4 6. 2 34.6 33.0 33.8 14.0 -1.31 5, Sa, 7, 7a 37.7 37.0 47.9 21. 8 48.6 15.2 -0.819 ST, SaT, 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, ST, 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 GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES WETWELL WALL FIGURE JA-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 lS.8 -1. s 7.4 3.3S 1.1 -0.2S4 3, 6 27. s 30.7 2S.S 7.S8 31.1 0.70 -0.S03 4' 4a 16.6 42.4 29.1 3S.3 31. 4 S.3 -0.744 4T, 4aT 12.2 3S.6 38.0 39.7 37.9 8.13 -1.SO S, Sa, 7' 7a 37.S 40.1 43.6 27. s S0.1 6.7 -1.13 ST, SaT, 7T, 29.4 4 6. 7 S3.8 3S.6 S2.4 7. 4 -2.2S 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, ST, 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 GENERA TING STATION UNITS 1AND2 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 4 4. 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES WETWELL WALL FIGURE JA-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.S -0.26S 4T, 4 aT 2.0 8. 8 0.81 3.3 7.S -0.26S S, Sa, 7, 7a 8.S 12.8 2.7 S.1 9.S -0.407 ST, SaT, 7T, 8.3 12.4 2.S 4. 7 9.S -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, ST, 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 1AND2 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. 2 6 -0.128 5, Sa, 7, 7a 10.7 3.6 2.9 1.1 2.4 -0.444 5T, 5aT, 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, ST, 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES SHIELD WALL FIGURE JA-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 -0.1S7 3, 6 17.2 13.4 29.2 17.4 3.9 -0.3S2 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 S, Sa, 7, 7a 17.2 14.7 2S.6 17.2 3.3 -0. 4 32 ST, SaT, 7T, 2S.7 19.3 2S.O 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 1AND2 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, ST, 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 GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE 3A-37 4 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, 5a, 7, 7a 45.0 2 6 .1 42.7 36.8 19.6 -0.931 5T, 5aT, 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, ST, 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 GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE JA-375 Rev. 12 9/04

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.S 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 -0.63S S, Sa, 7' 7a 18.6 lS.7 20.S 29.8 22.S -1.017 ST, 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 St.::-ess; "-" 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 GENERA TING STATION UNITS 1AND2 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, ST, 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 GENERA TING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES RPV PEDESTAL FIGURE JA-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.S 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 3S.9 27.6 9.S -1.82 S, Sa, 7, 7a 3S.6 30.l 29.3 23.3 8.8 -0.36S ST, SaT, 7T, 31. 7 21. s 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 GENERA TING STATION UNITS 1AND2 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.S 10.2 13.0 4. 4 6 -0.370 4, 4a 14 .1 21. s 18.4 24.2 16.1 -0.383 4T, 4aT -11.1 12.3 26.2 29.8 7.0 -1.367 S, Sa, 7, 7 a 16.4 23.1 23.7 27.9 18.0 -0.623 ST, SaT, 7T, -13.1 16.0 2S.S 3S.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, ST, 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 GENERA TING STATION UNITS 1AND2 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 30.5 21.1 5.9 -0.842 4T, 4aT -8.61 -8.29 33.2 2 9. 4 4. 2 -1.59 5, 5a, 7, 7a 27. 9 25.4 33.4 24.4 6.2 -0.931 5T, 5aT, 7T, -10.3 12.3 35.5 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 Equations are taken from Table 3A-14, 4T, 4aT, ST, 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES DIAPHRAGM SLAB FIGURE JA-380 Rev. 12 9/04

DIAPHRAGM SLAB SECTION: 25 Max.

1 I I

_M_A_X_I_M_U_M__R_F._,B_A_R__S_T I Load Combination!--~-----~~--+-------.------,

INNER

__RE_S_S_E_S~,__

OUTER K_S_I~(~l_)~(~3_;_)~-+-Concrete

!Transverse Stress, Ties KS!

Equations (4) Radial Hoop Ranial Hoop (2)(3) 1 3, 6 I 13.0 I 15.5 I 12.1 14.5 I 0.66 -.157 I

4, 4a I 26.7 28.0 23.5 30.6 9.9 -.336

~: 1:::~ 1:::: I ~~~::

4T, 4aT 12.9 5, Sa, 7, 7a 5T , 5a T , 7 T ,

33.6

19. 3 31. R 41. 1 I 42* 4 1:::

9* 5 1 - 2*4 O l_____1_a_T________.______._____._~---~'--~-------__._------'

1 1 NOTES: (1) Allowable Reinforcing Steel Stress = 54 KS!

(2) Allowable Concrete Compressive Stress = 3.4 KS!

(3) "+" for Tensile Stress~ "-" for Compressive Stress

( 4) Load Combination Equations are taken from Table 3A-14, 4T, 4aT, ST, Sa~, 7T, 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, KS! (1)(3) Concrete INNER OUTER Transverse Stabs, Load Combination Ties KS!

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

3, 6 1.7 16. 6 S.93 6.22 S.29 -0.318 I

4, 4a 2.72 1.61 I 7.10 3.291 0.43 -0.213 4T, 4aT -S.21 -S.63 lS.2 14.9 3.4 -1.21 S, Sa, 7, 7a 10.9 20.7 10.4 9.Sl 4.03 I -0.443 ST, SaT, 7T, -6.361 -4.9S 18. 4 17.3 3.12 I -1.34 7aT I I I I I I I I I NOTES: (1) Allowable Reinforcing Steel Stress = S4 KS!

(2) Allowable Concrete Compressive Stress= 3.4 KS!

