Text

5 to Updated Final Safety Analysis Report, Chapter 14, Figures (Redacted)
	ML21125A334
Person / Time
Site:	Palisades
Issue date:	04/14/2021
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML21125A344	List: ML21125A285; ML21125A287; ML21125A288; ML21125A290; ML21125A291; ML21125A292; ML21125A293; ML21125A294; ML21125A295; ML21125A296; ML21125A297; ML21125A298; ML21125A299; ML21125A300; ML21125A301; ML21125A302; ML21125A303; ML21125A304; ML21125A305; ML21125A306; ML21125A307; ML21125A308; ML21125A309; ML21125A310; ML21125A311; ML21125A312; ML21125A313; ML21125A314; ML21125A315; ML21125A316; ML21125A317; ML21125A318; ML21125A319; ML21125A320; ML21125A321; ML21125A322; ML21125A323; ML21125A324; ML21125A325; ML21125A326; ML21125A327; ML21125A328; ML21125A329; ML21125A330; ML21125A331; ML21125A332; ML21125A334; ML21125A335; ML21125A336; ML21125A337; ... further results
References
	PNP 2021-008
	Download: ML21125A334 (151)
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.1-3 Revision 21 PALISADES SCRAM CURVE 1.0

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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.2.1-3 Revision 21 CONTROL ROD WITHDRAWAL INCIDENT HZP TOTAL REACTIVITY

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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.2.2-5 Revision 21 PRESSURIZER LIQUID LEVEL FOR UNCONTROLLED BANK WITHDRAWAL AT FULL POWER 14 13

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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.2.2-6 Revision 21 PCS MASS FLOW RATE FOR UNCONTROLLED BANK WITHDRAWAL AT FULL POWER 0

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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.10-1 Revision 25 POWER COMPARISONS - EXCESS LOAD 130 Actual Reactor Power Decalibrated NI Power Decalibrated Thermal Power 120 VHPT setpoint Power (% RTP) 110 100 90 0 5 10 15 20 25 30 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.10-2 Revision 25 PCS COOLANT TEMPERATURE - EXCESS LOAD 620 610 Thot Tcold 600 590 Temperature ( F) o 580 570 560 550 540 530 520 0 5 10 15 20 25 30 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.10-3 Revision 25 PRESSURIZER PRESSURE - EXCESS LOAD 2200 2100 Pressure (psia) 2000 1900 1800 0 5 10 15 20 25 30 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.10-4 Revision 25 PRESSURIZER COLLAPSED LIQUID LEVEL - EXCESS LOAD 70 60 Level (% Span) 50 40 30 20 0 5 10 15 20 25 30 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.10-5 Revision 25 COMPONENTS OF REACTIVITY - EXCESS LOAD 0.5 0.4 I Total I Doppler I 0.3 Moderator I Scram 0.2 /
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FSAR CHAPTER 14- SAFETY ANALYSIS FIGURE 14.11-1 Revision 23 PARTIAL OPERATING FLOOR PLAN EL 649'-0" Portions of this page have been redacted per 10 CFR 2.390(d)(l).
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.12-1 Revision 23 REACTOR POWER LEVEL FOR LOSS OF EXTERNAL LOAD EVENT
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-1 Revision 33 Reactor Power, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled 1(10 llO 110
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-2 Revision 33 Primary Coolant System Loop Temperatures, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-5 Revision 33 Pressurizer Spray Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-6 Revision 33 Pressurizer SRV Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled 15 - - - - -.....-....---.....- . . . - - -.....- . . . - - -.....- - - - - - . . . - - -.....- . . . - - -
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-8 Revision 33 SG Auxiliary Feedwater Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled 35 ----------------.-------------.--------.
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-9 Revision 33 SG Dome Pressure, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled 1000
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-14 Revision 33 Pressurizer Pressure, LNFF Analysis with Off-Site Power Available and Steam Dump System Available i
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-15 Revision 33 Pressurizer Spray Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Available I~-
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-16 Revision 33 Pressurizer SRV Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Available
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-17 Revision 33 Pressurizer Level, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 60 * ................................. .
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-18 Revision 33 SG Auxiliary Feedwater Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 30 *******--*..... ***i*** *** *** **** *** --* *r**--........ -- * - - - ~ * ** * ** * * * * * * * . . . * . . * * * * * * *** * . . * . . * -- *r* ...... *** ** --* .. **r*******-*--... *--**1* ** **** .......... *--i --***** ... --* --* --r *--*********--...
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-19 Revision 33 SG Dome Pressure, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 1000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-21 Revision 33 Reactor Power, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 120------------------------------
100 ********************************! *******************************1********************************+********************************+*********************************l********************************
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-22 Revision 33 Primary Coolant System Loop Temperatures, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 590 ------------------------------- -t Vessel ouuet
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-23 Revision 33 Primary Coolant System Loop Flow, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 9000 -""""'!!!!!!!!!!!!!!!!!!!!!f!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!""""'="'!!!!!!!!""""'"""""!!!!!!!!!!!!!!!!!!!""""'""""'!!!!!!!!!!!!!!!!!!!!f!!!!!!!!""""'!!!!!!!!!!!!!!!!!!!!!f!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!""""'="'!!!!!!!!""""'"""""-
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-24 Revision 33 Pressurizer Pressure, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-25 Revision 33 Pressurizer Level, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 70 1""""'!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!"""""""""'!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!"""""""""'!!!!!!!!!!!!!!!!!!!!!!!!!!!!~
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-26 Revision 33 SG Auxiliary Feedwater Flow, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled s -------------------------------
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-27 Revision 33 SG Dome Pressure, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 1100 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.13-28 Revision 33 SG Liquid Mass Inventory, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 1400.'lO """"'""""'""""!!!!!!!!"""""=-!!!!!!!!""""'""""'!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!J!!!!!!!!!!!""""'""""!!!!!!!!""""'=-!!!!!!!!!!!!!!!!=!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!I 1200'.lO * ******************** ******** I I I I I
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-1 Revision 24 Break Flow Rates During LHR-Limiting Transient 6000
---0 From Unaffected SG

