ML17130A270
| ML17130A270 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/06/2017 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17130A259 | List:
|
| References | |
| Download: ML17130A270 (52) | |
Text
OPEN/CLOSE ANY VALVE STOP/START ANY COMPONENT ELECTRICAL FAILURE MANIPULATE ANY CONTROL DEVICE SINGLE OPERATOR ERROR FUEL BARRIER NUCLEAR SYSTEM PROCESS BARRIER 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 Of RADIOACTIVE MATERIAL RELEASE ACCIDENT TYPE ACCIDENT APPLICATION EVALUATION OF DAMAGE TO RADIOACTIVE MATERIAL BARRIERS FUEL Iii!!--------<~ BARRIER RELEASE OF RADIOACTIVE RADIOLOGICAL EFFECTS
Unit 3 Rev. 25 04/15
PBAPS UFSAR 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.
Rev. 26 04/17
PBAPS UFSAR 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
Unit 3 Rev. 25 04/15
PBAPS UFSAR FIGURE 14.5.3A PEACH BOTTOM, UNIT 2 UFSAR Figure 14.5.3A for Unit 2 is represented by Figure 2.8-23, "Response to MSIV Closure with Flux Scram," from GEH Document NEDC-33566P, Revision 0, Page 2-470 (as noted in PUSAR Section 2.2.4.2, Page 2-383), 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 14.5.3A (Unit 2) Rev. 25 04/15
PBAPS UFSAR FIGURE 14.5.3B Deleted Rev. 26 04/17
PBAPS UFSAR FIGURE 14.5.4 Deleted Rev. 26 04/17
PBAPS UFSAR FIGURE 14.5.4A Deleted Rev. 26 04/17
Unit 3 Rev. 25 04/15
PBAPS UFSAR 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 Deleted
PBAPS UFSAR Figure 14.5.7A thru 14.5.7B Deleted
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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
Unit 3 Rev. 25 04/15 Note: Historical for Unit 2
PBAPS UFSAR FIGURE 14.5.10 PEACH BOTTOM, UNIT 2 UFSAR Figure 14.5.10 for Unit 2 is represented by Figure 2.8-24, "Loss of Feedwater Flow," from GEH Document NEDC-33566P, Revision 0, Page 2-471 (noted in PUSAR), 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 14.5.10 (Unit 2) Rev. 25 04/15
PBAPS UFSAR Figure 14.5.10 thru 14.5.11C Deleted Figures 14.5.11A Rev. 25 04/15
PBAPS UFSAR Figures 14.5.12a through 14.5.13 Deleted Rev. 26 04/17
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 UNIT 3 ONLY REV. 26 04/17
PBAPS UFSAR Figure 14.5.14 thru 14.5.19 Deleted 15 Figures 14.5.15 through 14.5.19 REV. 26 04/17
2.8 2.4 2.0 1.2 0.8 0.4 1.0 0.96 0.92 NOTE:
Historical Information not accurate for current plant conditions MAXIMUM IN-SEQUENCE ANO OUT-OF-SEQUENCE CONTROL ROD WORTH AS A FUNCTION OF AVERAGE MODERATOR DENSITY WORST ROD IN WORST POSSIBLE PATTERN" WORST NON*-WITHDRAWABLE
....;.;R~O~O~IN~NORMALPATTERNS WORST WITHDRAWABLE RODS ALLOWED FOR NORMAL PATTERNS 0.88 0.84 0.80 0.76 0.72 MODERATOR DENSITY (&m/cm3)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT MAXIMUM ROD WORTH VERSUS MODERATOR DENSITY FIGURE 14. 6.1 REV. 13 01/95
~
- c I-ct:
0 31:
0 0 ct:
..J 0 ct:
I-z 0 u
- IE
- l
! x <
- IE 0.06 0.05 0.04 0.03 0.02 0.01 0 ~~---:-:--~-:-~~~~~~-1-~~......L~~-L~~-L~~......l..~~-1..~~__J 0
10 20 30 40 50 60 70 100 80 90 NOTE:
Historical Information not accurate for current plant conditions PERCENT CORE POWER PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CONTROL ROD WORTH AS A FUNCTION OF CORE POWER FIGURE 14.6.2 REV. 13 01/95
350 t---------,r--------------------T--------------------
300 250
'5 t.
..J c
i=
200
~
..J
=>
2
~
~
~
3
..J 150 1.6-4 100 0
NOTE:
Historical Information not accurate for current plant conditions.
However, these results continue to provide a reasonable representation of the trends and characteristics.
