ML21109A028
Text
OPEN/CLOSE ANY VALVE FUEL BARRIER STOP/START 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 Of RADIOACTIVE ACCIDENT RELEASE OF MATERIAL ACCIDENT TVPE APPLICATION EVALUATION OF DAMAGE TO RADIOACTIVE MATERIAL BARRIERS RADIOACTIVE RADIOLOGICAL RELEASE EFFECTS ii c
FUEL t;;il------<~ BARRIER
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
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Note: This event is analyzed every reload. Refer to the Supplemental TRANSIENT RESULTS*
Reload Licensing Report (SRLR) for CLOSURE OF ALL MAIN the most recent version of this figure. 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 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 Note: Historical for Unit 2 Rev. 25 04/15
PBAPS UFSAR 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 Figures14.5.10 Figure 14.5.11A thru 14.5.11C Deleted Rev. 25 04/15
PBAPS UFSAR 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 REV. 26 04/17 04/17
PBAPS UFSAR Figures Figure14.5.1515 through 14.5.14 14.5.19 thru 14.5.19 Deleted REV. 26 04/17
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 3
MODERATOR DENSITY (&m/cm )
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:
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- IE 0.01 o::--~-:~~---::--~~-!:-~~...1...~~---1..~~-L~~-1..~~--1.~~-1.~~__J 0 10 20 30 40 50 60 70 80 90 100 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
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~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 continue to provide a ROD DROP ACCIDENT {COLD, CRITICAL) reasonable representation PEAK FUEL ENTHALPY of the trends and characteristics.
FIGURE 14.6.3 REV. 14 05/97
350 300 250 Ii
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_____ _r_ INITIAL ENTHALPY 0
0.02 0.03 0.04
&K/CONTROL ROD PECO ENERGY COMPANY PEACH BOTTOM ~TOMIC POWER STATION UNITS 2 AND 3 NOTE: Historical Informatton not accurate for current UPDATED FINAL SAFETY ANALYSIS REPORT plant conditions.
However, these results continue to provide a reasonable representation ROD DROP ACCIDENT (HOT, CRITICAL) of the trends and PEAK FUEL ENTHALPY characteristics.
FIGURE 14.6.4 REV. 14 05/97
220 210 200 190 ----;----
.......... ....._-- c*
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EXCURSION INCREMENT
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20 10 0
0 0.01 0.02 0.03 0.04 h k/CONTROL ROD PECO ENERGY COMPANY PIACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 NOTE: Historical Infonnation UPDATED FINAL SAFETY ANALYSIS REPORT not accurate for current 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
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0 2 3 6 8
' 5 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
A9
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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
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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 HIMBOLOT BAY TEST CATA
~H-ll 1'0 BOOECA BAY TEST 1llTH DEFLECTOR, DATA
\ FLAG 1 / 1 IHOICATES CALC:ULlTEO POINTS
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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
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 3 Historical information for Unit 2 not accurate for current plant conditions.
Rev. 25 04/15
EXELON CORPORATION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEACH BOTTOM LONG TERMATOMIC POWER STATION CONTAINMENT PRESSURE UNITSRESPONSE 2 AND 3 -
UPDATED FINAL SAFETY ANALYSIS REPORT NORMAL ECCS FLOW LONG TERM CONTAINMENT Historical information for Unit 2 not accurate for current plant PRESSURE RESPONSE -
conditions. FIGURE FIGURE NORMAL 14.6.10B 14.6.10B ECCS REV. REV. 25 04/15 24 FLOW 12/12 FIGURE 14.6.10B 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 UNITS 2 AND CONTAINMENT 3 PRESSURE FINAL SAFETY UPDATED RESPONSE ANALYSIS
- SMALL STEAM REPORT LINE BREAK (1.00 CONTAINMENT PRESSURE SQFT)
RESPONSE - SMALL STEAM LINE BREAK (1.00 SQFT)
FIGURE FIGURE 14.6.10C REV. 24 14.6.10C 12/12 REV. 25 04/15 Historical information for Unit 2 not accurate for current plant conditions.
(Unit 3)
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 3 Historical information for Unit 2 not accurate for current plant conditions.
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 LONG TERMUNITS 2 AND DRYWELL 3 AIRSPACE FINAL SAFETY UPDATED TEMPERATURE ANALYSIS RESPONSE - REPORT NORMAL LONG TERM ECCS FLOW DRYWELL AIRSPACE TEMPERATURE RESPONSE -
NORMAL ECCS FLOW Historical information for Unit 2 not accurate for current plant conditions. FIGURE FIGURE 14.6.11B REV. 24 14.6.11B 12/12REV. 25 04/15 Unit 3
EXELON CORPORATION PEACH BOTTOM ATOMIC POWER STATION UNIT 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEACH BOTTOM ATOMIC POWER STATION DRYWELLUNITS 2 AND AIRSPACE 3 TEMPERATURE UPDATED FINAL SAFETY RESPONSE - SMALLANALYSIS STEAM REPORT DRYWELLLINEAIRSPACE TEMPERATURE BREAK (0.25 SQFT)
RESPONSE - SMALL STEAM LINE BREAK (0.25 SQFT)
Historical information for Unit 2 not accurate for current plant conditions. FIGURE FIGURE 14.6.11C REV. 24 14.6.11C 12/12 REV. 25 04/15 Unit 3
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 LONGUNITS TERM2SUPPRESSION AND 3 UPDATED FINAL SAFETY POOL TEMPERATURE ANALYSIS RESPONSE - REPORT LONG NORMAL TERM ECCS SUPPRESSION FLOW POOL TEMPERATURE RESPONSE -
NORMAL ECCS FLOW Historical information for Unit 2 not accurate for current plant conditions. FIGURE FIGURE14.6.12A 14.6.12A REV. 24 03/03 REV. 25 04/15 Unit 3
0.5 c 0.4 a:
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PECO ENERCY COMPANY PEACH BOTTOM ATOMIC POWER STATION NOTE: Historical Information UNITS 2 AND 3 not accurate for current UPDATED FINAL SAFETY ANALYSIS REPORT plant conditions.
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-------.,------...-------
0
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NOTE: Historical Infonnat1on PECO ENERCY COMPANY not accurate for current 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 STOP VALVES FLOW/JP\
'"--"""~""'i I ;NTROLVALVES TURBINE GENERATOR FLaf
-\ -,
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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 I
- LIQUID 2
u
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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 MAIN STEAM LINE BREAK 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
- REACTOR SCRAMMED AT T=O
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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.
However, these results UPDATED FINAL SAFETY ANALYSIS REPORT continue to provide a reasonable representation of the trends and MAIN STEAM LINE BREAK characteristics. 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 Zr0 2 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..>
t- 0.04~ 0.0287 0.1788 4 EQUAL VOLUME "'
0 a:: 0 0.177 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
- - - - - - - +--
CHANNEL SIDE WALL 0.0975 0.299 0.031 NIL 010 0 00 010 0:0100010 I I0 1
010:000 I
1 I
010 I
CHANNEL No. ROD 010 L00010,0 1
____ _J ROD TYPE OF ROOS POWER FACTOR
- 0 0 000 1
-~---- ____0 1,___ 0 20 l.24 l.09 010000010 I I 16 9
0.91 0.85 FUEL BUNDLE DETAIL PHILADELPHIA ELECTRIC COMPANY NOTE: Historical Information PEACH BOTTOM ATOMIC POWER STATION not accurate for current 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)
Rev. 27 04/19
PBAPS UFSAR 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 Rev. 27 04/19