1'::, From Affected SG 5000 Break Flow Rate (lbm/sec) 4000 I

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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-2 Revision 24 Steam Generator Pressures During LHR-Limiting Transient 1100
--0 Unaffected SG 1000 ----t::,. Affected SG 900 Steam Generator Pressure (psia) 800 700 600 500 400 300 200 100 0
0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-3 Revision 24 Steam Generator Heat Transfer Rates During LHR-Limiting Transient 2500
---0 Unaffected SG

6 Affected SG Steam Generator Heat Transfer Rate (MW) 2000 1500 1000 '\

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0 0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-4 Revision 24 Steam Generator Secondary-Side Total Fluid Inventories During LHR-Limiting Transient 250000
- - B Unaffected SG Steam Generator SecondarySide Total Fluid Inventory (lbm)

6 Affected SG 200000

-B----0--B----O--B---0--B---0--&---0--&---0--&
150000 100000 50000 0
0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-5 Revision 24 Core Inlet Temperatures During LHR-Limiting Transient 600
---0 Unaffected Sector

6 Affected Sector 550 500 Core Inlet Temperature ( F) o 450 400 350 300 250 0 50 100 150 200 250 300 350 Time (sec)

FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-6 Revision 24 Core Inlet Flow Rates During LHR-Limiting Transient 20000
/
/~~--O--~--&--o--B--~-~--&--o--~--&---0---
15000 Core Inlet Flow Rate (lbm/sec)
- - --0 Stuck Rod Region 10000 --------A Rest of Affected Sector
---0 Unaffected Sector
_ _ EJ- _ -B __ --- _ --D- _ - B-- - - G - - -B- - - El- - ----B - - -D---- - --D- - - B-- - - G
~G--B 5000 0
0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-7 Revision 24 Pressurizer Pressure During LHR-Limiting Transient 2200 2000 1800 Pressurizer Pressure (psia) 1600 1400 1200 1000 800 600 0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-8 Revision 24 Pressurizer Liquid Level During LHR-Limiting Transient 70 60 Pressurizer Liquid Level (% of span) 50 40 30 20 10 0
0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-9 Revision 24 Total HPSI Flow Rate During LHR-Limiting Transient 50 40 Total HPSI Flow Rate (lbm/sec) 30 20 10 0
0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-10 Revision 24 Reactivity During LHR-Limiting Transient 10
---0 Moderator
- - ---0 Doppler Boron

!> Scram

A Total 5

Reactivity ($)
0

E>----------E>----------E>----------E>----------E>----------E>----------E>----------l>----------l>----------l>-----------1>-----------!>-----------!>---------- -

5 10 0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-11 Revision 24 Reactor Power During LHR-Limiting Transient 30 25

0 Total Reactor Power (% of rated) 20 - - ---0 Stuck Rod Region

A Rest of Affected Sector

---0 Unaffected Sector 15
"' - - --B - - - - - G - - -B - - --G---
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/ 0 ~--
0 0 50 100 150 200 250 300 350 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-12 Revision 24 Break Flow Rates During DNBR-Limiting Transient 6000
---0 From Unaffected SG

6. From Affected SG 5000 Break Flow Rate (lbm/sec) 4000 3000 2000 1000 0

0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-13 Revision 24 Steam Generator Pressures During DNBR-Limiting Transient 1100
---0 Unaffected SG 1000 ----6 Affected SG 900 Steam Generator Pressure (psia) 800 700 600 500 400 300 200 100 0
0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-14 Revision 24 Steam Generator Heat Transfer Rates During DNBR-Limiting Transient 2500
---0 Unaffected SG

