ML18024B505
| ML18024B505 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/26/2018 |
| From: | Comanche Peak Nuclear Power Co |
| To: | O'Banion M Plant Licensing Branch IV |
| O'Banion M | |
| Shared Package | |
| ML18024B494 | List: |
| References | |
| Download: ML18024B505 (397) | |
Text
{{#Wiki_filter:CPSES/FSAR DELETED FIGURE 12.1-1 I 76 AMENDMENT 76 MAY 1, 1989
PROCESS IN TYPICAL DEMINERALIZER ARRANGEt.tENT < RESIN 0 ISPOSAL SPENT NITROGEN RESIN STORAGE TANK WASTE HOLDUP TANK RESIN SLUICE FILTER
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SPENT RESIN SLUICE PUMP COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 RESIN SLUICE AMENDMENT 87 WATER REUSE SYSTEM DECEMBER 18, 1992 FIGURE 12.3-1
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cv ~ ::::J 60 z 40 20 0.05 0. l 0.15 0.20 0.25 0.30 0.35 Cobalt Concentration (W/0) COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 87 CORE CRUD DEPOSITS DECEMBER 18, 1992 FIGURE 12.3-2
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z 8 6 4 2 ,... 0 t] mr 0.1 0.2 IT [ 0.3 0.4 0.5 rrr fmliil nm nn 0.6 0.7 0.8 0.~ n l. N1/Fe Ratio COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 87 CORE CRUD DEPOSITS DECEMBER 18, 1992 FIGURE 12.3*3
I CPE A B c D t E G H REV DWN CHKI APVD REMARKS CP-1 06~~ 0~~; TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0012-02-002945-01-00 2004 2004 RADIATION ZONES MAXIMUM DESIGN ZONE NO NOTE DOSE RATE(MREM/HR) DESCRIPTION AND EXPLANATION I THESE DRAWINGS INDICATE" AS-BUILT" SHIELDING THICKNESS AND PLANT RADIATION ZONE DESIGNATIONS BASED ON DESIGN BASES CD UNCONTROLLED,UNRESTRICTED ACCESS AREA RADIATION SOURCES LESS THAN 0.25 NON-RADIATION PERSONNEL & VISITORS OCCUPANCY: 40 HRS/WK, 50 WKS/YR 2 THESE DRAWINGS ARE ISSUED FOR INFORMATION ONLY ACTUAL RADIATION LEVELS AND INFORMATION PERTAINING TO ACCESS SHOULD BE OBTAINED FROM RADIATION CONTROLLED,OCCUPATIONAL ACCESS AREA 0 PROTECTION GROUP LESS THAN 2.5 RADIATION WORKERS & AUTHORIZED VISITORS 3 PLEASE REFER TO LATEST ISSUES OF STRUCTURAL AND OCCUPANCY: MAXIMUM 40 HRS/WK, 50 WKS/YR ARCHITECTURAL DRAWINGS FOR EXACT BUILDING DETAILS AND DIMENSIONS 0 LESS THAN 25.0 CONTROLLED,LIMITED ACCESS AREA 4 ALL ELEVATIONS ARE GIVEN TO FINISHED FLOOR LEGEND 8 MORE THAN 25.0 CONTROLLED,RESTRICTED ACCESS AREA WITH LIMITED OCCUPANCY NORMALLY EQUIPPED WITH LOCKABLE DOOR/GATE SH ST SHIELDING STRUCTURAL H.C HEAVY CONCRETE "1'" I G NO LIMITATION CONTROLLED,RESTRICTED ACCESS AREA,NORMALL Y INACCESSIBLE ACCESS IS VIA LOCKABLE DOOR M 0i
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CPE A B c D t E G H N...,...--- TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0013-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOMS 62A & B MAY EXCEED ZONE 11 LIMIT DURING RHR SYSTEM OPERATION REFERENCE DRAWINGs Al-0500 Sl-0600 Sl-0602 PLAN AT EL. 790'-6" RM# ROOM NAME 153 8 !53 63 FL. EL. 781'-7" 64 65 lf) 66 I FOR ROOM NAMES M 67 PLAN AT EL 773'-0" 68 SEE Al-0413 SERIES DRAWINGS 0i 69 70
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CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA 2005-003364-17-00 PER SK-0004-05-003364-17-00 NOTES FOR LEGEND, ABBREVlATlONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWINGS Al-0501 Sl-0519 Sl-0605 Sl-0618 PLAN ATEL. 808'-0" &812'-0" RM. # ROOM NAME 153 156A 154E 154F 154G FOR ROOM NAMES 154H SEE Al-0413 SERIES 1541 DRAWINGS 1541 154K 154L 154A 154B 154C 154D PLAN AT EL. 810'-6" 68 69 77A 77B 78 79 80 FOR ROOM NAMES 81 SEE Al-0413 SERIES 82 DRAWINGS 83 84 85 85A 85B 85C PARTIAL PLAN AT EL 800'-6" 75 } FOR ROOM NAMES SEE 76 Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL 819'-6" 155A PARTIAL PLAN AT EL 821 '-0" 86 } FOR ROOM NAMES SEE 87 Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL 822'-9" 155B FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 808'-0" & 810'-6" M1-3500 04 CP-2 M1-3500-04 c me754600.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0016-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-01 ROOM 98 AREA NEAR ENTRANCE TO ROOM 97 MAY EXCEED ZONE III LIMIT REFERENCE DRAWINGS AI-0502 SI-0522 SI-0608 SI-0618 PLAN AT EL 831 '-6" & 832' -6" RM. # RM. NAME ISSB ISSC 156B
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!57 ISSH 1551 1551 ISSK ISSD I SSE IS SF FOR ROOM NAMES I SSG SEE AI-0413 SERIES 88 DRAWINGS 89 90 91 92 93 94 95A&B 96 96A 96B 99A 99B 99C 99D PARTIAL PLAN AT EL. 841'-6" 97 FOR ROOM NAMES 98 SEE AI-0413 SERIES 99 DRAWINGS PARTIAL PLAN AT EL. 842'-0" 154M FOR ROOM NAMES SEE 16IB AI-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 849'-0"
!59 FOR ROOM NAMES SEE AI-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL. 831'-6" & 832'-6" M1-3500 05 CP-1 M1-3500-05 c me547700.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0017-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-01 REFERENCE DRAWINGS AI-0503 SI-0525 SI-0528 SI-061 I PLAN AT EL. 852'-6" & EL. 860'-0" RM.# RM. NAME 155L 163 16IC 155P 155H 1551 1551 155K 155L 155M FOR ROOM NAMES 155N SEE AI-0413 SERIES 100 DRAWINGS IOOA THRU IOOH 101 102 103 104 105 105A 105B PARTIAL PLAN AT EL. 851 '-6" I 55L FOR ROOM NAMES SEE 16IB AI-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 871'-6" 155N FOR ROOM NAMES SEE AI-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 886'-0" 16ID FOR ROOM NAMES SEE AI-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 852'-6" & 860'-0" M1-3500 06 CP-1 M1-3500-06 c me547800.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0018-02-002945-01-00 NOTES FOR LEGEND, ABBREVlATlONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWINGS Al-0504 Sl-0528 Sl-0530 Sl-0614 PLAN AT EL. 873'-0" & 880'-6" RM.# RM.NAME 155L 161C,D 0'\ I 155P M 1550 155H 0i 1551 1551 155K 155M
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CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0019-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-0I REFERENCE DRAWINGS AI-0505 SI-06I7 PLAN AT EL. 905'-9" & 896'-4" RM. # ROOM NAME I6IE I60B I60A FOR ROOM NAMES I6IA SEE SI-04I3 SERIES DOME DRAWINGS III I I2 0,........ 246A I M 0i
