ML23110A191
Text
OPEN/CLOSE ANY VALVE
FUEL STOP/START BARRIER ANY COMPONENT
ELECTRICAL FAILURE
NUCLEAR SYSTEM MANIPULATE PROCESS ANY CONTROL BARRIER DEVICE
SINGLE OPERATOR ERROR
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
PLANT SAFETY ANALYSIS METHOD FOR IDENTIFYING AND EVALUATING ABNORMAL OPERATIONAL TRANSIENTS
FIGURE 14.4.1 CATEGORY RADIOACTIVE Of MATERIAL ACCIDENT RELEASE OF RELEASE ACCIDENT TVPE APPLICATION EVALUATION OF DAMAGE TO RADIOACTIVE MATERIAL BARRIERS RADIOACTIVE RADIOLOGICAL EFFECTS
ii c
t;;il------<~ BARRIER FUEL Unit 3
FIGURE 14.5.1AA
PEACH BOTTOM, UNIT 2
UFSAR Figure 14.5.1AA for Unit 2 is represented by Figure 3-6, "Peach Bottom Response to LRNBP," from GEH Document 0000-0100-9751-R0 Task Report T0900, Page 3-44, as provided in support of the Peach Bottom, Units 2 and 3, Extended Power Update License Amendment Request dated September 28, 2012, as approved by the NRC on August 25, 2014 (Amendment Nos. 293/296).
The information provided in the referenced figure is GEH Proprietary Information
FIGURE 14.5.1AA (Unit 2) Rev. 25 04/15 PBAPS UFSAR
FIGURE 14.5.1B
Deleted
UFSAR Figure 14.5.1B is presented by Figure 1, "Plant Response to MSIV Closure (Direct SCRAM) - ICF (HBB) - Nominal Inputs,"
from GEH Document 002N5709-R0), "Peach Bottom 3 Cycle 21 Spring Safety Valve Lift Margin Evaluation," April 15, 2015.
The information provided in the referenced figure is GEH Proprietary Information.
FIGURE 14.5.1BB
PEACH BOTTOM, UNIT 2
UFSAR Figure 14.5.1AA for Unit 2 is represented by Figure 3-7, "Peach Bottom Response to TTNBP," from GEH Document 0000-0100-9751-R0 Task Report T0900, Page 3-45, as provided in support of the Peach Bottom, Units 2 and 3, Extended Power Update License Amendment Request dated September 28, 2012, as approved by the NRC on August 25, 2014 (Amendment Nos. 293/296).
The information provided in the referenced figure is GEH Proprietary Information
FIGURE 14.5.1BB (Unit 2) Rev. 25 04/15 PBAPS UFSAR
Figure 14.5.2
Deleted
e ***
~ ****
~
i....
t.Qia.o I.I T11£ (SEC:JCS) *... TU£ (SECCNIS)
lur--....c;.-ili~~~--...-;,.,c.. =* __,:..__o...l
?::
i.... t---------t.~---+------_.
- .tiJ.o...
TIC (SEma) T 11£ (SEa>CIS)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
TRANSIENT RESULTS*
CLOSURE OF ALL MAIN STEAM ISOLATION VALVES
FIGURE 14.5.3 Rev. 28 04/21 PBAPS UFSAR
FIGURE 14.5.3A
PEACH BOTTOM, UNIT 2
DELETED
FIGURE 14.5.3A (Unit 2) Rev. 28 04/21 PBAPS UFSAR
FIGURE 14.5.3B
Deleted
FIGURE 14.5.4
Deleted
FIGURE 14.5.4A
Deleted
Rev. 26 04/17 Unit 3
FIGURE 14.5.5A
PEACH BOTTOM, UNIT 2
UFSAR Figure 14.5.5A for Unit 2 is represented by Figure 3-5, "Peach Bottom Response to FWCU," from GEH Document 0000-0100-9751-R0 Task Report T0900, Page 3-43, as provided in support of the Peach Bottom, Units 2 and 3, Extended Power Update License Amendment Request dated September 28, 2012, as approved by the NRC on August 25, 2014 (Amendment Nos. 293/296).