A Affected SG Steam Generator Heat Transfer Rate (MW) 2000 1500 1000

/1 I
500 I I
\
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\
(SJ 0
0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-15 Revision 24 Steam Generator Secondary-Side Total Fluid Inventories During DNBR-Limiting Transient 250000
--B Unaffected SG Steam Generator SecondarySide Total Fluid Inventory (lbm)

f:, Affected SG 200000

-B---O---B---0---&---0---&---0---&---0---&-~--&-~-
150000 100000 50000 0
0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-16 Revision 24 Core Inlet Temperatures During DNBR-Limiting Transient 600
---0 Unaffected Sector

6. Affected Sector 550 500 Core Inlet Temperature ( F) o 450 400 350 300 250 0 100 200 300 400 500 600 700 Time (sec)

FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-17 Revision 24 Core Inlet Flow Rates During DNBR-Limiting Transient 20000
- - ---0 Stuck Rod Region

A Rest of Affected Sector

---0 Unaffected Sector 15000 Core Inlet Flow Rate (lbm/sec)
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-18 Revision 24 Pressurizer Pressure During DNBR-Limiting Transient 2200 2000 1800 Pressurizer Pressure (psia) 1600 1400 1200 1000 800 600 0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-19 Revision 24 Pressurizer Liquid Level During DNBR-Limiting Transient 70 60 Pressurizer Liquid Level (% of span) 50 40 30 20 10 0
0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-20 Revision 24 Total HPSI Flow Rate During DNBR-Limiting Transient 50 40 Total HPSI Flow Rate (lbm/sec) 30 20 10 0
0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-21 Revision 24 Reactivity During DNBR-Limiting Transient 10
---0 Moderator
- - ---0 Doppler Boron

!> Scram

6 Total &--0--~

5 ----0-- - e- - - - ---- ---e
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5 10 0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.14-22 Revision 24 Reactor Power During DNBR-Limiting Transient 30

0 Total

- - ---0 Stuck Rod Region

A Rest of Affected Sector 25 ---0 Unaffected Sector Reactor Power (% of rated) 20 15 10 5