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CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0020-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0506 I M 0i
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I CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA 2000-003261-02-00 PER SK-0067-00-003261-02-00 N~-- FL. EL. 785' -6" NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWINGS: Al-0508 S-0700 S-0703 PLAN AT EL. 778'-0" & 790'-6" RM.# RM. NAME 113 114 115 115A 115B 115C 115D 130 162 C"l 163 I 164 M 165 0i 166 167 168 169 FOR ROOM NAMES
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CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0021-02-002945-01-00 NOTES FOR LEGEND,ABBREVIATIONS,RADlATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0508 S-0711 S-0714 S-0707 PLAN AT EL. 807'-0" RM.# RM. NAME 133 134 134A 134B 188 189 190 M 191 I 192 M 193 0i 194 195 196 FOR ROOM NAMES 197 SEE Al-0413 SERIES
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CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0022-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOM 218 IS RADIATION ZONE V ONLY BECAUSE OF HIGH RADIATION LEVELS DURING SPENT RESIN TRANSFERS PLAN AT EL. 830'-0" & 831 '-6" REFERENCE DRAWING: Al-0509 Al-0512 S-0718 S-0721 RM.# Rm. Name 135 136 137 138 139 140 141 142 143 144 145 146 147 207A 207B 210A 210B 211A 211B 212 FOR ROOM NAMES 213 SEE Al-0413 SERIES DRAWINGS 214 215A THRU 215V 216 217A THRU 217F 218 219 220 221 222 223 224 225 226 233A PARTIAL PLAN AT EL. 840'-6" 148 148A 148B FOR ROOM NAMES 148C SEE Al-0413 SERIES DRAWINGS 148D 149 NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY & ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL 830' -0" & 831 '-6" M1-3500 12 CP-1 M1-3500-12 c me548300.dgn A B D E G FINAL PRINT H
I CPE A B c D t E G H REV DWN CHKI APVD REMARKS CP-1 06~~ 2004 oizi 2004 TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0023-02-002945-01-00 N ---.. 1 1 B A
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CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0024-02-002945-01-00 N DEMINERALIZER CUBICLES SHIELD WALL THICKNESSES NORTH EAST SOUTH WEST SLAB ABOVE RM.NO WALL WALL WALL WALL &BELOW 228A 3'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228B 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228C 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" NOTES 228D 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228E 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" FOR LEGEND, ABBREVIATIONS, RADIATION ZONES 228F 2'-0" 2'-0" 2'-0" 3'-0" 2'-9" AND GENERAL NOTES SEE MI-3500-01 228G 2'-0" 2'-0" 2'-0" 2'-6" 2'-2" 228H 2'-0" 2'-0" 2'-0" 2'-6" 2'-2" 2281 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" REFERENCEDRAWINGS AI-0511 228K 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" S-0725 228L 2'-0" 2'-0" 2'-0" 2'-0" 2'-2" 228M 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228N 2'-0" 2'-0" 3'-0" 3'-0" 2'-2" PLAN AT EL. 842'-0" 23IA 2'-9" 3'-0" 2'-0" 3'-0" 2'-2" RM.# RM. NAME 23IB 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 23IC 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 207A 23ID 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 219A 23IE 2'-0" 3'-0" 2'-0" 3'-0" 2'-9" 228A TIIRU 228G 228H TIIRU 228N 227 SEE TABLEZONEF-1 SEETABLEZONEF-1 23IF 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 2'-0" 3'-0" 2'-0" 3'-0" 2'-9" 227A 23IG 23IH 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 228A 23IJ 2'-3" 3'-0" 2'-0" 3'-0" 2'-2" THRU 23IK 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 228N FOR ROOM NAMES 2'-0" 3'-0" 3'-0" 2'-2" SEE AI-0413 SERIES 23IL 2'-0" 230 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" DRAWINGS 231M 23IA G 23IN 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 2'-0"SLAB,SH THRU 2'-0"SLAB,SH 230 23IP 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" ABOVE & BELOW ABOVE & BELOW 23IQ 23IQ 2'-0" 3'-0" 2'-9" 3'-0" 2'-2" 232 G 233 NOTE: ALL DEMINERALIZER CUBICLES ARE RADIATION ZONE 233A 233A 231J TIIRU 231Q SEETABLEZONEF-1 PIPE CHASE EL. 844'-6" PLAN AT EL. 842'-0" NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY BUILDING PLAN AT EL 842'-0" M1-3500 14 CP-1 c me548400.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0025-02-002945-01-00 N 2'-0" SH 234 0 S> ~ NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES D D D D AND GENERAL NOTES SEE MI-3SOO-OI REFERENCE DRAWING: AI-OSlO 23S (III) S-0728 S-0707 PLAN AT EL. 8S2'-6" & 8S4'-4" D D D D D D @) RM.# RM.NAME
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CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-02945-01-00 PER SK-0026-02-002945-01-00 N NOTES (1) FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-0I (2) THE RM 80 ASSOCIATED WITH THIS TAG NUMBER IS SHOWN TO BE IN A RADIATION ZONE III. HOWEVER IT HAS BEEN DETERMINED BY EVALUATION THAT THE DOSE RATE AT RM 80 MEETS THE REQUIREMENTS FOR A ZONE II DESIGNATION REFERENCE DRAWING: AI-05II AI-0506 GPM S-0735 S-074I (NOTE 2) PLAN AT EL. 873'-6" PARTIAL PLAN AT EL. 886'-6" Rrn.# 244 } FOR ROOM NAMES 245 SEE AI-04I3 SERIES 1:'-- 246C DRAWINGS I M PARTIAL PLAN AT EL. 886'-6" 246 FOR ROOM NAMES SEE AI-04I3 SERIES DRAWINGS 0i
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I NON-SAFETY ROOFEL 873'-4" LUMINANT CPSES GLEN ROSE, TEXAS PLAN AT EL. 873'-6" RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY & ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL. 873'-6" & 886'-6" M1-3500 16 CP-1 c me548700.dgn A M1-3500-16 B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0027-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOMS 251 AND 252 ARE RADIATION ZONE IV ONLY BECAUSE OF HIGH RADIATION LEVELS DURING SPENT RESIN TRANSFERS TRANSIENT CONDITIONS SUCH AS SPENT FUEL OR RESIN TRANSFER MAY CAUSE INDICATED RADIATION ZONE LIMITS IN THE FUEL BUILDING TO BE EXCEEDED REFERENCE DRAWING: Al-0520 S-0800 S-0814 PARTIAL PLAN AT EL. 802'-0" 247 } FOR ROOM NAMES 247A SEE Al-0413 SERIES 249B DRAWINGS 00 PLAN AT EL. 810'-6" I RM.# RM. NAME M 247 0i 247A 248 249 249A