( 3) "+" for Tensile Stress; "-" for Compressive Stress

( 4) Load Combination Equations are taken from Table 3A-14 ,

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

LIMERICK GENERATING STATION UNITS 1AND2 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, KS! (1)(3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KS!

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

3, 6 2S.4 26.8 lS.S 6.43 24.7 -0.479 4, 4a 4T, 4aT 10.3 22.4

-0.431 11. l

-7.3 29. 8 I 0.65 13.3 23.9 33.l I

-0.309

-1.70 I

S, Sa, 7, 7a 39. 8 34.4 29. 3 13.9 41. 0 -0.540 ST, SaT, 7T, 30.0 20.2 29. 0 17.1 39.8 -1.79 7aT NOTES: (1) Allowable Reinforcing Steel Stress = S4 KS!

(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, ST, 5aT, 7T, 7aT include thermal components.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A*383

BASE SLAB SECTION: 28 Max.

MAXIMUM REBAR STRESSES, KS! (1)(3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KS!

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 I I I 5, Sa, 7, 7a ST, SaT, 7T, I 42.1 I 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 KS!

(3) "+" for Tensile Stress: "-" for Compressive Stress

( 4) Load Combination Equations are taken from Table 3A-14 ,

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

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A*384

BASE SLAB SECTION: 29 Max. I MAXIMUM REBAR STRESSES, KS! (1)(3) Concrete Load Combination INNER OUTER Transverse Stress, Ties KS!

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

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

4, 4a 11.8 I q. I) 1 17. 3 7.951 11. 0 I -0.243 4T, 4aT 9.32 -6.401 20.fi 12.6 12.0 -1. 23 S, Sa, 7, 7a 17. 7 18. 9 19. 0 13.3 18.S -0.508 ST, SaT, 7T, 14.4 -6.22* 21. 5 16.l 18.9 -1.18 7aT NOTES: (1) Allowable Reinforcing Steel Stress = S4 KS!

(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, ST, SaT, 7T, 7aT include thermal components.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A-385

BASE SLAB SECTION: 30 Max.

MAXIMUM REBAR STRESSES, KS! (1)(3) Concrete INNER OUTER Transverse Stress, Load Combination Ties KS!

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

3, 6 9.32 16.9 9.14 8.S4 7. () -0.414 4, 4a 29.9 33. E) 34.1 10.2 2S.6 -0.430 4T, 4aT 29.2 5.S 38.S 12.9 27.4 -0.902 s, Sa, 7, 7a 23.9 36.S 32.9 116.6 28. 4 -0.688 ST, Sa%, 7T, I 7aT 22.s 28. 9 -0.91S I

-6.36,36.5 119.6 I I NOTES: (1) Allowable Reinforcing Steel Stress = S4 KS!

(2) Allowable Concrete Compressive Stress = 3.4 KS!

(3) "+" for Tensile Stress; "-" for Compressive Stress

( 4) Load Combination Equations are taken from Table 3A-14 ,

4T, 4aT, ST, SaT, 7T, 7aT include Thermal Components.

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTAINMENT STRESSES BASE SLAB FIGURE 3A-386

I I

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

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT SUPPRESSION CHAMBER COLUMNS MODE SHAPES FIGURE 3A-387

SUPPRESSION CHAMBER COLUMNS MAXIMUM ALLOWABLE MAXIMUM jALLOWABLE COMBINED ICOLUMN AXIAL STRESS AXIAL STRESS FLEXURAL (KS!) (KS!)

!FLEXURAL STRESS STRESS (KS!) STRESS (KS!) RATIO STRESS MARGIN %

42" dia pipe (shell element) 11. 7 27.3 I 8.7 28. 0 0.74 26

!Top Anchorage 22.6 29. 9 - - I 0.76 24

!Bottom Anchorage I I I I 10 NOTE: These stress margins are based on load combination 7 of Table 3A-15 which is the critical load combination.

""i5c .,,c c

ll Oen !t  !:

m w

Oc r- .,,

c m

m c 5:

m l> c .,, en  !! JJ w

I

s:Zm
n C5 z n co z co l> ~c~

en en en en z C>

cen mo en l>-m m .,, en en

-4 z en ~ ... JJ m .

~z ~ <>>

e>o m J> z :::!

z z ::c -t zCz J> NC)

)>
:D

)> :s: .,,

nm 0 m ~

en (ii en

-4

-4 C> m  ::D JJ 0z

-:n z

-t m

0 JJ

-4

I j

I I

I I

I I

I I

.. -w-_J J k ~ k>. '<1;". I I

I Moc:>&'l t-r.o H2 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER MODE SHAPES, K = soktin FIGURE 3A-389

M~Pe 1 II.Cf H'Z LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER MODE SHAPES,

=

K 35ok11n f IGURE 3A-390

J--~-

1 k* 1~00. 'Y*"* I J

I LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER MODE SHAPES, K =1SOOOkJin FIGURE 3A-391

DOWNCOMER - STRESS

SUMMARY

AND DESIGN MARGINS I

I I

I LOAD COMBINATION CONDITION J

I ALLOWABLF, S'T1RESS (KS!)

I I

STRESS (KS!)