0 0 100 200 300 400 500 600 700 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-1 Revision 21 SGTR WITH LOAC: CORE POWER vs TIME l 2 0 - - - - ----.-,-----r----.,.,---.,.i-----,
(00 -
-I 80 ... -
~
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40 .,_
za- -
I I I 300 600 900 lZ00 1500 l800 TIME, SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-2 Revision 21 SGTR WITH LOAC: CORE COOLANT TEMPERATURE vs TIME 660r---"T-"----.-----.----,.----,,-...--
~
w 630
~
600 I
m...
.........,.. 570 i,..
y i 540 i
SLO 48Q..__ _--1,..._ _ _..___ __ , __ _ _..1..-_ _......r.._ ___,
300 600 900 l 200 1500 lBOO T{ME. SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-3 Revision 21 SGTR WITH LOAC: PRIMARY COOLANT SYSTEM PRESSURE vs TIME 2200r---~--~----,-------,-----,----,
3' 2000 i"'
! 1800
~
I...
1600
~
1400 l200 l 000 ..__ _..___ _......__ _~_ ___.__ ___.__ _---'
300 600 900 1200 1500 1800 TI NE. SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-4 Revision 21 SGTR WITH LOAC: STEAM GENERATOR PRESSURE vs TIME llSQr---...--------.------,,--------
10S0
--*i c ... 950 4'I
! 850 s...
!... 750 650 sso..___~30_0_ _ _6~0-0--~90-0--~12_0_~-~~~50_0_ __.1800 Tif'1E SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-5 Revision 21 SGTR WITH LOAC: TUBE LEAK FLOW RATE vs TIME 60.----,---.-----.-----.----:-----,
so
~ 40
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I 30 3
w 20 lO II I
3GO soo goo l .Zoo* LSOO i :00 TIME. SECON05-
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-6 Revision 21 SGTR WITH LOAC: INTEGRATED TUBE LEAK FLOW vs TIME 10000,----r---~~---,----.--~---
60000
-~~
50000
~
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-7 Revision 21 SGTR WITH LOAC: PRESSURIZER LIQUID VOLUME vs TIME 900.---~---,---------,.---.----
750 600
...-t:
- 450 I
Cl
-=--
I 300
"'.... lSO I t I 300 600 <300 l200 L500 lSOO T[ME. 5ECONOS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-8 Revision 21 SGTR WITH LOAC: AFFECTED STEAM GENERATOR SAFETY VALVE (MSSV)
FLOW RATE vs TIME 360 C.)
~
~
E 300
~
§
~ 240
~
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2 ix: 180 zi:tl 0
120 i
nn Q 60 I 300 600 900 Tff1E, 5ECOND5 l
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FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-9 Revision 21 SGTR WITH LOAC: AFFECTED STEAM GENERATOR SAFETY VALVE (MSSV)
INTEGRATED FLOW vs TIME soooo...---~---r------r-----r-------
i
.:. 50000
~
~
40000 30000 20000 lOOOO 300 soo I goo 1200 LSOO 1800 T(ME, 5Ea:ONOS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-10 Revision 21 SGTR WITH LOAC: STEAM GENERATORS LIQUID MASS vs TIME 360000 300000
... 240000 iQ AFFECTED SO
!_. l 80000 /
i!
I l20000 60000 "
UNAFFECTED SG 7
I II 300 600 900 l,00 l5CO 1800 T f ME, SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-11 Revision 21 SGTR WITH LOAC: CORE POWER vs TIME 120 r - - - - T1- - - - , , - - - ~1 - - , , - - - - ,1- - - - ,
I 8Qi- -
I so- -
I I 40 .. -
20 - -
I I I I I 5000 lOOOO 15000 20000 25000 30000 r I ME, SECONOS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-12 Revision 21 SGTR WITH LOAC: CORE COOLANT TEMPERATURES vs TIME 650r---.---.---,----r---,----,
ssa sao I.. 0 1M Q
. 4S0 I a:
~
en 1M CL.
400
c
"' 350
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-13 Revision 21 SGTR WITH LOAC: PRIMARY COOLANT SYSTEM PRESSURE vs TIME 2500r-----,---,------.-------r----.-----.
C 2000
-I¥:
"' 1500
=
VI I 1000 I
~ 500 I I 5000 10000 l 5000 20000 25000 30000 TIME. SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-14 Revision 21 SGTR WITH LOAC: STEAM GENERATORS PRESSURE vs TIME l40Or---r----ir------r-----.----.---
t200
-:s lOOO
-I!
I 800 AFFECTED SO II 600 /
400 200 /
UNAFFECTED SG 5000 10000 25000 30000
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-15 Revision 21 SGTR WITH LOAC: PRESSURIZER LIQUID VOLUME vs TIME 2000r---~--~----------,-----..---
11500 w
2 3
0 1000 Q
5 0
3 500 1¥ w
N c2 ell
~
1¥
~
-500---~~-----~~-~~-~~~~~~~
5000 lOOOO 15000 20000 25000 30000 TIME. SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-16 Revision 21 SGTR WITH LOAC: TUBE LEAK FLOW RATE vs TIME so--------------------
50 20 10 5000 LOOOO LSOOO 20000 25000 30000 T[f'1E. SECONDS
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-17 Revision 21 SGTR INTEGRATED LEAK FLOW vs TIME INTEGRATED LEAK FLOW 700 600
/'
! 500
/
~* /
...1,-..
u. ID 00
/
~
"' a
'2 V
~ !
0 .2 WI- 300
~/
~v
/
w /
i 200 V
V J
/
100
/
0 0 4 8 12 16 20 28 CThou*&nd*)
TIME, li4ilCOnd&
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-18 Revision 21 SGTR ADV FLOW RATE vs TIME ADV FLOW RATE 300 280 260 Affected SIG 240 220 u 200 QI II
~ 180
.Q 160 w'
I- 140
~
120
~
~ 100 BO lntac:t. SIG 60 40 20 0
a 4 8 12 16 20 24 28 (Thousands)
T1Me, s.econds
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-19 Revision 21 SGTR INTEGRATED ADV FLOW vs TIME INTEGRATED ADV FLOW 800 700 600 a
~-'f"I
..I~
o*
w:,
i 500 400 Intact SIG It, I-300
'z 200 100 A1'1'ected SIG 0
0 12 16 20 24 29 (Tnoueande)
TIME, seconds