The information provided in the referenced figure is GEH Proprietary Information
FIGURE 14.5.5A (Unit 2) Rev. 25 04/15 PBAPS UFSAR
Figure 14.5.6
Figure 14.5.7A thru 14.5.7B
Deleted
... - SUlll.llCJ H ~ llUI n....... ""' **.,.
tf ~l~c.J
- u.
1~1-----***Y""SS-Sll-*I OW--:--**-----
lJ..-:;
§ I
- I~
- ~ -*~ --*---* ~--* h~****
......., /. *.6-*.. **.
g:
,~*! ~* Q... /
- Jail 1.1J..1.L1 &.1.1. *----- --~ *--*-..
- 0. 20. *O. '° IO.
=--- TIU( (SEC).......>*'*
,, rr HI UINUM II"*
lilll* ollC:L 1* Al I Ill no 1-----1---*--1-----**------
- ..., t 0
- ~ IO I I
~
... ~.
0
-1~ 0.
..,_..... 40. '° TIME (SEC)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
TRANSIENT RESULTS -
PRESSURE REGULATOR FAILURE - OPEN
FIGURE 14.5.8 REV. 13 01/95
FIGURE 14.5.10
PEACH BOTTOM, UNIT 2
UFSAR Figure 14.5.10 for Unit 2 is represented by Figure 1, "Peach Bottom LOFW - Water Level Inside the Shroud - Upper Plenum," from GEH document 003N4534 R0 (G-080-VC-463), dated May 25, 2016.
The information provided in the referenced figure is GEH Proprietary Information
FIGURE 14.5.10 (Unit 2) Rev. 28 04/21 PBAPS UFSAR
Figure 14.5.10 thru 14.5.11C Figures 14.5.11A
Deleted
Figures 14.5.12a through 14.5.13
Deleted
Rev. 26 04/17 UNIT 3 ONLY
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3
TRANSIENT RESULTS Single Recirculation Flow Controller Failure Increasing Flow FIGURE 14.5.14 REV. 26 04/17 PBAPS UFSAR
Figure 14.5.14 thru 14.5.19
Deleted MAXIMUM IN-SEQUENCE ANO OUT-OF-SEQUENCE CONTROL ROD WORTH AS A FUNCTION OF AVERAGE MODERATOR DENSITY
2.8 WORST ROD IN WORST POSSIBLE PATTERN"
2.4
2.0
WORST NON*-WITHDRAWABLE
....;.;R~O~O~IN~NORMALPATTERNS
1.2
0.8
WORST WITHDRAWABLE RODS ALLOWED FOR NORMAL PATTERNS
0.4
1.0 0.96 0.92 0.88 0.84 0.80 0.76 0.72
MODERATOR DENSITY (&m/cm 3)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT NOTE: Historical Information not accurate for current plant conditions MAXIMUM ROD WORTH VERSUS MODERATOR DENSITY
FIGURE 14. 6.1 REV. 13 01/95 0.06
0.05
~ 0.04
- c I-ct:
0 31:
0 0 0.03 ct:
..J 0
ct:
I-z 0 0.02 u
- IE
- l x
- IE 0.01
o::--~-:~~---::--~~-!:-~~...1...~~---1..~~-L~~-1..~~--1.~~-1.~~__J 0 10 20 30 40 50 60 70 100 80 90 PERCENT CORE POWER
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 NOTE: Historical Information UPDATED FINAL SAFETY ANALYSIS REPORT not accurate for current plant conditions CONTROL ROD WORTH AS A FUNCTION OF CORE POWER
FIGURE 14.6.2 REV. 13 01/95 350 t---------,r------------------~-------------------
300
250
'5 t.
..J c
i= 200
~
..J
=> CURVE NUMBER INITIAL POWER
"" 2
~
- .:: 1 10-8 x DESIGN
~ 2 10~ x DESIGN*
~
..J 150 3 3 10-3 x DESIGN
!: 4 Hrl x DESIGN 1.6-4
100
0 0.04
~K/CONTROL ROD
PECO ENERGY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 NOTE: Historical Information UPDATED FINAL SAFETY ANALYSIS REPORT not accurate for current plant conditions.