~
249B 250 250A 250B FOR ROOM NAMES 251 SEE Al-0413 SERIES ........ 252 DRAWINGS ~
~
253 254 255 Vl 256 ~ 257 257A 258 259
~
260 262
""::;1 Si PARTIAL PLAN AT EL. 825'-2" AND 822'-6" 5 254 FOR ROOM NAMES
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261 SEE Al-0413 SERIES '""" 262
}
DRAWINGS 'r:l"
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NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT FUEL BUILDING PLAN AT EL 810'-6",822'-6" & 802'-0" M1-3500 17 CP-1 c me548800.dgn A M1-3500-17 B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0028-02-002945-01-00 NOTES I FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 2 TRANSIENT CONDITIONS SUCH AS SPENT FUEL OR RESIN TRANSFER MAY CAUSE INDICATED RADIATION ZONE LIMITS IN THE FUEL BUILDING TO BE EXCEEDED REFERENCE DRAWING: Al-0521 S-0803 PLAN AT EL. 838'-9" & 841'-0" RM.# RM. NAME 258 259 260 263 263A 264 265 FOR ROOM NAMES 266 SEE Al-0413 SERIES DRAWINGS 267 268 269 270 270A 271 271A 271B NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT FUEL BUILDING PLAN AT EL 838'-9" & 841'-0" M1-3500 18 CP-1 Ml-3500-18 c me548900.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0029-02-002945-01-00 N NOTES I FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 2 TRANSIENT CONDITIONS SUCH AS SPENT FUEL OR RESIN TRANSFER MAY CAUSE INDICATED RADIATION ZONE LIMITS IN THE FUEL BUILDING TO BE EXCEEDED 3 AREA ABOVE POOL IS DESIGNATED A RADIATION ZONE 11 AREA REFERENCE DRAWING: Al-0522 S-0806 S-0809 PLAN AT EL. 860'-0" RM.# RM.NAME 272 FORROOMNAMES 272A SEE Al-0413 SERIES
}
272B DRAWINGS PARTIAL PLAN AT EL. 899'-6" 0 273 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS C"l I M 0i ROOF X-RE-6272 LRAM ~
~
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0 D 272 Vl
~
X-RE-6274 PARTIAL PLAN AT EL. 899'-6" LRAM
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NON-SAFETY PLAN AT EL. 860'-0" LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT FUEL BUILDING PLAN AT EL. 860'-0" & 899'-6" M1-3500 19 CP-1 M1-3500-19 c me549000.dgn A B D E G FINAL PRINT H
t N 1 LOCATION B (APPROX) MOVABLE RCA BOUNDARY DOORS ADMINISTRATIVELY CLOSED WHEN REQUIRED FOR LEGEND, ABBREVIATIONS, RADIATION ZONES FOR RCA BOUNDARY AND GENERAL NOTES, SEE DRAWING Ml-3500-01 c::1 J-, CD ~ I I
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~
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ffi SWITCHGEAR ROOM ROOF PLAN AT EL. 833'-10" v NON-SAFETY PLAN AT EL. 810'-6" TXUPOWER CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT- UNIT 1 TURBINE BUILDING PLAN AT EL. 810'-6" & 833'-0" Ml-3500 23 CP-2 me600300dgn A Ml-3500-23 FINAL PRINT
I CPE A B c D t E G H REV DWN CHKI APVD REMARKS CP-1 o7"o~ 07~~ TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0030-02-002945-01-00 2004 2004
~
- ~
PLANT
-----NciR.T'H"-- NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-0I I
s REFERENCE DRAWING: AI-0408 I-RE-5IOO LPM PLAN AT EL. 755'-4" 1-001 1' \ I I RM.# RM.NAME
***~-*:?ei)~]I CD I-OOI FOR ROOM NAMES SEE AI-04I3 SERIES DRAWINGS b
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NON-SAFETY LUMINANT PART- PLAN AT EL 755'-4" CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT TURBINE BUILDING PLAN AT EL 755'-4" DWG.NO M1-3500 Is2oo IREV CP-1 M1-3500-20 c me549IOO.dgn A B D E G FINAL PRINT H
I CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0031-02-002945-01-00 N~-- 1-007D 1-007B NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-0I REFERENCE DRAWING: AI-04I3-0I PIPE TRENCH ID I PLAN AT EL. 778'-0" RM.# RM. NAME I-005 I-006 I-007 I -007A FOR ROOM NAMES I-007B SEE AI-04I3 SERIES I-007C DRAWINGS I-007D I-007E ~ 2-282A ,........ 2-282C C"l () () I M 0i D JJJ 1-005 ~
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2-282C DDDO 1-007C "'r:l D D FORCONT ~ SEE M2-3500-09 NON-SAFETY PLAN AT EL 778'-0" LUMINANT TURBINE BUILDING CPSES BASEMENT FLOOR PLAN GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 1 TURBINE BUILDING PLAN AT EL 778'-0" M1-3500 21 CP-1 M1-3500-21 c me549200.dgn A B D E G FINAL PRINT H
I CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0011-02-002945-01-00 N /
/"'*"
/
/
1
/
/
/
/
/
" ""I NOTES
/ /
1 FOR LEGEND, ABBREVlATlONS, RADIATION ZONES
/ i AND GENERAL NOTES SEE Ml-3500-01
/ I
// i REFERENCE DRAWING: A2-0403
// ~I~==~~
/
/ PLAN AT EL. 810'-6"
/ Rrn.# RM. NAME
< 38
"" 39
"" 39A 39B FOR ROOM NAMES SEE Al-0413 SERIES
"" 39C DRAWINGS 42 42A
"" 287
~~~- --_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--_--c--~=~d-~~=rm1""
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~~ ~~IL
~
d h 42A qL__~-P 42 (!) 39 G NON-SAFETY PLAN AT EL 810'-6" SWITCHGEAR ROOM ROOF LUMINANT PLAN AT EL 833'-10" CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT- UNIT 2 TURBINE BUILDING PLAN AT EL 810'-6" & 833'-0" M2-3500 11 CP-1 M2-3500-11 c me547200.dgn A B D E G FINAL PRINT H
I CPE A B c D t E G H REV DWN CHKI APVD REMARKS CP-1 o7"o~ o7'o~ TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0008-02-002945-01-00 2004 2004
~
~ -
PLANT
-----NciR.T'H"--
NOTES FOR LEGEND,ABBREVIATIONS,RADIATION ZONES AND GENERAL NOTES SEE MI-3500-01 II 2-RE-5100 REFERENCE DRAWING: AI-0408 LPM I 2-001 I t
~
PLAN AT EL. 755' -4" 1[~9&1: ___ RM.# 2-001 RM.NAME FOR ROOM NAMES SEE AI-0413 SERIES DRAWINGS d LJ '--m'-6"
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NON-SAFETY LUMINANT PART- PLAN AT EL 755'-4" CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNlT 2 TURBINE BUILDING PLAN AT EL 755'-4" DWG.NO M2-3500 I soso I REV CP-1 me546400.dgn A M2-35QQ-Q8 B c D E G FINAL PRINT H
I CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0009-02-002945-01-00 N~-- 2-282B NOTES 2-282D FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0413-01 PIPE TRENCH PLAN AT EL. 778'-0" RM.# RM. NAME I-007A 2-281 2-282 FOR ROOM NAMES 2-282A SEE Al-0413 SERIES 2-282B DRAWINGS 2-282C 2-282D C"l 0i () () C"l I M 0i 2-281 D D uuu ~