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-20 Revision 21 SGTR PCS SUBCOOLING vs TIME RCS SUBCOOLING 100 90 A Ji'\
l.-
V V \V 80 V
I 70 ~
I u..
0 I
60 I
~ /~ v
,.3 ./
50 a 1\,._.,, /
V 8 40 I
Cil
i r./l
{\
30 I \
V 20 10 0
I 0 4 e 12 16 20 24 28 (Thousand s)
Tl~E. seconds.
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.15-21 Revision 21 SGTR HPSI FLOW RATE vs TIME HPSI FLOW RATE 60 I
I 50
\)
40 \
QI UI 30 w'
I-
~
3111 0
..J
u. 20 .i\
I 10 \ \Vn, r I\j
\ \I I
\ \
0 a 8 12 16 20 24 29 (Thou*anda)
TIME, s.aconds.
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.16-1 Revision 23 CONTROL ROD EJECTION, EOC HZP CASE: CORE POWER 60000 50000
~ *
... *~**
.* :30000 .*. . .**
~
I 0
&120000 .*
10000* .
0 *** ._........,,.;.i.,...;,;::,i..-.i.__,ii.,..;....ia,.....J..;;._,L..-,J;,i...-L-i.-.1,;,;...,.._-+-,--1...,.._.&-l--. . ....i--
o ', s 10: 15 20 Tfme(s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.16-2 Revision 23 CONTROL ROD EJECTION, EOC HZP CASE: CORE AVERAGE HEAT-FLUX-BASED LHR 8.
0---0 Core Ave. LHR 6.4
-=~
JI:
Ill:
3 4.8 Ill Cit e 3.2 l
I!
0 u
1.6
.0 0 5 10 15 20 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.16-3 Revision 23 CONTROL ROD EJECTION, EOC HZP CASE: TOTAL CORE REACTIVITY 2.
c 0 -_,c Total 1.
-e 0
-f*
0 0
a::
-1.
-2.
-3.
-4.
0 5 10-, 15 20 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-1 Revision 28 SCATTER PLOT OF OPERATIONAL PARAMETERS l -*-~-:- :*----* :*-J OneSided Break Area 2
(ft /side) 0.0 1.0 2.0 3.0 4.0 5.0 Burn Time (hours) ***************************
0.0 5000.0 10000.0 15000.0 Core Power (MW) l--*--~* . .***H 2565.0 2570.0 2575.0 2580.0 J
2585.0 LHGR (KW/ft) l *. -~----~-* j 12.0 13.0 14.0 15.0 16.0 ASI l :: ~ ~---:: : ::j 0.4 0.3 0.2 0.1 0.0 0.1 0.2 0.3 0.4 l -~-- ---: -* ~..-,
Pressurizer Pressure (psia) 2000.0 2020.0 2040.0 2060.0 2080.0 2100.0 l --*- --~--- j Pressurizer Liquid Level
(%)
40.0 50.0 60.0 70.0 RCS (Tcold)
Temperature o
( F) l :- :--*----:-**--1 536.0 538.0 540.0 542.0 544.0 l-*--*- -*:-- --**-*-J Total Loop Flow (Mlb/hr) 130.0 135.0 140.0 145.0 l : .---* : *~ *- j SIT Liquid Volume 3
(ft )
1000.0 1050.0 1100.0 1150.0 1200.0 l :-------*: --,
SIT Pressure (psia) 210.0 220.0 230.0 240.0 l : *~---* . -~:- ,
Containment Volume 3
(ft )
SIT Temperature o
( F) r-----.... -~. *-**J 1.60e+06 80.0 1.65e+06 100.0 1.70e+06 1.75e+06 120.0 1.80e+06 140.0
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-2 Revision 28 PCT VERSUS PCT TIME SCATTER PLOT FROM TRANSIENT CALCULATIONS PCT vs Time of PCT 1800 1§1
~
l 1600 1400 0
-i='
LL 1200
[2J
(.)
D..
~
1000 I
800
Split Break Guillotine Break 600 400 ~~-~-~-~-~-~-~~-~-~
0 100 200 300 400 500 Time of PCT (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-3 Revision 28 PCT VERSUS BREAK SIZE SCATTER PLOT FROM TRANSIENT CALCULATIONS PCT vs One-sided Break Area 1800 Cb 8
1600 1:J fa
§ c§J
~ Do 1400 w
0 LL
- 1200
(.)
a..
1000 I
800 1111 600 Split Break Guillotine Break 400 ~~-~-~-~-~-~-~~-~-~
0.0 1.0 2.0 3.0 4.0 5.0 Break Area (ft2/side)
FSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.17.1-4 Revision 28 Page 1 of 1
SUMMARY
OF MAJOR PARAMETERS FOR THE LIMITING PCT CASE 6.0 % Gad Rod Core Average Burnup (EFPH) 7,381.22 Core Power (MWt) 2,572.79 Hot Rod LHR, kW/ft 14.60 Total Hot Rod Radial Peak (FrT) 2.040 Axial Shape Index (ASI) 0.1602 Break Type Guillotine Break Size (ft2/side) 3.339 Offsite Power Availability Not Available Decay Heat Multiplier 1.01073
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-5 Revision 28 MAXIMUM OXIDATION VERSUS PCT SCATTER PLOT FROM TRANSIENT CALCULATIONS Maximum Oxidation vs PCT Split Break 0.9 Guillotine Break 0.8 0.7 0.6 C:
8cu 0.5
'O
~
0.4 0.3 0.2
~-
0.1 0.0 ::-=--~:-::--=------"--l-!lllllllllll:--~~-=-1=-:-~-:--:1-=-~----:--:=1-=-=-~::1=--=-~~
400 600 800 1000 1200 1400 1600 1800 2000 PCT (°F)
FSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.17.1-6 Revision 28 Page 1 of 1 CALCULATED EVENT TIMES FOR THE LIMITING PCT CASE Event Time (sec)
Break Opened
- - - - - - - - - - - - - + - - - I PCP Trip 0 SIAS Issued 0.6 Start of Broken Loop SIT Injection 14.9 Start of Intact Loop SIT Injection (loops 1B, 2A and 2B, respectively) 17.1, 17.1 and 17.1 Beginning of Core Recovery (Beginning of Reflood) 27.2 PCT Occurred 27.2 Start of HPSI 40.6 LPSI Available 40.6 Broken Loop LPSI Delivery Began 40.6 Intact Loop LPSI Delivery Began (loops 1B, 2A and 2B, respectively) 40.6, 40.6 and 40.6 Broken Loop HPSI Delivery Began 40.6 Intact Loop HPSI Delivery Began (loops 1B, 2A and 2B, respectively) 40.6, 40.6, 40.6 Broken Loop SIT Emptied 50.7 Intact Loop SIT Emptied (loops 1B, 2A and 2B, respectively) 50.8, 54.6 and 53.1 Transient Calculation Terminated 300
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-7 Revision 28 BREAK FLOW FOR THE LIMITING CASE Break Flow
- - Vessel Side
- - - - Pump Side
- - - Total 60 0
-g
~
E 40 I
I
-Q) cu 0:::
I I
I
~ I u::: 20 0
-20 ~ - - ~ - - ~ - - ~ - - ~ - - ~ - - ~
0 100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-8 Revision 28 CORE INLET MASS FLUX FOR THE LIMITING CASE Core Inlet Mass Flux
-- Hot Assembly