CURVE NUMBER INITIAL POWER 1
10-8 x DESIGN 2
10~ x DESIGN*
10-3 x DESIGN 3
4 Hrl x DESIGN 0.04
~K/CONTROL ROD PECO ENERGY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD DROP ACCIDENT {COLD, CRITICAL)
PEAK FUEL ENTHALPY 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 a..
....J 3
z Li.:
100 50
_____ _r_
0 0.02 NOTE:
Historical Informatton not accurate for current plant conditions.
- However, these results continue to provide a
reasonable representation of the trends and characteristics.
CURVE NUMBER 1
2 3
INITIAL ENTHALPY 0.03
&K/CONTROL ROD INITIAL POWER 10~ x DESIGN url x DESIGN url l DESIGN 0.04 PECO ENERGY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNiTS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD DROP ACCIDENT (HOT, CRITICAL)
PEAK FUEL ENTHALPY FIGURE 14.6.4 REV. 14 05/97
220 210 200 c *
- f.
u a..
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- z:
I-z:
i.J
....J i.J
~
w..
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190 180 170 160 150 140 130 120 110 100 90 80 70 60 so 40 30 20 10 0
0 NOTE:
Historical Infonnation not accurate for current plant conditions.
' ' ' '\\
0.01
- However, these results continue to provide a
reasonable representation of the trends and characteristics.
\\
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FINAL MAXIMUM ENTHALPY EXCURSION INCREMENT CURVE No.
INITIAL POWER 2
\\
\\
1 2
3% Of' DESIGN 3~ OF DESIGN
\\
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' ' /',
INITIAL MAXIMUM CENTERLINE ENTHALPY 0.02 0.03 0.04 h k/CONTROL ROD PECO ENERGY COMPANY PIACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD DROP ACCIDENT (POWER RANGE)
PEAK FUEL ENTHALPY FIGURE 14.6.5 REV. 14 05/97
1200 1000
.§:
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0 2
3 A9 =AREA OF THE BREAK To= INITIAL DRYWELL TEMPERATURE A9 = 0.0147 D
TEST DATA CALCULATED x----)<
Toi~ 184 F. CARRYOVER 95:.*
To,* 70 f.. CARRYOVER 7P, lo,** 64 F,CARRYOVER 10';
To,. 103' F. CARRYOVER::: e:,c CALCULATED HOMOGENEOUS CARRYOVER CALCULATED ZEnO CARRYOVER
- --CALCULATED ZERO CARRYOVER ANO CONDENSATION 5
6 8
TIME fSECONOSI 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;
w a:
=>
VI VI 30 w
30 cc a..
w 3:
a:
20 A9=AREA OF THE BREAK c
20 To=DRYWELL TEMPERATURE 10 10 o.._ __________ _._ ____________ 1-. __________ -L __________ __,_o 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
H 1200 U)
Po..
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1000 U)
U) l'.:J 0::
Po..
800
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ZERO CARRYOVER Ae =AREA OF THE BREAK TO= ORYYIELL TEMPERA TU RE 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
\\
1'0 HIMBOLOT BAY TEST CATA BOOECA BAY TEST 1llTH DEFLECTOR, DATA FLAG 1
/
1 IHOICATES CALC:ULlTEO POINTS
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110
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10 JC
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~o 60 70 8G 90 100 ii4
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\\'!~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
Rev. 25 04/15 Unit 2 NOTE: For current plant conditions see Figures 14.10.1 14.10.3, and 14.10.5 Unit 3
Unit 3 Rev. 25 04/15 Historical information for Unit 2 not accurate for current plant conditions.
EXELON CORPORATION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM CONTAINMENT PRESSURE RESPONSE -
NORMAL ECCS FLOW FIGURE 14.6.10B REV. 24 12/12 FIGURE 14.6.10B REV. 25 04/15 FIGURE 14.6.10B REV. 25 04/15 LONG TERM CONTAINMENT PRESSURE RESPONSE -
NORMAL ECCS FLOW PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Historical information for Unit 2 not accurate for current plant conditions.
EXELON CORPORATION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PRESSURE RESPONSE - SMALL STEAM LINE BREAK (1.00 SQFT)
FIGURE 14.6.10C REV. 24 12/12 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CONTAINMENT PRESSURE RESPONSE - SMALL STEAM LINE BREAK (1.00 SQFT)
FIGURE 14.6.10C REV. 25 04/15 Historical information for Unit 2 not accurate for current plant conditions.
(Unit 3)
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 Historical information for Unit 2 not accurate for current plant conditions.
EXELON CORPORATION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM DRYWELL AIRSPACE TEMPERATURE RESPONSE -
NORMAL ECCS FLOW FIGURE 14.6.11B REV. 24 12/12 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM DRYWELL AIRSPACE TEMPERATURE RESPONSE -
NORMAL ECCS FLOW FIGURE 14.6.11B REV. 25 04/15 Historical information for Unit 2 not accurate for current plant conditions.