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FORCONT ~ SEE Ml-3500-21 NON-SAFETY PLAN AT EL 778'-0" LUMINANT TURBINE BUILDING CPSES BASEMENT FLOOR PLAN GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 2 TURBINE BUILDING PLAN AT EL 778'-0" M2-3500 09 CP-1 M2-3500-09 c me546600.dgn A B D E G FINAL PRINT H
I CPE A B c D t E G H REMARKS CORPORA 1E DESIGN CHANGE
~:-~02-002945-01-00 RAWING REVISED TO ~032-02-002945-01-00 PER SK-1~1 Dl 10
~ ~
l-RE-2959 llll 1)1 CD I ClQ]II NOTES: RADIATION ZONES FOR LEGEND, ABBREVlATlONS,WlNG NOTES, SEE DRA Ml-3500-01 AND GENERAL REFERENCE DRAWING: Al-0401
~ lOB 0 PLAN ATEL 803'-0" & 810'-6" Rm# RM.NAME TYP 16 0
10 lOA lOB B 8(D llA llB FL. EL. 803'-0" 11 12 13 14 l0 MNAMES 15 FOR RlO 00413 SERIES SEEA-16 DRAWINGS A(APROX) [: LOCATION ABOUNDARY 17 MOVABLE RC RY MAY BE 18 RCA BOU~~'bCATlON B 19 MOVEDT NDER 20 (Ml-3500-23) U E CONTROLS 21 IL8JIL8JI ADMlNlSTRATlV 22 SEE Ml-3500-23 23 D 24 27A 33 41 43A
~
D D NON-SAFETY 03'-0" & EL. 81 0' -6" PLAN AT EL. 8 PLAN MEZZANINE FLOOR Ml-3500-22 c me549300.dgn A B D E G FINAL PRINT
I CPE A B c D t E H TillS DRAWING REMARKS FDA-2002-002945~~~~~~R~K~~~0~2~:~45DESIGN 00 CHANGE N I II =n l- = I 288A (!) FOR LEGEND AND GENE RAL NOTES SEE MI~:J5~~iATION ZONES
'ABBREVIATION REFERENCE DRAWING: A2-040I i PLAN AT EL. 803' -O " & 8I0'-6" RM.#
i RM.NAME [~ i IO 288B (!) I6 2-32 34
! 35 D i i
I-36 I-37 43 D 283 284 i 285 FL. EL 285A 8I0'-6" i 2-286 2-286A (!) 286 i 288A 288B i
~
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00 I 32 (!) B FL. EL. 803'-0" 283 (!) 285A d 2-RE-2959 11(1 Ill NON-SAFETY IO lrr==TIIc'J~ PLAN AT EL. 803'-0" & MEZZANINE EL. 810'-6" FLOOR PLAN me546200.dgn A M2-35QQ-1Q B c D E G
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0001-02-002945-01-00 NOTES 1 FOR LEGEND, ABBREVlATlONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 2 ROOMS 62A AND 62B MAY EXCEED ZONE 11 LlMlT DURING RHR SYSTEM OPERATION REFERENCE DRAWING: A2-0500 ,S2-0600 ,S2-0602 PLAN AT EL. 790'-6" RM. # ROOM NAME 153 63 64 65 66 67 FOR ROOM NAMES SEE Al-0413 SERIES 68 DRAWINGS 69 C"l 70 M 71 C"lI 72 M 73 0i 74 74A
~
PL.AN ATEL 773'-0" 51 52 53 ~
~
54 55 Vl 56A
~
56B FOR ROOM NAMES SEE Al-0413 SERIES 57 DRAWINGS 58
~
59
""::;1 60 Si 61 5 62 "'u
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~
62H NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 773'-0",785'-6" & 790'-6" M2-3500 01 CP-1 M2-3500-01 c me546700.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0002-02-002945-01-00 N~-- NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-0I ROOM 85D CONTAINS SOURCES WHICH MAY EXCEED ZONE III LIMIT DURING REFUELING WATER TRANSFER FL.EL.810'-6" REFERENCE DRAWING: A2-0500 S2-03I8 REFUELING WATER STORAGE TANK PLAN AT EL. 8I0'-6" & BELOW REACTOR MAKE-UP
'WATER STORAGE TANK Rm # ROOM NAME 70 } FOR ROOM NAMES SSD SEE AI-04I3 SERIES DRAWINGS M
M C"lI I I
- L______________________________ _ M L----r-.+---------------,- ------+---------------------------------
0i 1 1 I GFL.EL.800'-0" I I GFL.EL.800'-0" I I
~
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,-----------~l~---------------~ 1---------------------------------
FL.EL. 810'-6" 1 I r------------------------------- I 1 I I 85D I I I I
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SEEMZ-3500-01
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G 10 FL. EL. 790'-6" PLAN ATEL 810'-6" NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 810'-6" & BELOW M2-3500 02 CP-1 c me546800.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA 2005-003364-07-00 PER SK-0007-05-003364-07-00 NOTES 1 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SE Ml-3500-01 R REFERENCE DRAWING: A2-0501 S2-0605 S2-0618 S2-0519 PLAN AT EL. 808'-0" & 812'-0" RM. # ROOM NAME 153 156A 154E 154F 154G 154H ~ FOR ROOM NAMES M 1541 SEE Al-0413 SERIES C"l 1541 DRAWINGS I 154K M 154L 0i 154A 154B 154C 154D
~
PLAN AT EL. 810'-6" 68 69 77A
~
77B 78 79 80
~
Vl FOR ROOM NAMES 81 SEE Al-0413 SERIES ~ 82 DRAWINGS 83 84 85 ~ 85A ""::;1 85B Si 85C 5 PARTIAL PLAN AT EL 800'-6" "'u
~
FOR ROOM NAMES '"""
~~ } SEE Al-0413 SERIES 'r:l" DRAWINGS
~
PARTIAL PLAN AT EL 819'-6" ""
- l 155A FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS u 0
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PARTIAL PLAN AT EL 821 '-0" FOR ROOM NAMES 86
}
SEE Al-0413 SERIES "'r:l 87 DRAWINGS
~
PARTIAL PLAN AT EL 822'-9" 155B FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT-UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLAN AT EL 808'-0" & 810'-6" DWG.NO M2-3500 03 CP-2 c me692200.dgn A M2-3500-03 B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0004-02-002945-01-00 NOTES FOR LEGEND, ABBREV1AT10NS, RADIATION ZONES AND GENERAL NOTES SEE M1-3500-01 ROOM 98 AREA NEAR ENTRANCE TO ROOM 97 MAY EXCEED ZONE lll LlM1T REFERENCE DRAWING: A2-0502 S2-0608 S2-0522 S2-0618 PLAN AT EL. 831 '-6" & 832' -6" Rm.# RMNAME 155B 155C 156B lf) 158 M 157 C"l I 155H M 1551 0i 155J 155K 155D 155E
~
155F 155G FORROOMNAMES 88 SEE A1-0413 SERIES 89 DRAWINGS 90 ~ 91 92 93 ~ Vl 94
~
95A&B 96 96A 96B
~
99A ~ 99B ::;1 99C Si 5 99D
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~
97 } FOR ROOM NAMES ""
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99 DRAWINGS
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~
154M} FORROOMNAMES 161 B SEE A1-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 849'-0"
!59 FOR ROOM NAMES SEE A1-0413 SERIES DRAWINGS LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 2 CONTAINMENT & SAFEGUARD BUlLDING PLANS AT EL. 831'-6" & 832'-6" DWG.NO M2-3500 04 CP-1 M2-3500-04 c me547000.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0005-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: A2-0503 S2-0611 S2-0525 S2-0528 PLAN AT EL. 852'-6" & EL. 860'-0" Rrn.# RM.NAME 155L 163 161C 155P 155H 1551 1551 155K 155M 'D 155N FOR ROOM NAMES M 100 SEE Al-0413 SERIES C"lI DRAWINGS lOOA M THRU 0i lOOH 101 102
~
103 104 105 105A 105B ........