I DESIGN MARGIN

( %)

I I

I Equation l I Upset 28. 4 17.5 38.4 I Equation 2 Emerqency I 42.5 19.9 53.2 I I Equation Equation 3

4 Emergency Faul tea 42.5 56.7 II 37.4 20.0 12.0 64.7 I I Equation 5 Faulted 56.7 I 37.4 I 34.0 I I Equation 6 Faulted 56.7 37.5 I 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER DESIGN MARGIN FIGURE 3A-392

USAGE FACTOR

SUMMARY

OF DOWNCOMERS NORMAL/UPSET CONDITION EMERGENCY/FAULTED CONDITIONS SBA IBAORSBA DBA

!. OBE +  :!:. SRV 1 !. SRV 1 o PRESSURE o PRESSURE o PRESSURE

- SRV 1

.:.!:. SRV 1

!:. SRV 2 .:!: SRV 2 o THERMAL TRANSIENT o THERMAL TRANSIENT o THERMAL TRANSIENT la.I

~o LOADS +/-SRV 2

!. CHUG oSTEAM FLOW oSTEAM FLOW oSTEAM FLOW j~

.:.!:. CHUG .:.!:. CHUG

.:!: SRV 1

.+/-. CHUG u

~

.:.!:. SRV 1

.+/-. SSE

!:. SRV .:!: SRV 2 2

+/-. SSE AT PLATFORM RING 0.001 0.800 0.116 0.080 0.003 o.*

AT 24" x 24" 0.002 0.194 0.160 0.151 o.ocn 0.51 VACUUM BREAKER TEE

,. c:

'V AT PIPE ATTACHMENT ( 1 ) 0.001 0.545 0.078 0.071 0.003 0.70 i5 c ELEV. 221'-0" c:

~

cc !im

"'w

> c:

om

e C5 c

1 w

I co en z z ( ) ORIGINAL LOCATION OF VACUUM BREAKER (ABANDONED) w J:iiiO >

G'>O ~

mi: m

.,,m ~

):Iii :a a:

0.,, m

~):Iii~

o~ :u

a- m G') .,,

c: 0 m~

STRESS CYCLES FOR FATIGUE EVALUATION OF DOWNCOMERS LOAD TYPE No. OF CYCLES NsRvl 14100 NsRv2 7700 NOBE so NcHUG I 3000 NssE I 10 II NOBE = Cycles associated with QBE NSRVl = Cycles associated with SRV1 (Submerged Structure Load)

NSRV2 = Cycles associated with SRV 2 (Inertia)

NcHUG = Cycles associated with Chugging NssE = Cycles associated with SSE LIMERICK GENERATING STATION UNITS 1AND2 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 I

+ OBE II -

+ SRV11 + SRV1

- Pressure

-+ SRV11: Thermal I: Pressure Thermal 0

0 Pressure Thermal

+ SRV11 -+ SRV21 -+ SRV21 Transient Transient Transient I0 Steam Flow I 0 Steam Flow I 0 Steam Flow

-+ SRV21 -+ CHUGI -+ CHUG -+ CHUG -+ CHUG I I I I

-+ SRV1 -+ SRV1 -+ SSE I I I I I I +

II

-+ SRV2 SRV2 I I I I I -

SSE I

-+

I I

,. .,,c c:

sc

D m ~ r CJ m im w om IC c 50 3000 4650 6400 I Load s~t pair 9-10 is for one of the

)>

c:.,

U)

e ~
J:ZZ zJ>i
a n

cycles I

cycles! cycles\ cycles! three above events which produce the I I largest combined stress.

UI re~

-o>tn

"'o (I) z G')

.... !C ~ J>i -t m en m

- zm The cycles associated with oscillatory Om tn :a loads combined with SSE are assumed C) ::n

n .,,

Im -t

..A conservatively to be 10.

):Iii z :!

J> J> z zCz

!C .... ;: ):Iii N G')

-m C) ,,

(I) en

-t c: 0 c;; >

-t m~ :a 0

.,,m z 0

~

0 o~nco*cr

  • SR.v Line.

f r 10"* p;p~ or eauiv.

, I ICc,6 pipe or £ctUi'1.

\

rso

. LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER BRACING MATHEMATICAL MODEL FIGURE 13A-396

DOWNCOMER BRACING SYSTEM - STRESS

SUMMARY

BRACING MEMBER DESIGN MARGINS FOR CRITICAL MEMBERS 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) Equation number is hased on Table 3~15

( 2) Figure 3A-396 gives location reference LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT DOWNCOMER BRACING SYSTEM DESIGN MARGIN FIGURE 3A-397

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE & CONTROL STRUCTURE FLOOR PLAN AT ELEVATION 177 FT.

FIGURE 3A-398

14.I 20 2.3 7i'£ACTO"R "PLAN; 2.6~ 6" 9' 8.

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REACTOR ENCLOSURE

'?>'-~* .e!.o~ 1~~* 5~o* a! o" 4Lo" T~~* 10'-o" STEEL FRAMING PLAN

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  • o* z1'- o* 27'- o* '7~ o*

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@ FIGURE 3A-400

14. 1 14.* 15.5 17.6 18.5 19.4 21.s 23 11'-0" 19°-0* 1'!1'- ,..

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LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE ELEMENT 25 I* STEEL FRAMING PLAN EL. 313' FIGURE 3A-403

REACTOR

£ G

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D 1z.'-o' 15.5 18.5 20 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE STEEL FRAMING PLAN EL. 331' FIGURE 3A-404

~ ~ I 1 26 -6'

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,___ _ _L_4~'D-~~E._ Al.J~ L.E!!> 4* ~" 'z. (- ~~-'-_,_z~'z"-') _ U - ' - N - ' - 0 ' - - - - i - - - - - - - - - - - -

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--'~-'-~G=-'-'+----w I '-6

l---r-~-=--------+---t--- - - - - _-

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@---l~-~-*.....___ - - - ' f - - - - - - - - " - -

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~

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LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE STEEL FRAMING PLAN EL. 217' FIGURE 3A-407

~ ~~ ~3Cd' ~--li!j~l~--~--+20~~~~~~~-~~5~-;>~~~--~~~12~=~~0"~~~~-~~*-~~U.4.-S~~~-~~~~1~f--~--~~~~-+-~----~