Surround Assembly

- - - Average Core
- -- Outer Core 500 NE u,
I E
.0 u:::
u, u,
(U 0
-500 ~ - - ~ - - ~ - - ~ - - ~ - - - ~ - ~
0 100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-9 Revision 28 CORE OUTLET MASS FLUX FOR THE LIMITING CASE Core Outlet Mass Flux
-- Hot Assembly

Surround Assembl)

- - - Average Core
- -- Outer Core 500 0
II : t II 1 ,l\\1 ,"/
1 Iii ,,
II II
-500 II II I
-1000 ~ - - ~ - - ~ - - - - - ~ - - - ~ - -
0 100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-10 Revision 28 VOID FRACTION AT PCS PUMPS FOR THE LIMITING CASE Pump Void Fraction 0.8 0.6 C:
0 u
I!!
LL
't:I
~
0.4 Broken Loop 1 Intact Loop 2 Intact Loop 3 0.2 Intact Loop 4 0.0 ~ - - ~ - - - ~ - - - ~ - - - ~ - - - ~ - - ~
0 100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-11 Revision 28 ECCS FLOW (INCLUDES SIT, HPSI, AND LPSI) FOR THE LIMITING CASE ECCS Flows 3000
-- Loop 1 (broken)

Loop 2

--- Loop 3
--- Loop4 I
ii
,1 I I I
I
\ \
l I 2000 ~ \ \
\ \;, .
-.!!?
E
.c
\' 'I
\\
\'~
JJ
-Q) cu a:
,I I
'I
~ !1 U:: I
'I 11 1000 ~ '
11
'I
!1 11
,1 11 i
,1 I\
'1 I_
lf I\,_,r-,._
0 0
100
~
200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-12 Revision 28 UPPER PLENUM PRESSURE FOR THE LIMITING CASE Upper Plenum Pressure 2000 ~
cu "iii E::
~
i a..
1000 0
0 100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-13 Revision 28 COLLAPSED LIQUID LEVEL IN THE DOWNCOMER FOR THE LIMITING CASE Downcomer Liquid Level
- - Sector 1 {broken}
Sector 2
- - - - Sector 3
- - - Sector4
- - Average 20 g
Q)
(I)
...J
2 I
i C"
i I,,
I I 10 i'i Ii

:
II I
i
I o~~-~--~---~--~---~--~
0 100 200 300 Time (s}
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-14 Revision 28 COLLAPSED LIQUID LEVEL IN THE LOWER PLENUM FOR THE LIMITING CASE Lower Vessel Liquid Level 8
6
-~
j Q)
....I 4 r o~--~--~--~--~-~~-~
0 100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-15 Revision 28 COLLAPSED LIQUID LEVEL IN THE CORE FOR THE LIMITING CASE Core Liquid Level
-- Hot Assembly