However, these results ROD DROP ACCIDENT {COLD, CRITICAL) continue to provide a reasonable representation PEAK FUEL ENTHALPY of the trends and characteristics.
FIGURE 14.6.3 REV. 14 05/97 350
300
250
Ii
~
~
a.. 200
....J
< ~
z M.I
....J M.I
~
~ 2 M.I lSO CURVE NUMBER INITIAL POWER a..
....J 3 1 10~ x DESIGN z 2 url x DESIGN Li.: 3 url l DESIGN
100
50
_____ _r_ INITIAL ENTHALPY
0 0.02 0.03 0.04
&K/CONTROL ROD
PECO ENERGY COMPANY PEACH BOTTOM ~TOMIC POWER STATION NOTE: Historical Informatton UNITS 2 AND 3 not accurate for current UPDATED FINAL SAFETY ANALYSIS REPORT plant conditions.
However, these results continue to provide a ROD DROP ACCIDENT (HOT, CRITICAL) of the trends and reasonable representation characteristics. PEAK FUEL ENTHALPY
FIGURE 14.6.4 REV. 14 05/97 220 210 200..............._-- c
- 2 190 ----;----
180....... FINAL MAXIMUM ENTHALPY 170 ' ' '
160 EXCURSION 150 ' INCREMENT 140 '
....... f. ' '\\
- u \\
130 \\ \\
>- CURVE a..
....J 120 No. INITIAL POWER
- z: 1 3% Of' DESIGN I- \\ \\
z: 110 2 3~ OF DESIGN i.J
....J i.J \\
~ 100 w.. \\
~
i.J 90 \\
a..
80 \\
\\
70 60 '
so /',
40 INITIAL MAXIMUM "
CENTERLINE ENTHALPY '
30 ',......
20
10
0 0.01 0.02 0.03 0.04 0
h k/CONTROL ROD
PECO ENERGY COMPANY PIACH BOTTOM ATOMIC POWER STATION NOTE: Historical Infonnation UNITS 2 AND 3 not accurate for current UPDATED FINAL SAFETY ANALYSIS REPORT plant conditions.
However, these results continue to provide a ROD DROP ACCIDENT (POWER RANGE) reasonable representation PEAK FUEL ENTHALPY of the trends and characteristics.
FIGURE 14.6.5 REV. 14 05/97 1200
.. 1000
.§:
I.I.I a:
- i V)
V)
""" 800 a: A9 = 0.0147
~
~
I.I.I V)
V)
I.I.I D TEST DATA
> 600 CALCULATED
50
- 40 x---- )<
Q. "'
&...I a:
~ Toi~ 184 F. CARRYOVER 95:.*
&...I JO To,* 70 f.. CARRYOVER 7P, a:
Q.. lo,** 64 F,CARRYOVER 10';
&...I -' To,. 103' F. CARRYOVER::: e:,c
- t:
0 20 a: - CALCULATED HOMOGENEOUS CARRYOVER
- - -CALCULATED ZEnO CARRYOVER 10 - * --CALCULATED ZERO CARRYOVER ANO CONDENSATION
o 0 2 3 ' 5 6 8 TIME fSECONOSI A9 =AREA OF THE BREAK To= INITIAL DRYWELL TEMPERATURE PECO ENERGY COMPANY
PIACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
LOCA - HUMBOLDT PRIMARY CONTAINMENT PRESSURE RESPONSE
PIGURI 14.6.6 REV. 14 05/97 1200 A9
- 0.0573 SQ. ft. 1200
To= 150 F
1000 1000 v;
w a: 0 a aoo VI 800 w
a:
a..
~
w VI VI
> 600 600 0 TEST CATA
~ CALCULATED
HOMOGENEOUSCARRYOVE~
60
so 0 50 CJ 0 ZERO CARRYOVER
< 40 40 v;
""' a:
VI =>
VI 30 w 30 cc a..
w 3:
a: 20 A9=AREA OF THE BREAK 20 c
To=DRYWELL TEMPERATURE
10 10
o.._ __________ -'-------------1....-----------L------------LO 0 2.0 4.0 6.0 *a.a
TIME (SECONDS)
PECO ENERGY COMPANY PIACH BOTTOM.ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
LOCA BODEGA BAY PRIMARY CONTAINMENT PRESSURE
RESPONSE
. FIGURE 14.6. 7 REV. 14 05/97
< As= o.om n2 H 1200 U) To= 65 F Po..