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LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE STEEL FRAMING PLAN EL. 239' FIGURE 3A-408

r- - ~

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STRUCTURE N-S OVERTURNING MOMENTS (X106.K-FT)

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LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE & CONTROL STRUCTURE E-W OVERTURNING MOMENTS (X1a6K-FT)

DBE+LOCA+SRV (5% DAMPING)

FIGURE 3A-428

REACTOR ENCLOSURE FLOOR SLABS ELEMENT ELEVATION SLAA GOVERNING REBAR~ L. J STRESS NUMBER (FT) THICKNESS EQUATION(!) STRESS MARGIN (FT) (KS!) ( ¥; )

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. () 7a 27.70 48.7 5 253 1. 2S 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 EQN 1 = 1.40 + l.7L + 1.5 SRV Load Combination EON 7a = I.OD + 1. OL + 1. 0 ESS

+ 1.0 SRV + 1. 0 LOCA

( 2 ) Allowable Reinforcing Steel Stress = 54 KS!

LIMERICK GENERATING STATION UNITS 1AND2 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 BENDINGjSTRESS NUMBER (FT) STEEL SIZE EQUATION(2) STRESS MARGIN(3)

(KS!)  %

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 18 217 W33 x 141 1 21.90 8.6 19 217 W33 x 130 I 7 27.40 15.5 I 20 21 253 253 W24 W27 x 76 x 84 I 1 22.66 20.92 5.6 12.8 I 1 22 283 72" Girder 1 24.00 o.

23 283 W33 x lc;2 1 19. 27 19. 7 24 313 56" Girder 7 30.28 6.5 I

25 313 W36 x 300 7 29. 44 I C}.l 26 331 W36 x 182 I 7 23.58 I 27.2 27 331 1w21 x 73 7 20.31 37.3 28 352 IW36 x 300 I 7 18.54 I 42.7 29 352 IW24 x 68 I 7 16.94 47.7 I I I 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 KS! and 32.4 KS!,

respectively.

LIMERICK GENERATING STATION UNITS 1AND2 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 !Steel 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, Slee! 0.88 12 28 3 '-313' I 30.5 &E !Steel 0.78 22 I 313'-333' 27. 5 30.5

&E Steel I 0.97 I 3 313'-333' & E Steel 0.91 9 333'-352' 29 & 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 + E0 + LOCA + SRV + PB LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE MARGINS SUPPORTING COLUMNS FIGURE 3A-431

REACTOR ENCLOSURE SHEAR WALLS I I I !COMBINED AXIAL !SHEAR I I WALL I !GOVERNING I& BENDING STRESS STRESS ELEVATION' WALL MARK(l) EQUATION(2) MARGIN (%) (3) MARGIN (FT) ( % ) ( 4) 177 Line 14.1 7a 67 1 I

177 177 177 I Line 31. 9 D

Line 23 I 7a 7a 7a I

I 67 48 24 I 12 1

8 I I 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 KS!

(4) Allowable Reinforcing Steel Stress = 51 KS!

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT REACTOR ENCLOSURE MARGINS SHEAR WALLS FIGURE 3A-432

CONTROL STRUCTURE FLOOR SLABS I SLAB I REBAR STRESS!

ELEMENT,ELEVATION THICKNESS I GOVERNING STREss(2) MARGIN' NUMBER (FT) (FT) EQUATION(!) KS! ( %)

I I 30 200 1. 5 1 14.47 73.2 31 32 200 217 I 6.0

1. 25 1

1 I 37.64 14.15 30.3 73.8 I

33 237 I 1.0 1 I 31.10 I 42.4 I 34 237 1. 0 1 30.89 I 42.8 35 254 1.0 1 27.86 48.4 36 37 269 289

1. 5
1. 5 1

1 12.15 10.26 I 77.5 81.0 38 304 1.0 1 I 22.95 I 57.5 I 39 332 1.5 1 I 16.92 I 68.7 I 40 332 2.0 1 41.4 I 23.3 I 41 350 1. 5 1 I 16.65 I 69.2 I NOTES: (1 ) Taken from Tahle 3A-14 as follows:

Load Combination EON 1 = 1.40 + l.7L + 1.5 SRV (2 ) Allowable Reinforcing Steel Stress = 54 KS!

LIMERICK GENERATING STATION UNITS 1AND2 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) (KS!)  %

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. l 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 II Girder I 7 24.80 23.5 I 50 I 350 Wl8 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 EQN 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 KS! and 32.4 KS!, respectively.

LIMERICK GENERATING STATION UNITS 1AND2 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) MARGIN ( %)(3) (%)(4)

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

7a 1

I I

39 44 I

I 2

24 I

239 J I 1 48 19 177 Line 19.4 7a 23 I 0 239 177 Line 19.4 Line 26.6 I 1 7a I 3.4 28 I 24 0

I I

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

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

Load Combination EON 1 = l.4D + l.7L + 1.5 SRV Load Combination EON 7a = I.OD+ l.nL + 1.0 E55

+ 1.0 SRV + 1.0 LOCA (3) Allowable Reinforcing Steel Stress = 54 KS!

Allowable Concrete Compressive Stress = 2.8 KSI (4) Allowable Reinforcing Steel Stress = 51 KS!