Center Core

- - - Average Core
- -- Outer Core 10 g
Q)
(I)
...J
2 O"
i 5
100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-16 Revision 28 CONTAINMENT AND LOOP PRESSURES FOR THE LIMITING CASE Containment and Loop Pressures 100
- - Containment 90 - - - - SG Outlet (primary side)
Upper Plenum
- - - Downcomer Inlet 80 70
-cu "iii
.8, 60
~ 50 U)
U)
~
a.
40 30 20 10 0
0 100 200 300 Time (s)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-17 Revision 28 CORE EFFECTIVE FLOODING RATE DELETED in Revision 28
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-18 Revision 28 CORE COLLAPSED LIQUID LEVEL DELETED in Revision 28
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-19 Revision 28 CORE QUENCH LEVEL DELETED in Revision 28
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-20 Revision 28 PCT-NODE HEAT TRANSFER COEFFICIENT DELETED in Revision 28
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.1-21 Revision 28 PEAK CLADDING AND RUPTURE LOCATION CLADDING TEMPERATURE FOR THE LIMITING CASE DELETED in Revision 28
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-1 Revision 28 Break Mass Flow Rate (Limiting Case)
ID:08968 240ct2007 20:59 0.08 ft2 Break
00 pal_M5_0.08ft2_DMX 1000 I=
.c 500 0 ..._.....___.__...._.............___....._..............___.~..,__.......___._..._.......___._..._.......___._...._......____._...._.......__.___.
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-2 Revision 28 Primary and Secondary Pressures (Limiting Case)
ID:06968 240ct2007 20:59:00 pal_M5_0.06fl2_DMX 0.08 ft2 Break 2400 2200

e Pressurizer 2000 ****-**** SG-1

--- SG-2 1800 1600 i
.e, 1400
~ 1200
I
~
a. 1000 800 600 400 200 0
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-3 Revision 28 Normalized Reactor Power (Limiting Case)
ID:08968 240ct2007 20:59:00 pal_M5_0.08ft2_DMX 0.08 ft2 Break 120 110 100 90 80
§'
6 70 I
0..
60 I!! 50 0
(.)
40 30 20 10 0
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-4 Revision 28 Total HPSI Mass Flow Rate (Limiting Case)
ID:08968 24Oct2007 20:59:00 pal_M5_0.08ft2_DMX 0.08 ft2 Break 80 uQ)
.!!! 60 E
..0
=
~
0:::
~ 40 Li:
20 0 .___._......._..._....___.__...._...._......_...._...___.____....._..............___._......_.......___._...__.____._..._.......___.___,
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-5 Revision 28 Total SIT Mass Flow Rate (Limiting Case)
ID:08968 240ct2007 20:59:00 pal_M5_0.08fl2_DMX 0.08 ft2 Break 4000 u
~ 3000 E
..c I
0::
~ 2000 u:::
1000 0 ~~~-~~~-~~~-~-~~~--~--~-I!_ _~ - - - ~ - ~
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-6 Revision 28 Loop Seal Void Fractions (Limiting Case)
ID:08968 24Oct2007 20:59:00 pal_M5_0.08ft2_DMX 0.08 ft2 Break 1.00 -
~
~
-~
0.90

e Loop 1A

- ****-* Loop 1B 0.80 --- Loop 2A
- -.& Loop 28 (broken) I 0.70 I c: 0.60 I 0
~
it I
"C
o 0.50 I
> 0.40 I 0.30 I
I 0.20 I
0.10 I I
0.00 0
~- 500 1000 1500 I~ I 0
I
- u -*
I '"
2000
--2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-7 Revision 28 Break Void Fraction (Limiting Case)
ID:08968 240ct2007 20:59:00 pal_M5_0.08fl2_DMX 0.08 ft2 Break 0.80 0.70 c 0.60 0
u~
IL 0.50 "O
~ 0.40 0.30 0.20 0.10 0.00 .___._....._.....,_.__......___.__.__......____.__.___.____.____..___._____.___._ _.___,._..__.,,___.____._ _.____.____.___.
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-8 Revision 28 Reactor Vessel and PCS Mass Inventories (Limiting Case)
ID:08968 24Oct2007 20:59:00 pal_M5_0.08ft2_DMX 0.08 ft2 Break 300000 .--""T"""r-T"----,-..---.----.----,.--...-----.----.--.--"T""""""T""----r-..--""T"""---.-----,-..---.----,----,.--...-----.----,

ePCS 250000 *-****-*RV 200000 E

g, 0 150000 0
cu
i!
i 100000 !
I I
50000 0 ...._.............._..._.............._...._.............._...._..._.......__....._..............__._....._.......__._....._.......__._..._.......__.__,
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-9 Revision 28 Hot Channel Collapsed Level (Limiting Case)
ID:08968 240ct2007 20:59:00 pal_M5_0.08fl2_DMX 0.08 ft2 Break 12 10 g
j Q)
....I 8 "C
5 tT
i "C
Q)
II) 6 Q.
0
(.)
4 2
o~~~-~~~~~~~~-~~~-~~~-~~~-~~~-~~~~
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-10 Revision 28 Fluid and Cladding Temperatures (Limiting Case)
ID:08968 24Oct2007 20:59:00 pal_M5_0.08ft2_DMX 0.08 ft2 Break 1600 1400 iU:::- 1200
~
8.
E 1000
~
800 600 400._................_._................_.._................_.._...._.......___..._................._._......._........___._..._....,____._..._........__._,
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-11 Revision 28 SG Narrow Range Liquid Levels (Limiting Case)
ID:08968 240ct2007 20:59:00 pal_M5_0.08fl2_DMX 0.08 ft2 Break 100 .----.-----.--.----r-.----r----,--..-"""T""--,--.----,--,----.-----.--.----r----,.----r----,--..-"""T""----.--.---,