~
~
PARTIAL PLAN AT EL. 851'-6" 155L FOR ROOM NAMES Vl 161B } SEEAl-0413 SERIES DRAWINGS
~
PARTIAL PLAN AT EL. 871 '-6" 155N FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 886'-0"
~
161D FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS
""::;1 Si 5
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NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 852'-6" & 860'-0" DWG.NO M2-3500 05 CP-1 M2-3500-05 c me546900.dgn A B D E G FINAL PRINT H
CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0006-02-002945-01-00 N G 155N NOTES 1 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: A2-0504 S2-0528 S2-0530 S2-0614 PLAN AT EL. 873'-0" & 880'-6" Rrn.# RM. NAME 155L 161C,D 155P B.O.CEL 155P 1550 881 '-6" 155H 155I 1551 1:'-- 155K M 155M C"lI G 155N M 155M 106 FOR ROOM NAMES 0i 107 SEE Al-0413 SERIES 108 DRAWINGS 108A
~
THRU 108H 109A THRU 109D ........
!lOA ~
~
THRU EL. 897' -6" llOD Vl (TYP) ~ X-RE-5570B WRGM ROOF EL. 873' -4" G
~
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CPE A B c D t E G H TillS DRAWING REVISED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0007-02-002945-01-00 N NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES 2-RE-6290B AND GENERAL NOTES SEE MI-3500-0I HRRM REFERENCE DRAWING: A2-0505 S2-06I 7 PLAN AT EL. 905'-9" & 896'-4" 2-RE-6290A Rm # ROOM NAME HRRM I6IE I60B I60A I6IA FOR ROOM NAMES SEE AI-04I3 SERIES DOME DRAWINGS III I I2 246B 00 M C"lI M 0i FL. FL. 900'-3"
~
~
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~
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~
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COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS ~ AND 2 FUEL TRANSFER TUBE SHIELDING PROVISIONS FIGURE 12.3-33 Sh. I of 3
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS i AND 2 FUEL TRANSFER TUBE SHIELDING PROVISIONS FIGURE 12.3-33 Sh. 2 of 3
A B c D t E G H 3A 5TEEL PLATES 5HJEL.OIN~ SECTION 3A* 3A SECTION 3-3 Amendment 102 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 SECTION 3C- 3C CAS SHOWN) FUEL TRANSFER TUBE SECTION 30-30 (OPP. HAND) SHIELDING PROVISIONS FIGURE 12.3-33 SH 3 OF 3 I fsOOOOl b.dgn A B c D E G H
CPE A B c D t E G H TillS DRAWING CREATED TO INCORPORA 1E DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0014-02-002945-01-00 N NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE MI-3500-0I ROOM 85D CONTAINS SOURCES WHICH MAY EXCEED ZONE III LIMIT DURING REFUELING WATER TRANSFER FL.EL. 810'-6" REFERENCE DRAWINGS AI-0500 SI-03I8 I I I REACTOR MAKE-UP I WATER STORAGE TANK I
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I I FL.EL. 800'-0" I I FL.EL. 800'-0" PLAN AT EL. 8I0'-6" & BELOW I I I I
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PLAN AT EL 810'-6" NON-SAFETY LUMINANT CPSES GLEN ROSE, TEXAS RADlA TION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 810'-6" & BELOW M1-3500 03 CP-1 M1-3500-03 c me547500.dgn A B D E G FINAL PRINT H
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CPSES/FSAR FIGURE 12.5-1 HAS BEEN DELETED 1 87 Amendment 87 December 18, 1992
CPSES/FSAR Figure 12.5-2 has been deleted. 83 AMENDMENT 83 DECEMBER 13, 1991
CPSES/FSAR FIGURE 12.5-3 HAS BEEN DELETED 1 a7 Amendment 87 December 18, 1992
Vistra Energy Corp. Vistra Intermediate Company LLC Vistra Operations Company LLC* (Operator) Vistra Asset Company LLC Vistra Preferred Inc. Comanche Peak Power Company LLC* (Owner) COMANCHE PEAK S.E.S.
- Denotes NRC Licensee.
FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 Amendment 108 Corporate / Licensee(s) (Simplified Organization Diagram) FIGURE 13.1-1
Chief Operating Officer, Vistra Operations Company LLC (1) Senior Vice President
& Chief Nuclear Officer Operations Review Committee Sr. Director, Nuclear Site Vice Engineering &
President Regulatory Manager, Nuclear Manager, Affairs Plant Director, Organizational Oversight Regulatory Manager Effectiveness Affairs Director, Director, Manager, Safeteam Projects & Director, Site Environmental Manager Support Nuclear Engineering Services Engineering Director, Director, Training Operations Maintenance Manager, Emergency Manager, Planning Nuclear Corrective Manager, Manager, Director, Manager, Action Program Manager, System Technical Work Radiation Security Engineering Support Management Protection Manager, Plant Reliability COMANCHE PEAK SES SAFETY ANALYSIS REPORT for DUAL UNIT OPERATIONS Nuclear Generation NOTE: (1) Located at Corp. Office All others located on-site Figure 13.1-2 AMENDMENT 108
Site Vice President Director, Director, Nuclear Organizational Effectiveness Training Plant Manager Manager, Manager, Manager, Emergency Environmental Nuclear Corrective Planning Services Security Action Manager Director, Manager, Director, Director, Work Safety Program Maintenance Operations Management Manager, Radiation Protection Maintenance Maintenance Manager, Shift SMART Plant Operations Operations Team Support Support. Mgr. Managers Managers Manager, Nuclear Shift Chemistry. Mgr. Maintenance Support Group Ops Performance Improvement Warehouse COMANCHE PEAK SES SAFETY ANALYSIS REPORT FOR DUAL UNIT OPERATIONS NUCLEAR OPERATIONS FIGURE 13.1-3 Amendment 108
January 19, 1982 UNITED STATES OF AMERICA NUCLEAR REGULATORY C01f1ISSION It is agreed that this Stipulation is contingent upon its acceptance BEFORE THE ATOMIC SAFETY ANO LICENSING BOARD by the NRC Staff and upon dismissal of Contention 1 by the licensing Board, In the Matter of and shall be incorporated in and become a part of the Final Safety Analysis TEXAS UTI LIT! ES GENE RAT! NG COMPANY, !!_ ill* Docket Nos. 50-445 and Report to Comanche Peak. 50-446 (Comanche Peak Steam Electric Station, Units 1 and 2) 6/lil~ STIPULATION
~o/~re Citizens for Fair Utility Regulation On the basis of negotiations between Citizens for Fair Utll ity Regulation
("CFUR") and Texas Utilities Generating Company,!!_!}_. ("Applicants") and the representations below, CFUR hereby withdraws Contention 1 from litigation in this proceeding. DATE: January 19, 1982 Applicants hereby represent that they will assemble a qualified in-house technical staff prior to fuel loading for Comanche Peak and maintain that tn
"'T1
-l ro staff for the duration of plant operations. Applicants further represent that
-n fT1 C5 n c:::0 (/) :c (f)~ the technical staff will itself be qualified to deal with normal operations,
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A B c D t E G H I. UNIT I MAIN CONTROL BOARD
- 2. NOTUSED
- 3. NOTUSED
- 4. SWITCHYARD CONSOLE
- 5. UNIT I RMS
- 6. UNITS I & 2 NIS
- 7. HVAC PANELS
- 8. FIRE DETECTION PANEL & COMMON ELECTRICAL SYSTEMS PANEL
- 9. HVAC PANELS
- 10. INCORE MOVABLE FLUX MAPPING SYSTEM 12 10 II. SEISMIC RECORDER PANEL 9 12. IN CORE MOVABLE FLUX MAPPING SYSTEM
- 13. UNIT 2 RMS
- 14. UNIT 2 MAIN CONTROL BOARD 11
- 15. OPERATORCONSOLEA
- 16. OPERATOR CONSOLE B 7 17. SUPERVISOR CONSOLE C
- 18. EMERGENCY PLANNING CONSOLE I
- 19. QUIET ROOM WORKSTATION
- 20. QUIET ROOM 6
16 15 18 14 17 20 19 17 15 16 4 Amendment 100 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AREA DESIGNATION "AT THE CONTROLS" 05-27-2004 FIGURE 13.5-1 A B c D E G H fsOOOOOl.dgn
CHAIRMAN I I OPERATIONS ENGINEERING WESTINGHOUSE (NOTE 1) (NOTE 2) NOTE 1: Design, testing, and technical support functions. NOTE 2: For all matters concerning initial startup testing performed on the NSSS and associated auxiHary systems. AMENDMENT 83 DECEMBER 13, 1991 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TEST REVEW GROUP FIGURE 14.2-1
CHAIRMAN I I I I NUCLEAR OPERATIONS ENGINEERING WESTINGHOUSE STARTUP OVERVIEW NOTE 1 NOTE 2 NOTE 1: Design and technical support functions. NOTE 2: For all matters concerning preoperational testing performed on the NSSS and COMANCHE PEAK S. E.S. associated auxiliary systems. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 87 JOINT TEST GROUP DECEMBER 18, 1992 FIGURE 14.2-2
Figure 14.2-3 PREOPERATIONAL TEST SCHEDCLE r RCS Cold Hot Hydrostatic Con tainmc..!:: Functional Fuel Initial 50% 100%
);1 Test Test Test Load Criticality Power Power I I SPrepar~ Procedures ) Begin Testing
(-15 months) (-10 months) I (-4 months) (-2 months) (0 months) I Demineralized and Reactor Makeup Water - - - - - - - - - - - - - - - - - - . . . . . { Pressurizer Safety and Relief Valves- - - - - - - - - Steam Generator Safety and Relief Valves- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Main Steam and Feedwater Isolation Valves - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . Residual Heat Removal System - - - - - - - - - - - - ------------(1--------------- Safety Injection System - - - - - - - - - - - - - - -----------ir-Au.xiliary, Fuel, and Safeguards Building Ventilation - - - -------------------i0~-----~01-------....,** 0 - Partial completion of system Containment Ventilation - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- test.
Combustible Gas Control System - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- Containment Isolation System-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Integrated Engineered Safety Features Test - - - - - - - - - - - - - - - - - Control Room V e n t i l a t i o n - - - - - - - - - - - - - * - System test completed. Auxiliary Feedwater System- - - - - - - - - - - - - --------------------------<...:)--------- Electrical Area And Battery Room V e n t i l a t i o n - - - - - - - - - - - - - - - - ( ) - - - - - - - - - - - - - - ( Diesel Generator Ventilation- - - - - - - - - - - - - 1-------* DC Power S y s t e m - - - - - - - - - - - - - - - - --------------~o~---------~o~----------~or------------~* AC Power Distribution System - - - - - - - - - - - - -------------------<~---------~or----------~o~------------* Diesel Generators - - - - - - - - - - - - - - - - --------------------------<">-------... Instrument and Control Power Supply - - - - - - - - - - -----------ll-------{ )-------Or--------** Communication Systems - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Emergency Lighting System - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - * =~~E~meNoc~rin&r~~~oo-------------------------------------------~ Seismic Instrumentation - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -.. Reactor Protection S y s t e m - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - { } - - - - - - - - - Radiation Monitoring Systems - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Fire Protection System- - - - -- - -- - - ---- ----------------------------------- F~lHand~ga~VesselSmvkingE~~me~----------------~~------------~~------* Service Water System - - - - - - - - - - - - - - --------------------(.0)--------- Amendment 88 Component Cooling Water System- - - - - - -- - - *-- ------------------0._________ APRIL 16, 1993 Waste Processing Systems - - - - - - - - - - - - - --------------------------0....._------* Contaimnent Spray System - - - - - - - - - - ------------------0--------------..* Chemical and Vol~e Control System- - - - - - - - - - -----------<~-------------~ Vents And Drains--~------------------------~----------------~-~-~~* COMANCHE PEAK S.E.S. Process Sampling System- - - - - - - - - - - - - - ---------------------------cJ--------- FINAL SAFETY ANALYSIS REPORT g:~~:~g f Spent Fuel Pool Cooling and Cleanup System- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- UNITS 1 and 2