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE MARGINS SHEAR WALLS FIGURE 3A-435

CONTROL STRUCTURE STEEL PLATFORM (1)

ELE:MENT ELE:VATION STEEL GOVERNING BENDING STRESS J MARGIN\))

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

I 51 313 Wl0x21 2 14.7 38.8 I

52 313 Wl2x27 2 18.9 21. 3 I I 53 322 Wl2x27 2 10.7 55.4 54 340 W8x24 2 10.0 58.3 I

I 55 350 W8x24 2 1 7. fi 26.7 I 56 350 Wl0x54 2 10. fi 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 EQN 2 = D + L + To + SRV LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT CONTROL STRUCTURE MARGINS STEEL PLATFORM FIGURE 3A-436

//~* ( ~

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UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT P~.:>.TFORM ~T :;'.~ 211'*0~ 1 PLATFO~~ AT EL. 223'-4' U.N.O.

,. =>.5.  !:_. 21~*-1ci'a' T.O.S. l!l..'Zt.!l'-'Z 1z' U.lol.0.

'N/1lz*...,!'1rQ' Gi"'~T1NG I'll/ J't' * ..._, GfU.T*NGr ~'!'I" DESIGN ASSESSMENT REPORT SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM SENSOR LOCATIONS FIGURE 3A-437

CONTAINMENT WALL

~ (DEGREES)

ACTUAL &

MODELED COLUMN

...5  ;:;

e a

a

..J U1 0

~

°'

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT PLAN VIEW OF MESH SYSTEM MODELING OF SUPPRESSION POOL FOR SRV-H HIGH AND LOW REACTOR PRESSURE SLOWDOWN (WITH SPTMS SENSOR LOCATIONS)

FIGURE 3A-438

VIEW A-A OF FIGURE 3A-438

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24.4'3i

( 1 ~) "V NI TI AL t>QOL W~ JER ~ EIGHT

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LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT SECTION VIEW OF MESH SYSTEM MODELING OF SUPPRESSION POOL FOR SRV-H HIGH REACTOR PRESSURE BLOWDOWN (WITH SPTMS SENSOR LOCATIONS)

FIGURE 3A-439

VIEW A-A OF FIGURE 3A*438 26.042 (ll )

23.347

( 10) v I NI TI~ L POOL WATEI HEIGH 20.653

( 9) 17.958 TE101 B TE103B TE101A TE103A CB J e TE101 D TE1030 TE1 01 C TE103C e TE101F TE103F TE101 E TE103E IS .264 TE101H TE103H - - TE101G TE103G

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FIGURE 3A-440

~ (DEGREES)

\.'ii'*

'. !(J fl::

IC;*!

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MODELED COLUMtf ~* a: ~--

0 ~ 0 0

LIMERICK GENERATING STATION UNITS 1AND2 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

~~. C*t:'

(1 ii

23. J.17 Cl~) \l I ~ITIAL Pl *OL WATH HEIGHT 20.'i'.;3 (9) 17.9~&

TE101B TE103B TE101A TE103A Co) e TE1010 TE1030 TE101C TE103C

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LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT SECTION VIEW OF MESH SYSTEM MODELING OF SUPPRESSION POOL FOR SRV-L HIGH REACTOR BLOWDOWN (WITH SPTMS SENSOR LOCATIONS)

FIGURE 3A-442

0

.,,C?

o SENSOR TE-101 B a

C?

0 A TE-101 D

+ TE-101 F 0

x 0 TE-101 H N

BULK POOL TEMPERATURE 0

0 0

LL~

C!>

LU co C?

LU-a::- "'

J

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C?

0 0

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0 0

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

°b.oo 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 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF COLUMN MOUNTED SPTMS SENSORS (TE-101 B, D, F & H) FOR SRV-H HIGH REACTOR PRESSURE BLOWDOWN FIGURE 3A-443

a

.,,,.,~

- SENSOR 0 e> TE-101 A C?

..,a

+

TE-101 C TE-101 E a

~ x TE-101 G N

BULK POOL TEMPERATURE a

~

a LL~

c!>

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.,,~

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a:o a:::o UJ.

Q..~ Response z:- Time UJ CJ

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c CJ CJ c

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°b.oo 90.00 tao.oo 210.00 350.00 450.00 540.00 s30.oo 120.00 e10.oo 900.00 TIME SEC LIMERICK GENERATING STATION UNITS 1AND2 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.... SENSOR a TE-101 8 a

a TE-101 D

+ TE-101 F a

TE-101 H

.,,~ )(

N BULK POOL TEMPERATURE a

~

0 lL~

0 UJ co

~

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~

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0

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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 1AND2 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 0

SENSOR 0 e> TE-101 A

~

0 A TE-101 c

+ TE-101 E 0

0 x TE-101 G N

BULK POOL TEMPERATURE 0

~

0 LL~

0 LU co LU-

.,,~

a::: ...

I-a:o a:::o LU.

o...~

r:-

w I-0

.,,~ Response Time 0

0

~

0 0

0

~

60.00 l20.00 LB0.00 240.00 300.00 360.00 420.00 480.00 540.00 600.00 TIME SEC LIMERICK GENERATING STATION UNITS 1AND2 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*L HIGH REACTOR PRESSURE SLOWDOWN FIGURE 3A-446

0 0

....a SENSOR N

TE-101 B 0

~

a N

TE-101 0

+ TE-101 F a

0 )( TE-101 H UI a

N BULK POOL TEMPERATURE a0 lL~

!:!Qll.§.

0 l&J 1. ENLARGED SCALE co 2. ELEVATED POOL TEMPERATURE 0

REFLECTS AHR SYSTEM INOPERATION l&JO Q::N a:a o:o l&J

  • Q..~
J::N l&J a

a

Response

a N Time a

0 C>

0 N

0 CJ CJ)

CJ)e-4~~;...._,~~~--~~~---~~---~~~--~~~---~~---..~~~--~~~~~~--.