eSG-1

-**** SG-2 80
i 60
~
1Q)
....I "Cl
5 tT
i 40 20 0 .___.____._....___.__.__....,____._..___.____._....___.__.___.____._....___._~.__....,____._..___._____._....____,
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-12 Revision 28 AFW Flow Rates (Limiting Case)
ID:08968 240ct2007 20:59:00 pal_M5_0.08ft2_DMX 0.08 ft2 Break 50 .---r----.--.---r----.-----,.---r----.-----,~-.----.---,--.---.-----.--.---.---,-..-........_,.-..-........---,.--,
40

SG-1

SG-2 30 20 u(I) 10
~
.c 0
i a:
~ -10 u::
-20
-30
-40
-50 ~~~-~~~~~~~~~~~~-~~~-~~~-~~~-~~~~
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.17.2-13 Revision 28 Total MSSV Flow (Limiting Case)
ID:08968 240ct2007 20:59:00 pal_M5_0.08fl2_DMX 0.08 ft2 Break

eSG-1

SG-2 600 200 o..._.___.~.........----...___.___..._______.____.____._______._..___.___.___.___.__.........,
0 500 1000 1500 2000 2500 Time (sec)
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.18.1-1 Revision 29 LOCA CONTAINMENT PRESSURE PROFILE 60 50 40 Pressure (psig) 30 20 10 0
1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 1.E+07 Time (sec)
D/G 1-1 Failure D/G 1-2 Failure
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.18.1-2 Revision 29 LOCA CONTAINMENT TEMPERATURE PROFILE 300 I - . . . ..
280 --......*
260 11 ~-
//1/
\
240 '
220
/// \ ' __ *-**---- ,_*-**-*,
/ '-
Temperature (oF)
V \/'
v.
I I " ,.\*
~
/
200 180
/:__/ \r ~r- \
160
[/
\ 1\--,- *.
~\,\'
\
140 "' ~
'\
' \'~
\ I-**-- * -
120 100 1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05
'\
1.E+06 1.E+07 Time (sec)
D/G 1-1 Failure D/G 1-2 Failure EEQ Profile
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.18.2-1 Revision 29 MSLB CONTAINMENT RESPONSE MAXIMUM PRESSURE PROFILE PR1 i i i i i i
-*-*-*-*-*+*- *-**-*-*-*-~ ,-- - * .. *--~ -- ------*-*-**}----*-*-*-*- *
-*-*-*-*-.L__ !
1*---*-*-*.l.! ____________
~------*-*-*j_-*
I
I I I i i i i i i i i
-*-*-*-*-*t*- *-** : . *-*-j--*-*-*-*-*-*---;*- *-* *-*-*- **t*-*-*-*-*-*- *
! . ! ! \ !
I I I I i i i i
__ _________ i_
_________ L ___________ _j__ __ __ _ ______ i ____________ _
[l_
i i i i
. i i i i i i I i i i
-*+*- *-**-*-*-*--i-*-*-*-*-*-*---i*-*-*-*-* *-**+*-*-*-*-*-*-
i i i i i i i i
! ! ! i
,o mo 18+004!- 1e+005 GOTI-IIC 7.2.a.(Cl\S. ~.Jarrf27/20tD. 1Ei:31!-:1l!I
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.18.2-2 Revision 31 MSLB CONTAINMENT RESPONSE ENVIRONMENTAL QUALIFICATION PROFILE 300
~
'?.....
2!
J
-; 250 Cl.
E Cl)
I-200 100 + - - - - - - - - - + - - - -- - - - - - -- - - - - - - - - ! ! - - - - - - - -- - - - - -- - -----<
1.E+OO 1.E 01 1.E +03 1.E+04 1. +{)5
- EEQLimit - - - 0% 1-1 EOG Failure 1Mi1:h LOOP * * * * * *0% 1-2 EOG Failure with LOOP
- * -
5P-7 (0%) - - - - - *5f'-7 (102%) - - - - SIS*B (0%),
* * * *
SIS-6 (102/I,}
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.22-1 Revision 25 PALISADES CONTAINMENT HYDROGEN ANALYSIS Deleted per FSAR-2479
FSAR CHAPTER 14 - SAFETY ANALYSIS FIGURE 14.22-2 Revision 25 CONTAINMENT TEMPERATURE FOR H2 GENERATION Deleted per FSAR-2479

ML21125A334

Text

SUMMARY

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