~ronRec~~S~tem----------------~-----------------------~~------*
Q423.171 PREOPERATIONAL TEST SCHEDULE Reactor Control System- - - - - - - - - - -- - - ------------
- F~URE 14.2-3 (Sheet 1 of 2)
Figure 14.2-3 PREOPERATIONAL TEST SCHEDULE RCS Cold f-~ot Hydrostatic Containment Functi ona 1 Fuel Initial 50% 100% Test Test Test Load Criticality Power Power s Prepare Procedures ,.,. Cegi n Testing ~~ I I I I I I I (-18 months) (-10 months) (-4 filonths) (-2 months) (0 months) Boron Injection Tank ... deleted from the CPSES design Computer System--------------------------- --------------------------------------------~o~----------~8* Incore Thermocouples ----------------------- o,___________,** Operational Vibration Tests -------------------------------------------*----------4~----------------------~ Containment Local Leak Rate Tests - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Containment Integrated Leak Rate Tests ________ ,___ ---**-**---*------ *---**- . **----------- o - Partial completion of system test. 8- System test completed. AMENDMENT 87 DECEMBER 18, 1992 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 PREOPERATIONAL TEST SCHEDULE FIGURE 14.2-3 (Sheet 2 of 2T
FIGURE 14.2-4A INITIAL STARTUP TEST SCHEDULE (Unit 1) FUEL PRIOR '1'0 INITIAL POif&R ASCII:NSI elf LOAD CRITICALITY LOW POMER 'l.'EST 0\ 10\ 20\ 30\ (0\ 50\ 60\ 70\ 80\ 90\ 100\
- - - - - - - - - - _ _ _ _ _ _ _ _ _ 1_ _ 1_ _ 1_ _ , _ _ 1_ _ , _ _ 1_ _ 1_ _ 1_ _ 1_ _
I Caa.ercial Operation o423.1o 1 ------------X I Approx. 5 1a0ntba I fter fuel lo.d Boron Reactivity Wortha- - ---------------------X I Rod Drop Teat* - ------------X I I 0423.10 ( Autc.atic Reactor Control Sy*t- Teat- - - - - - - - - - - - - - - - - - - - - - - - - - - - -X Reaotor Coolant Flow Teat - - - - - - -----------X---------------------------------------------X-----------X I I Reactor Coolant Flow Coaatdovn- - - - - - - -----------X I I I Control Rod Drive Taata- - - - - - - - - - ------------X---------------------------------------------X I I Rod Poaition Indicator*- - - - - - ------------X I I I Moderator Temperatura Reactivity Coefficient- --------------------X I Control Roda Reactivity Wortha- --------------------X I 0423.10 l Auxiliary Startup Inatrumantation- -X I I I cheaical Teat* - - - - - - - - -x----------x---------------------------------------------x-----------x------------x I I I Flus Diatribution Haaaurementa - - - - - - - - - - - - - - - - - -X I I I Raaote Shutdown- - - - - - - - - - - - - - - - - - - - - - - - - - - X I I Calibration of Nuclear Inatrumentation -x----------x--------------------x------------------------x-----------x------------X I I I Radiation Survey - - - - - - - - - - - - -x------------------------x------------------------x I I Procaaa and Effluent Monitoring- -----------------------------------------------------------------------X I I Cora Reactivity Balance- -----------------------------------------------------------------------X I I Loa* of Off*ite Power- - - - - - - - - - - -X Turbine Trip - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -X I Core PerfoDDADce &valuation - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -x-----------x------------x I Unit Load Tranaients- - - - -x---------x-----------x------------x I 0423.10 l Incore Nuclear Inatrumentation ------------------------X-----------------------------------X I I Reactor Coolant Leak Teat -----------X I I Amendment 88 Rod Control Syat._ Teat - -----------X I APRIL 16. 1993
------------~~--~--~--~--~~-------------------------------------------------------1 X. Teat requ.Lred to be parfoz:aed at thla powar.
FIGURE 14.2-48 NTIAL STARTUP TEST SCHEDULE (Unit 2) ron PRIOil 'l'O INI'fiAL POIRR A.SClrNSION LOAD CRI'riCALJ:rr
.LOIIf I.>OIIIUl 'ESS'r 0\ 10\ 20\ 30\ 40\ 50\ 60\ 10\ 80\ 90\ 100\
- - - - - - - - - _ _ _ _ _ _ _ _ 1__ 1__ 1__ 1__ , __ 1__ 1__ 1__ 1__ 1_ _ 1 I Caa.ercial Operation 0423.10 1 Reactor Trip Sy*t-- - - -----------X I Approz. 5 - t h a I I aftar fa.! la.d Boren Reactivity Worth*- - - - - - - - ---------------------X I I Rod Drop 'raata - - - - - - - - - - - -----------X I
I I 0423.10 1 Auta.atio Reactor Control Syat. . 'raat- -- - - - - - - - - - - - - - - - - - - - - - - - - - - - -X
----------x-------------------------------------------------------x------------x I I Reactor Coolant Flow CoaatdowD- - - ----------X I I I Control Rod Drive Taata- ------------x-------------------------------------------x I I Rod Poaition Indicator*- - - ------------X I I I Mod.rator 'ra.peratura Raactivity Coefficient- - - - --------------------X I I Control Rode Raactivity Martha- - - - - - - - - - - - - --------------------x I I o423.1o 1 Auxiliary Startup Inatru.antation- -x I I I Ch.aical 'raata - - - - - - - - -x----------x---------------------------------------------x-----------x------------x I I I Fluz Diatribution tt.aaur-anta aDd - - ----------------x---------x-----------x------------x Core Parfo~oa Evaluation* I I I I
~ta Shutdown- - X I I
Calibration of Nuclear Inatruaantation - - -X----------x-------------------x------------------------X-----------x------------x I I I Radiation Survey - - - - - - - - - - - - - - -x-----------------------x------------------------x I I Cora Reactivity Balance- -----------------------------------------------------------------------x I I Loaa of Offaita Power- - - -X I I Turbin* Trip - - - - - - - - - - - - - - - - - - - - - - - - - - - - -X I
-x-----------x------------x I
0423.10 l Inoore Nuc1ear Instrum*ntation -------------------------X----------------------------------X I I I I Raactor Coolant Leak Ta*t - ------------X I I I I I Rod Control Sy*tam Te*t - - ------------X I I Amendment 88
--~-~~-~~~~--~-~~~---------------------------------------1 X. - Teat required to be parfoJ:Ilad at thia power.
April 16, 1993
610~*********************************************************************************************************************************************************************************************************************************************************** *w******************************* 1 600 590 LL' Q) ....:::lcu 1.. 580 1.. Q) c. E Q) 1- ~
!: 570 Q) 1..