...o.oo le.oo 36.oo s,.oo 12.00 90.00 l9e.oo 126.oo l*oo 162.00 leo.oo TIME SEC *10 LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT TEMPERATURE TIME HISTORIES OF COLUMN MOUNTED SPTMS SENSORS (TE-101 8, D, F & H) FOR SRV-H LOW REACTOR PRESSURE SLOWDOWN FIGURE 3A-447

0 0

0 SENSOR N

0 0

TE-101 A CD 0

TE-101 C N

+ TE-101 E 0

0 )( TE-101 G U>

0 N

BULK POOL TEMPERATURE 0

0 lL~

f:iQlli 0

l&.J 1°F 1. ENLARGED SCALE co 2. ELEVATED POOL TEMPERATURE 0

l&.JO

.,, REFLECTS RHR SYSTEM INOPERATION Q::N a:o a::::o UJ.

(L~

Z:::N UJ

...... Rt!sponse g Time 0

N 0

0 0

0 N

0 0

18.00 36.00 s*.oo 12.00 90.00 lq8.oo 126.00 1'4 .oo 162.00 180.00 TIME SEC *10 LIMERICK GENERATING STATION UNITS 1AND2 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

0 0

In 0

0 0

.t?

0 0

In N

OVERALL AVERAGE TEMP.

0 0 BULK POOL TEMPERATURE 0

lL~

0 w

co 0 U>

w-a:::-

=:J t-a:a a:::o w*

a..~

2=-

w 0

0 In 0

Response

g Time 0

0 90.00 ieo.oo 210.00 350.00

  • o.oo s*o.oo 630.00 120.00 eto.oo 900.00 TIME SEC LIMERICK GENERATING STATION UNITS 1AND2 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 BLOWDOWN FIGURE 3A-449

0 C?

N 0

CJ 0

LL_

c!>

w co 0

BULK POOL U>

TEMP.

w-a::::-

> OVERALL 1- AVG. TEMP.

a:o a::::o we;;

CL-J::_.

UJ CJ CJ II) 0

Response

CJ CJ Time 0

0 0

0

.,,._..IE:.Z~--.~~~~~~~---~~----..~~~-,......~~~r--~~---r~~~-..-~~---,.--~~-.

°b.oo 60.00 l20.00 l80.00 240.00 300.00 360.00 420.00 480.00 540.00 600.00 TlME SEC LIMERICK GENERATING STATION UNITS 1AND2 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 SLOWDOWN FIGURE 3A-450

0 0

~

0 N

0 0

co 0

N 0

0 ID 0

N NOTES 0 1. ENLARGED SCALE 0 2. ELEVATED POOL TEMPERATURE LLg

  • REFLECTS RHR SYSTEM INOPERATION C!>

UJ BULK POOL TEMPERATURE co 0

UJo "'

0::::N

~

~ SPTMS AVERAGE TEMPERATURE a:o o::::o UJ.

Q...~

%:N UJ I-

_ovERALI. AVERAGE TEMPERATURE 0

0 0

N

Response

g Time 0

0 N

0 0

m m+---..~~.--~~-,.~~~-,-~~~-r-~~~r-~~-,.~~~-r~~~--~~~..--~~_,

""'b.oo 18.00 36.oo s*.oo 12.00 90.00 1~8.00 126.00 1u.oo 162.00 1eo.oo TlME SEC *lO LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT BULK TEMPERATURE VERSUS AVERAGE TEMPERATURE FROM SPTMS DIVISION 1 (TE 101A.**TE-101H) FOR SRV-H LOW REACTOR PRESSURE BLOWDOWN FIGURE 3A-451

SUPPRESSION POOL BULK TEMPERATURE LIMl'Y (APPLYING VERIFIED LOCAL-TO-BULK 6T=10° Fl 220 --...--. --r--- **---- - -- . . . . - . T'" i/ 1300 210 - 1-- . -. - - -. -~ -- - - - _,_ v I>-

1200 205 JI 200

-*-... - - -~

- -*- - .. 1100 190 - -- ,_.....- i.-

i.-- ~

r-,...

r-.....,...

I - - . - - - 1-- 1000 180 -

  • - -*~ - - - *-- - - ,_ - -

-- 900 0

u..

Q..

170 160 1-- .

-- - -.- . \ -- -

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~ .....

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- -- 800

<{

(/)

Q..

w 700 a:

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t- " i\ 7  ::::>

(/)

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--- -. 1-

-- ,_ - I-*.

(/)

600 w

~~

a:

0Q..

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~ 14 0 - - I I/ ....J

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/ *- ,_ - ,_ ,_ 500 w

(/)

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ll ll

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1201--- .._ - _,_ . - .

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- -*- 300 10 1-.

- _,_ 200 00

  • ~

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r-r---_

100 90 2 4 10 10 3 2x 10 3 4x 103

._ *---i.- -- 0 20 40 100 200 400 10 4 2x 104 5x 104 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 1AND2 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.a FIGURE 3A-452 Rev. 5, 4/96

SUPPRESSION POOL BULK TEMPERATURE LIMIT (APPL YING VERIFIED LOCAL-TO-BULK 6T=10° Fl 7

1--*J-~~++4'-~~'--+-+-+-t-++*-H---+---+----_-,- ~- ~1:- - __- ---1~ --~,,._J+l-+--+--4-4 1300 1200 205 ~

200 J.-4-4--+-+-+- ~

1100 1000 180 -~i- - )

900

\ -- -*.'.. '----'---~7 i.c::..vi..-

<(

u.

0 170 ~-~~~ ... lf+J--+--+--+--+--t-t-H-t-t---+--+--+--1'""'" - ,_ - *. v; 800 a..

a..