Unit 3
EXELON CORPORATION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT DRYWELL AIRSPACE TEMPERATURE RESPONSE - SMALL STEAM LINE BREAK (0.25 SQFT)
FIGURE 14.6.11C REV. 24 12/12 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT DRYWELL AIRSPACE TEMPERATURE RESPONSE - SMALL STEAM LINE BREAK (0.25 SQFT)
FIGURE 14.6.11C REV. 25 04/15 Unit 3 Historical information for Unit 2 not accurate for current plant conditions.
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 SHORT AND LONG TERM SUPPRESSION POOL TEMPERATURE RESPONSE -
NORMAL ECCS FLOW FIGURE 14.6.12A REV. 24 03/03 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT LONG TERM SUPPRESSION POOL TEMPERATURE RESPONSE -
NORMAL ECCS FLOW FIGURE 14.6.12A REV. 25 04/15 Historical information for Unit 2 not accurate for current plant conditions.
Unit 3
>-< c a:
UJ n..
UJ
- E
- J
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UJ UJ a:
~
UJ 0
~
UJ
..J 0.5 0.4 0.3 0.2 0.1 0......................,...... w.i... ____________________ _,_ ________....J~---------L-----------L----------J 10-1 NOTE:
Historical Information not accurate for current plant conditions.
- However, these results continue to provide a
reasonable representation of the trends and cha~acteristics.
TIME (-.seconds)
PECO ENERCY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 io' UPDATED FINAL SAFETY ANALYSIS REPORT PRIMARY CONTAINMENT LEAK RATE FIGURE 14.6. 13 REV. 14 05/97
z 0
~
(.)
UJ a::...
z UJ
(.)
a::
UJ G..
70r------..,.-------r------.------,.-------,-------,r-------r-------.,------...-------
2 RHR HX 60 50 40 30 20 10 0.8 1.0 1.6 o------::-':-------:'--------J------..J------L-------L------L-----..J.._-----L----_J o~
OA o~
1.2 1.4 1.8 2.0 DURATION OF RELEASE (hours)
NOTE:
Historical Infonnat1on not accurate for current plant conditions.
- However, these results continue to provide a
reasonable representation of the trends and characteristics.
PECO ENERCY COMPANY PEACH BOTTOM ATOMIC POWER STATION U~ITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT 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 u
FLaf
\\
-, o/
RESTRICTORS ~ _J/'
ISOLATION VALVES REACTOR TURBINE DRIVEN FEED PUMPS (3)
TURBINE TURBINE BYPASS SYSTEM COND.
PECO ENERGY COMPANY GENERATOR 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 I 2 u
~
'l:: <
w 20 a::
CD (j
0 a::
~
- i:
0
...J L'-
~
- E 10 z
STEAM ONLY
...J 0 0 u NOTE:
Historical Information not accurate for current plant conditions.
- However, these results continue to provide a
reasonable representation of the trends and characteristics.
LIQUID MIXTU~E LEVEL INSIDE VESSEL REACHES STEAM LINES STEAM TIME (seconds)
PECO ENERCY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT MAIN STEAM LINE BREAK ACCIDENT MASS OF 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 NOTE:
Htstortcal Infonnatton not accurate for current plant conditions.
- However, these results continue to provide a
reasonable representation of the trends and characteristics.
5 TIME (SEC) 6 7
a 9
10 PECO EHERCY COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT MAIN STEAM LINE BREAK ACCIDENT NORMALIZED CORE INLET FLOW FIGURE 14.6.17 REV. 14 05/97
3.0r--------r-------~--------~------...,...------_,.--------...-------
a:
I.I..
- c u
~
2.0 1.0
- 10 SECOND ISOLATION
- PUMPS TRIPPED AT T=O o __________________________...._ ______..._ ______ __.1 ________..._ ______ _J NOTE:
Historical Information not accurate for current plant conditions 2
4 6
8 10 12 TIME (SEC) iAFTER BREAK)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT MAIN STEAM LINE BREAK 14 ACCIDENT MINIMUM CRITICAL HEAT FLUX RATIO FIGURE 14.6.18 REV. 13 01/95
FUEL ROD DETAIL 4 EQUAL VOLUME RADIAL FUEL NODES CHANNEL CROSS SECTION I
I 010000010
- --- --- +--
010 0 00 010 0:0100010 10 I
I 010:000 1010 I
I I
010 100010,0 L ____ _J 0
10 000 0 10
- -~---- ____, ___
010000010 I
I FUEL BUNDLE DETAIL NOTE:
Historical Information not accurate for current plant conditions 0 a::
0 lol\\
Wl/lhl FUEL
~CLADDING f::;:f}~:H Zr02 Zr~
TABLE OF RADIATION HEAT TRANSFER COEFFICIENTS RECEPTOR a.. >
t-0 0 a::
_J IA.