CiJ 0:: 1000 U)
U) l'.:J 0::
Po.. 800
~
l'.:J U)
Ul CJ TEST CATA
- > 600 l'.:J
- CALCULATED
HOMOGENEOUS CARRYOVER
so
< 0 "
H 40 Cl en Po. ZERO CARRYOVER Czl 0:: 30 Ul Ul
~
Po. 20 Ae =AREA OF THE BREAK
~
~ TO= ORYYIELL TEMPERA TU RE
~
)-4 0:: 10 Cl
0 0 2 6 8 10 12 14 16 TIME (SECONDS)
PECO ENERGY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
LOCA - BODEGA BAY PRIMARY CONTAINMENT PRESSURE
RESPONSE
. FIGURE 14.6.8 REV. 14 05/97 160 r-----r.--r--~~-~---------------------
f AT 184 11s1a
~H-ll HIMBOLOT BAY TEST CATA 1'0 BOOECA BAY TEST 1llTH DEFLECTOR, DATA
\\ FLAG 1 / 1 IHOICATES CALC:ULlTEO POINTS
\\
110
- t
\\
--- -- ---- -- ---* H-n
2U
~---------.__....... _ _._ __.._--' _ _.__....___. __....... _______ _.__...._ __
10.., JC ~ ~o 60 70 8G 90 100 ii4 !~ 1 '.I :*r. ISO lbG
" \\'!~T &RFA BRFA* &RfA P&T1J '*JAri
PECO ENERGY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 *AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
- LOCA COMPARISON OF CALCULATED AND MEASURED PEAK DRYWELL PRESSURE FOR BODEGA BAY AND HUMBOLDT TESTS
FIGURE 14.6.9 REV. 14 05/97 Unit 2 NOTE: For current plant conditions see Figures 14.10.1 14.10.3, and 14.10.5
Unit 3
Rev. 25 04/15
Unit 2 NOTE: For current plant conditions see Figures 14.10.2, 14.10.4, and 14.10.6.
Unit 3
Rev. 25 04/15
Unit 2 NOTE: For current plant conditions see Figures 14.10.8 and 14.10.8a.
Unit 3
Rev. 25 04/15 EXELON CORPORATION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
PEACH BOTTOM ATOMIC POWER STATION SHORT AND LONG TERM SUPPRESSION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT POOL TEMPERATURE RESPONSE -
LONG TERM SUPPRESSION NORMAL ECCS FLOW POOL TEMPERATURE RESPONSE -
Historical information for Unit 2 not accurate for NORMAL ECCS FLOW current plant conditions. FIGURE 14.6.12A REV. 25 04/15 FIGURE 14.6.12A REV. 24 03/03 Unit 3 0.5
c 0.4 a:
UJ n..
- UJ :E
- J..J
> 0 UJ 0.3 UJ a:
~
UJ 0
~ 0.2 UJ
..J
0.1
0 -................................... ____________________ _,_ _________.....1~---------L---------.....1.-----------J 10- 1 102 io' TIME (-.seconds)
PECO ENERCY COMPANY NOTE: Historical Information PEACH BOTTOM ATOMIC POWER STATION not accurate for current UNITS 2 AND 3 plant conditions. UPDATED FINAL SAFETY ANALYSIS REPORT However, these results continue to provide a reasonable representation of the trends and PRIMARY CONTAINMENT LEAK RATE cha~acteristics.
FIGURE 14.6. 13 REV. 14 05/97 70r------..,.-------r------.------,.-------,-------,r-------r-------.,------...-------
50
z 0
~ 40
(.)
UJ a::
z UJ
(.) 30 a::
UJ G..