~ w w

t-160 '---'--4-+4-H~+-+--+---t--t--HH-1H-t-+-+--~-t--~~~~ 1--~~/~/-*---+--*~~ 700 a:

(/)

  • "-~~---.._._..-HH~~-+---+--+-+-+-+-t- \i'r--.1-v-+---+--+-+- ..... *

...J (/)

0 w 0

a..

150 1--4--4--4*--+--4 a:

a..

l---t--4~1-t-t-t-i-~~--1~~.L.K 600

~ ...J

...J w

J 140 -- >-

500

(/)

(/)

al

,..,............._____.,.i(l,; I I'\....,___,---'__._...._.~ w 130 i.--

t-+ 1--+----4--+--+--t-it-t- --l---l~v~/---1"' ":'. ~" -- __.:\ 1- -_. _ 400 120

~~~~:~L.vl....o! *-+--+- \_~ _._,_ *--+--J-.--t-+-i 300

-"--I-- ,..,

110 "--+--1-+4..+444-C::::~l--+-+-*+-~~H+-+-+--t--t--HH-iH-1--t-t--t--r;- \ .. -

200 100 l-..-l--l--l-4-W..J+.-~~-4--+--HH-JH+-+-+--t--t--H~t-tt--t-t--r-~-;-r~N1'* 100 90 L__l_.LJLLUl.!__L_J__J__l--1.JLLJUL__J_.l.~1-LL...L..l.J..l.1~..1-..l---L.-L.LL-U.Jl.l._--1.--L-_.._...._.

~

.___ 0 2 4 10 20 40 100 200 400 TIME AFTER SCRAM *SECONDS NOTE: The Information presented In this figure is LIMERICK GENERATING STATION UNITS 1AND2 based on the original design basis conditions. The UPDATED FINAL SAFETY ANALYSIS REPORT current suppression poof temperature response results are discussed In Section 3A.15.2. 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 TEMPER A T u RE LIMIT (APPLYING VERIFIED LOCAL-TO-BULK ~T=10° Fl 220 *- . . -*~ -

v J

1300 210 205 -


JI i

1200 200 - - ,_ lo-,_ ~~ - -- -- i-i.-

~v

~ ...

"' /

..- '\ ,.....v \

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-- 1100 190 180 -- ,__

~

-~- - - - ~

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~ - 1000 900 u.

o, 0..

170

E 160 w

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r\. - -- 17

-- ~

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w a:

,,\/

t- 700 :::>

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w a:

0.. 600 c...

~

- I _J

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> 140 cc 130 j

v- \ 500 w

Cl)

Cl) w I I

- 400

~

120 ,.._ -* - . .....

~

v I ,__

'\ -* - - - 1-300 110 l/

- -. -~

v-- v 200 100 90


i.,.

L.--" ~

- i.- - _,_ ~ I'

~ r-- , _

100 0

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 1AND2 results are discussed In Section 3A.15.2. 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 CASE 2.a FIGURE 3A*454 Rev.5, 4/96

SUPPRESSION POOL BULK TEMPERATURE LIMITF)/

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

220

.... ------ - . *-* -- -- . -*--- / 1300 210

'---"--"-.f-+~-++---+-1-4.-~~-~~- - _.__ -- - - - .. ~~--4-~-l-4 --- ,_ y~-+-+---4-4--f / 1200 205 ...

200 1100 190 1000 180 900 J ct:

1+---4-~~-+--1-- -/ .1,.1--~~-~--+--1 CJ)

LL. 170 800 a..

o, /.,,,,.

a. w

~

w 160 '---"-~~-+-~~+-~-J---f-4-...++-+-~-+-+~+--+-+-~~~ 1/1-~ 700 a:

~

...J

~ [7 CJ)

CJ) w 0

0 150 .,__..__._-+-+-+-4 ~~-""-J---+-_._~~-H-~-+--+--+-l--H ~ 1\~ .._._/_ ..v*~,1~__.- ._.... . *-'--'---"-_._, 600 a:

a..

a. ...J

~

w CJ)

...J 140 ~~----~ -4*~1--4~~-1-~4-1--1--4-4-~ 1-...._-+--l----+--1---1-t -4 1-L.--'t*'--1----'~~ 1- CJ)

> 500 w m

130

/ ~~ 400

'--U---'--l~U~ ~ \ - - -

120 L.---1~1---14-1-~-'---'--*-~~l...+-+.l~J--+.I-+---_,_,_1/1/I I \\ - _ j . 300 I 1..,..,)/ ~~

110 -- - ~. 200

- v-7 i\

100 -- --L--~ _..,.... r'1I -L--+---1--.+-+-.

100 1-_._-'-.+--!.....~--l..-

"~~

90 0 2 4 10 20 40 100 200 400 103 2x103 4x103 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 1AND2 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-4.55 Rev.5, 4/96

220 1300 210 1200 205 ,_

200 1100 190

"--1*-~l- 1000 I

180 t--._~ ...... - - - . __ .,__._._.___j __ .._ '-. -*1-t--i-*--i- - -f- *.

900

--1--~

<(

u...

o, 170

---1-i.- 800 ~

0... w

~

160 a:

w *-~-.... - ' - 700 l/)

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w 0

0...

150 .----i-i-.. 600 g:

_J

~ w

_J l/)

> 140 al

- -f--- - - 500 ~

400 300 L...-...... \

110 t---+--+-1~1~*--t----"-~-~1-L.I. +--t--+-~*--"-.L./1-:: -* _ -t+--1--1----+--J- .._ . 200 v.J.-*..... I\

100 1----1-~-i-1 .... _.___ --+--..._..............,~~-----+~--&..-J- _....._.._. - "' 100 90 :====::~:::=------~-_.._. . -__.-..L-1..-L..I _ _