FUEL ROD TYPE 2
3 CHANNEL SIDE WALL 0.205 0.084, 0.007 0.2914 0.04~
0.177 0.0287 0.1788 0.0212 0.221 0.150 0.0235 0.003 0.0637 0.268 NIL CHANNEL 0.0975 0.299 0.031 NIL SIDE WALL CHANNEL No.
ROD ROD OF POWER TYPE ROOS FACTOR l.24 20 l.09 16 0.91 9
0.85 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION 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 14.10.14 PEACH BOTTOM, UNIT 2 UFSAR Figures 14.10.1 thru 14.10.14 for Unit 2 (with the exception of Figure 14.10.13) 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 (with the exception of Figure 14.10.13) are GEH Proprietary Information 14.10.1 (Figure 2.6-4)
Design Case Short-Term RSLB DBLOCA Containment Pressure Response - Design Case (Unit 2) 14.10.2 (Figure 2.6-5)
Design Case Short-Term RSLB DBLOCA Containment Temperature Response -
Design Case (Unit 2) 14.10.3 (Figure 2.6-6)
Bounding Case Short-Term RSLB DBLOCA Containment Pressure Response - Bounding Case (Unit 2) 14.10.4 (Figure 2.6-7)
Bounding Case Short-Term RSLB DBLOCA Containment Temperature Response -
Bounding Case (Unit 2) 14.10.5 (Figure 2.6-8)
Reference Case Short-Term RSLB DBLOCA Containment Pressure Response -
Reference Case (Unit 2) 14.10.6 (Figure 2.6-9)
Reference Case Short-Term RSLB DBLOCA Containment Temperature Response -
Reference Case (Unit 2) 14.10.7 (Figure 2.6-10)
Long-Term Small Steam Break LOCA Drywell Temperature Response (Unit 2) 14.10.8 (Figure 2.6-1)
SP and WW Temperature Response to RSLB DBLOCA (CIC) (Unit 2) 14.10.8A (Figure 2.6-1a)
SP and WW Airspace Temperature Response to RSLB DBLOCA Dual-Unit Interaction (CIC) (Unit 2)
FIGURES 14.10.1 thru 14.10.14 (Unit 2) Rev. 25 04/15
PBAPS UFSAR FIGURES 14.10.1 thru 14.10.14 (continued) 14.10.9 (Figure 2.6-2)
DW and WW Airspace Temperature Response to DBLOCA (CIC) (Unit 2) 14.10.9A (Figure 2.6-2a)
DW and WW Airspace Temperature Response to DBLOCA Dual-Unit Interaction (CIC)
(Unit 2) 14.10.10 (Figure 2.6-11)
Long-Term Small Break LOCA Suppression Pool Temperature Response (Unit 2) 14.10.10A (Figure 2.6-11a)
Long-Term Small Break LOCA Suppression Pool Temperature Response Dual-Unit Interaction (Unit 2) 14.10.11 (Figure 2.6-1b)
SP Temperature Response of Non-Accident Unit During Safe Shutdown (Unit 2) 14.10.12 (Figure 2.6-3)
SP Temperature Response to Loss of Normal RHR Shutdown Cooling Event (CIC)
(Unit 2) 14.10.12A (Figure 2.6-3a)
SP Temperature Response to Loss of Normal RHR Shutdown Cooling Event Dual-Unit Interaction (CIC) (Unit 2) 14.10.13 SP Temperature Response to Station Blackout Dual-Unit Interaction (Unit 2) 14.10.14 (Figure 2.5-6)
SP Temperature Response to Appendix R Method A Shutdown (Unit 2)
FIGURES 14.10.1 thru 14.10.14 (Unit 2) Rev. 25 04/15
Figure 14.10.13 SP Temperature Response to Station Blackout-Dual Unit Interaction 0
50 100 150 200 250 0
5000 10000 15000 20000 25000 30000 Temperature(degF)
Time(second)
TorusTemperature ECR 10-00478 Rev. 0 - UFSAR Markups Page 318 of 389 PEACH BOTTOM ATOMIC POWER STATION UPDATED FINAL SAFETY ANALYSIS REPORT UNITS 2 AND 3 SP TEMPERATURE RESPONSE TO STATION BLACKOUT - DUAL UNIT INTERACTION FIGURE 14.10.13 REV. 25 04/15 NOTE: Applicable to Unit 2 - Post EPU implementation