20
10
o------::-':-------:'--------J------..J------L-------L------L------'------L----_J o~ OA o~ 0.8 1.0 1.2 1.4 1.6 1.8 2.0 DURATION OF RELEASE (hours)
NOTE: not accurate for current Historical Infonnat1on PECO ENERCY COMPANY plant conditions. PEACH BOTTOM ATOMIC POWER STATION However, these results U~ITS 2 AND 3 continue to provide a UPDATED FINAL SAFETY ANALYSIS REPORT reasonable representation of the trends and characteristics. PRIMARY CONTAINMENT CAPABILITY INDEX FOR METAL-WATER REACTION
FIGURE 14.6.14 REV. 14 05/97 PRIMARY CONTAINMENT BYPASS HEADER FLOW/JP\\ STOP VALVES I ;NTROLVALVES
'"--"""~""'i
TURBINE
GENERATOR
- u FLaf \\ -, o/
RESTRICTORS ~ _J/' TURBINE ISOLATION VALVES BYPASS SYSTEM
CONO.
REACTOR TURBINE DRIVEN FEED PUMPS (3)
PECO ENERGY COMPANY PEACH BOTTOM ATOMIC POWER STATION
. UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
MAIN STEAM LINE BREAK ACCIDENT - BREAK LOCATION
FIGURE 14.6.15 REV. 14 05/97 30
,.., - LIQUID I 2
u
~
'l::
w 20 a::
CD (j MIXTU~E LEVEL 0 INSIDE VESSEL a:: REACHES STEAM
~ LINES
- i:
0
...J L'-
~
- E
.,_ 10 z STEAM ONLY STEAM
...J 0
0 u
TIME (seconds)
PECO ENERCY COMPANY NOTE: Historical Information PEACH BOTTOM ATOMIC POWER STATION not accurate for current UNITS 2 AND 3 plant conditions. UPDATED FINAL SAFETY ANALYSIS REPORT However, these results continue to provide a MAIN STEAM LINE BREAK reasonable representation of the trends and ACCIDENT MASS OF characteristics. COOLANT THROUGH BREAK
FIGURE 14.6.16 REV. 14 05/97
'.J
- 10 SECOND ISOLATION 0.9 - PUMPS TRIPPED AT T=O
!I: - REACTOR SCRAMMED AT T=O 0
..J
~
~ 0.6 a::
0 u
0 I.I.I
~
..J 0.4
- e a::
0 z
0.2
o""-____ _... ______.._ ____ __. ______________.._ ____ __.. _______________,__ ____ _._ ____ __,
0 2 3 5 6 7 a 9 10
TIME (SEC)
PECO EHERCY COMPANY NOTE: Htstortcal Infonnatton PEACH BOTTOM ATOMIC POWER STATION not accurate for current UNITS 2 AND 3 plant conditions. UPDATED FINAL SAFETY ANALYSIS REPORT However, these results continue to provide a reasonable representation MAIN STEAM LINE BREAK characteristics. of the trends and ACCIDENT NORMALIZED CORE INLET FLOW
FIGURE 14.6.17 REV. 14 05/97 3.0r--------r-------~--------~------...,...------_,.--------...-------
2.0
a:
I.I..
- c u - 10 SECOND ISOLATION
~
- PUMPS TRIPPED AT T=O
1.0
o __________________________...._ ______..._ ______ __.1 ________..._ ______ _J
2
- 4 6 8 10 12 14
TIME (SEC) iAFTER BREAK)
PHILADELPHIA ELECTRIC COMPANY NOTE: Historical Information PEACH BOTTOM ATOMIC POWER STATION not accurate for current UNITS 2 AND 3 plant conditions UPDATED FINAL SAFETY ANALYSIS REPORT
MAIN STEAM LINE BREAK ACCIDENT MINIMUM CRITICAL HEAT FLUX RATIO
FIGURE 14.6.18 REV. 13 01/95 FUEL ROD DETAIL
Wl/lhl FUEL
~CLADDING
f::;:f}~:H Zr02
Zr~
TABLE OF RADIATION HEAT TRANSFER COEFFICIENTS RECEPTOR FUEL ROD TYPE CHANNEL 2 3 SIDE WALL
0.205 0.084, 0.007 0.2914 a..