  • _ _.. _ __.__.._ .._~.JJ _.._~ _ _ __, * - ~ J r~~,,_=~=:~,_-. 0 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 1AND2 current suppression pool temperature response UPDATED FINAL SAFETY ANALYSIS REPORT results are discussed in Section 3A.15.2 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.a FIGURE 3A-456 Rev.s, 4/96

SUPPRESSION POOL BULK TEMPERATURE LIMIT 7

,v (APPLYING VERIFIED LOCAL-TO-BULK 6T=10° Fl 220

---*~......_~~~""T"Tr--..-- .. - **-4*- - -- -- 1300 210 - - - - - - . - - - - *- - - - - ~,~--+--+--t*-1 1200 205 ~ J 200 ,_ - 7 1-1,r--......._ _,_7r'\ ... - L;>~. ---~------~ .. ,._ _ _ _ _ 1100

~~ ,"... _.......... I--"..... ,,__-+--+----1-r--rt""M"'~\ '

,.._-+--r-~.,.. J 190 1000 180 t--+-+-t-t-,... **t---""i--1"----~1-- - - - - - - - - *. --~----

h ... ~ . .-r---

I >*

900

<t:

u.. 170

o. ----1 -* . -- -*--t---t-1 1- - -1--+--1-- - _,_ . -*1--+--tl\_,_..,_ - - / - - -~--- 800 ~

0..

w

~ 160 *--+-*t--t-t - *l---+-*l--t--+-1-t-"t-H 1--1--+--1- _,_,_ _ ___\_. ____ / i/ a:

1- ----*- 700 :J V>

  • ~--t--+--t-t--1-*T'"'I...,.. _,_._~V

...J V>

g 150 1---t--+--+- IH* _ _ _ _ _ - - ___ ..... - .

---*-- 600 w

g:

-tt-* \

0..

~ ...J w

3CD 140 - -~ - - - .. - - - - _,__,_ - t - l

  • t - - - t - , - - t - - - , --

-*--*--- V>

500 ~

130


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*-** -f---1-+-ti-t-H - \

400 120 __ ,___ .... * - - _,_ ______ 1--+--+--i.--.*--:~~

~/-1--+--t*-

v . . . "'".\.,__~_

\ t-+i-==t9-~ - 300 110 .,__.,._-+-~H-IH+--+-+--t---t*-t-""t-"H- -*t---t--t---~l.l"'~~,..~ -t~--1-ti---i--,-

ioo v./

./

100 t---*---.._t-*H*H--+-t*-t--i~-::::>'f-r-r'!"'~l 11

~ .... _,_ - r--- -~ - - - - ,,i - - t - - - - - t - - t - - .

11 100

~I' 90 ..__~,_....._........._._ ... - _J_-1--1-..J....L-L...A...LL.-..\-..\-__._~~-_......,- -*'---"--£...~'--**- ~-. -*- 0 2 4 10 20 40 100 200 400 103 2x103 4x103 104 2x104 5x10 4 TIME AFTER SCRAM* SECONDS NOTE: The information presented In this figure is LIMERICK GENERATING STATION based on the original design basis conditions. The UNITS 1AND2 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 TllE ttSTORY PLOT OF' LOCAL TEMPERATURE 8

/

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCAL-TO-BULK TEMPERATURE DIFFERENCE (AT)

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

8 TME HSTORY Pl.OT OF LOCAL TEMPERATURE 8

si

=

8 2

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8

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., .... n.m 1a. 1IO.GD l~k: ao.ao 00.0D

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t40.00 ....

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCAL*TO-BULK TEMPERATURE DIFFERENCE (6n TRACE FOR SRV*L BLOWDOWN UNDER 1H IGH REACTOR PRESSURE FIGURE 3A-459

TIME t1S10RY PLOT Of LOCAL TEMPERATURE NOTES

1. ENLARGED SCALE
2. ELEVATED POOL TEMPERATURE REFLECTS AHR SYSTEM INOPERATION LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCAL*TO-BULK TEMPERATURE DIFFERENCE (4n TRACE FOR SRV*HBLOWDOWN UNDER Low: REACTOR PRESSURE FIGURE 3A-460

\~

I NOTE:

VACUUM BREAKERS ARE INST ALL ED ON DOWNCOMERS 10, 31, 50 AND 77 WHICH ARE CAPPED (E.G.,)

LIMERICK GENERATING STATION UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN ASSESSMENT REPORT LOCATION OF CAPPED reo*

DOWNCOMERS WITH VACUUM BREAKERS FIGURE 3A-461

JET DE FL ECTOR ASSEMBLY

-~EL 237'-11"

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- u - * '. ~ I~ , "'" .. - t>

~---**---f'r-*--:* .... - *- EL234'-5"

' i .. ----.. . . . 24" O.D. x 3/8" c::::>-...--) WALL PIPE

~

_1_ __ ~ __ It_ VACUUM BREAKER

'. J r EL . 229'-0" EXIST'G ---

24"PIPE~..-.n-~'

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11.\,.,.,.

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p.~

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CW; 3"Q}PIPE ,....

SCH. 160 TYP. c;,

STD. CAPS SCH. 20 - - - - - - EL 193'-11" 1" 3000 THREADED

.- - HALF COUPLING WITH THREADED PLUG LIMERICK GENERATING STATION O______ ___...__EL 189'-11" UNITS 1AND2 UPDATED FINAL SAFETY ANALYSIS REPORT T. 0. BASEMAT DESIGN ASSESSMENT REPORT EL 181'-11" """'-._

..... _ -_-------------+-

~...,..,... DETAILS OF

,\~* '~- ,_');h~*:::;',: CAPPED DOWNCOMER FIGURE 3A-462