4 EQUAL VOLUME 0 "' t- 0.04~ 0.177 0.0287 0.1788 a:: 0 RADIAL FUEL NODES ::> 0 0 a::
lol\\ _J 0.0212 0.221 0.150 0.0235 CHANNEL CROSS SECTION "'
IA.
0.003 0.0637 0.268 NIL I I 010000010 SIDE CHANNEL 0.0975 0.299 0.031 NIL WALL
- --- --- +--
010 0 00 010 0:0100010 10 I I 010:000 1 010 I I I CHANNEL
No. ROD 010 1 00010,0 L ____ _J ROD OF POWER TYPE ROOS FACTOR
-0 1 0 000 0 1-~----____, ___ 0 l.24 20 l.09 16 0.91 010000010 I I 9 0.85
FUEL BUNDLE DETAIL
NOTE: Historical Information PHILADELPHIA ELECTRIC COMPANY not accurate for current PEACH BOTTOM ATOMIC POWER STATION plant conditions UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT
FUEL ROD AND FUEL BUNDLE DETAILS
PIOURI 14.8.1 REV. 13 01/95 PBAPS UFSAR
FIGURES 14.10.1 thru 14.10.12A
PEACH BOTTOM
UFSAR Figures 14.10.1 thru 14.10.12A are represented by the figures listed below from GEH Document NEDC-33566P, Revision 0, as provided in support of the Peach Bottom, Units 2 and 3, Extended Power Update License Amendment Request dated September 28, 2012, as approved by the NRC on August 25, 2014 (Amendment Nos. 293/296).
The information provided in the referenced figures below are GEH Proprietary Information.
14.10.1 (Figure 2.6-4) Design Case Short-Term RSLB DBLOCA Containment Pressure Response - Design Case
14.10.2 (Figure 2.6-5) Design Case Short-Term RSLB DBLOCA Containment Temperature Response -
Design Case
14.10.3 (Figure 2.6-6) Bounding Case Short-Term RSLB DBLOCA Containment Pressure Response - Bounding Case
14.10.4 (Figure 2.6-7) Bounding Case Short-Term RSLB DBLOCA Containment Temperature Response -
Bounding Case
14.10.5 (Figure 2.6-8) Reference Case Short-Term RSLB DBLOCA Containment Pressure Response -
Reference Case
14.10.6 (Figure 2.6-9) Reference Case Short-Term RSLB DBLOCA Containment Temperature Response -
Reference Case
14.10.7 (Figure 2.6-10) Long-Term Small Steam Break LOCA Drywell Temperature Response
14.10.8 (Figure 2.6-1)SP and WW Temperature Response to RSLB DBLOCA (CIC)
14.10.8A (Figure 2.6-1a) SP and WW Airspace Temperature Response to RSLB DBLOCA Dual-Unit Interaction (CIC)
FIGURES 14.10.1 thru 14.10.12A (continued)
14.10.9 (Figure 2.6-2) DW and WW Airspace Temperature Response to DBLOCA (CIC)
14.10.9A (Figure 2.6-2a) DW and WW Airspace Temperature Response to DBLOCA Dual-Unit Interaction (CIC)
14.10.10 (Figure 2.6-11) Long-Term Small Break LOCA Suppression Pool Temperature Response
14.10.10A (Figure 2.6-11a) Long-Term Small Break LOCA Suppression Pool Temperature Response Dual-Unit Interaction
14.10.11 (Figure 2.6-1b) SP Temperature Response of Non-Accident Unit During Safe Shutdown
14.10.12 (Figure 2.6-3) SP Temperature Response to Loss of Normal RHR Shutdown Cooling Event (CIC)
14.10.12A (Figure 2.6-3a) SP Temperature Response to Loss of Normal RHR Shutdown Cooling Event Dual-Unit Interaction (CIC)
14.10.13 Deleted
14.10.14 (Figure 2.5-6) Deleted
UFSAR Figure 14.10.13 Deleted
UFSAR Figure 14.10.14 Deleted
Rev. 27 04/19