0 (.) 560 550 f--. I 1860 psia I Overpower N-16 Trip Line 540+-----~----~------~----~----~----~----~----~ 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 1.30 Core Power {fraction of nominal) Comanche Peak Final Safety Analysis Report Units 1 and 2 Illustration of Overtemperature and Overpower N-16 Protection Figure 15.0-1 Amendment No. 103
CPSES/FSAR Figure 15.0-2A has been deleted 92 August 1. 1996
CPSES/FSAR Figure 15.0-28 has been deleted 92 August 1. 1996
---0a. 1.0 ..r::: t/1 co c ....0 0.9 a. 0 1- .8 0.8 Q) u r::: co u; i5 0.7 "0 Q) a. a. 0 c 0.6 Q) u r::: s e.t/1 r::: 0.5 0 0 ll. 0.4 <( (..) (..) 0:: "0 Q) 0.3 co E 0 z 0.2 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 Normalized Drop Time (Time After Drop Begins I Drop Time to Top of Dashpot) Comanche Peak Final Safety Analysis Report Units 1 and 2 Normalized RCCA Position Versus Normalized Drop Time Figure 15.0-3 Amendment No. 103
0.80 J: t:= 0
- 0.60
~ (.) cu "0 Q) (ij E 0.40 1.. 0 z 0.20 0.00 L-.. . . . . . . . .~~:::::::::::::::_.,..........,.___,...---r--.--.......--,..........,..---,----.--....,....-.,..........,_J 0.00 0.20 0.40 0.60 0.80 1.00 Rod Insertion {Fraction of Full Insertion) Comanche Peak Final Safety Analysis Report Units 1 and 2 Normalized Rod Worth Versus Fraction Inserted Figure 15.0-4 Amendment No. 103
0.9 0.8 0.7 ..c: t:: 0 ~ 0.6 ~ co Q) l:t: (.) 0.5 (.) l:t: "C Q) iii 0.4 E0 z 0.3 0.2 0.1 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 Normalized Rod Drop Time (Time After Drop Begins I Time to Top of Dashpot) Comanche Peak Final Safety Analysis Report Units 1 and 2 Normalized RCCA Bank Reactivity Worth Versus Normalized Drop Time Figure 15.0-5 Amendment No. 103
-L..L. 7 0 E u CL 6 Unacceptable +> Operation c (!) u 5 4-4- Acceptable Operation (!) u 0 4 (!) I-
- l
+> n:l 3 I-(!) CL E (!) f- 2 I-0 +> n:l I- 1 (!) "0 0
- L 0
0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Moderator Temperature Coett1c1ent AMENDMENT 84 Versus Percent of FEBRUARY 28, 1992 Rated Thermal Power FIGURE 15.0-6
ABBREVIATIONS USED: AFWS - AUXILIARY FEEDWATER SYSTEM ECCS - EMERGENCY CORE COOLING SYSTEM CVCS - CHEMICAL AND VOLUME CONTROL HL - HOT LEG SYSTEM CL - COLD LEG ESFAS - ENGINEERED SAFETY FEATURES CCWS - COMPONENT COOLING WATEi ACTUATION SYSTEM SYSTEM FW - FEEDWATER RCS - REACTOR COOLANT SYSTEM RTS - REACTOR TRIP SYSTEM SWS -SERVICE WATER SYSTEM SIS - SAFETY INJECTION SYSTEM HPI -HIGH PRESSURE INJECTION Sl - SAFETY INJECTION LPI - LOW PRESSURE INJECTION RT -REACTOR TRIP Cl -CONTAINMENT ISOLATION CS - CONTAINMENT SPRAY SG - STEAM GENERATOR NOTES: I. FOR TRIP INITIATION AND SAFETY SYSTEM ACTUATION, MULTIPLE SIGNALS ARE SHOWN BUT ONLY A SINGLE SIGNAL IS REQUIRED. THE OTHER SIGNALS ARE BACKUPS.
- 2. NO TIMING SEQUENCE IS IMPLIED BY POSITION OF VARIOUS BRANCHES.
REFER TO EVENT TIMING SEQUENCES PRESENTED IN TABULAR FORM IN PfPTINENT ACCIDENT ANALYSIS SECTION OF CHAPTER 15.0 OF THE FSAR. DIAGRAM SY~BOLS: ( ) - EVENT TITLE 0 -BRANCH POINT FOR DIFFERENT PLANT CONDITIONS I'--------'~ - SAFETY SYSTEM
- > - SAFETY ACTION fT."
\ )
-SYSTEM REQUIRED TO MEET SINGLE-FAILURE CRITERIA 1-;\ -MANUAL ACTION REQUIRED DURING SYSTEM OPERATION FEBRUARY 20, 1981
\ )
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 ABBREV lATIONS FIGURE 15.0-7
18000-7 AMENDMENT 15 FEBRUARY 20, 1981 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 EXCESSIVE HEAT Ra10VAL DUE TO FEEDWATER SYSTEMS ~1ALFUNCTION FIGURE 1 5. 0-8
18000-10 AMENDMENT 15 FEBRUARY 20, 1981 COMANCHE PEAK S.ES. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 EXCESSIVE LOAD INCREASE FIGURE 1 5 . 0- 9
COMANCHE PEAK S. E. S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2
*-------------------1 DEPRESSURIZATION OF MAIN STEAM SYSTEM AMENDMENT 78 JANUARY 15, 1990 FIGURE 15 0--l 0
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 LOSS OF EXTERNAL LOAD FIGURE l 5. 0-ll
COMANCHE PEAK S.E.S. FINAL SAFETY Ai\ii-\LYSIS REPORT UNITS 1 and 2 LOSS OF OFFSITE POWER TO STATION AUXILIARIES (BLACKOUT FIGURE
COM A NC HE PE AK S E.S. FINAL SAFETY AN,A; ISIS REPORT UNITS 1 and 2 LOSS OF NORt.W.L FEEDWATER FIGURE 1 5. 0-1 3
18000-14 COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MAJOR RUPTURE OF A MAIN FEEDWATER LINE FIGURE l 5
- 0-14
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MARCH 31, 1981 LOSS OF FORCED REACTOR COOLANT FLOW FIGURE 1 5 . 0-1 5
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 UNITS 1 and 2 00 8 FEBRUARY 20, 1981 I en 0 UNCONTROLLED ROD CLUSTER CONTROL
~SSEMBLY BANK WITHDRAWAL FIGURE 15.0-16
COMANCHE PEAK S.E.S. Fl NAL SAFETY ANALYSIS REPORT UNIT 1 AND 2 Amendment 94 DROPPED ROD CLUSTER August 1, 1996 CONTROL ASSEMBLY Fl GURE 15.0-17 TUF150170.DGN
18000-1 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 SINGLE ROD CLUSTER CONTROL ASS-EMBLY WITHDRAWAL AT FULL POWER FIGURE 15. 0-18
CPSES/FSAR FIGURE 15.0-19 THIS FIGURE HAS BEEN DELETED 1 1a AMENDMENT 78 JANUARY 15, 1990
COMANCHE PEAK SES FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 BORON DILUTION FIGURE 15.0-20
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 RUPTURE OF CONTROL ROD DRIVE MECHANIS~-1 HOUSING AMENDMENT 54 JANUARY 21, 1985 FIGURE 15. 0-21
18000-3 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 IfJADVERTENT ECCS OPERATION AT POWER FIGURE 15.0-22
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS P.U:lQRT UNITS 1 and 2 ACCIDENTAL DEPRESSURIZATION CXl OF REACTOR COOLANT SYSTEM 0 FIGURE 15. 0-2 3
~
N
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Amendment 70 Apri 1 22, 1988 STEAM GENERATOR TUBE RUPTURE FIGURE 15.0-24
COMANrHE PE AK S.E.S. FINAL SAFE: 1 Y ANALYSIS REPORT UNITS 1 and 2 LOSS OF COOLANT ACCIDENT FIGURE 15.0-25
AMENDMENT 76 MAY 1, 1989 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 eves LETDOWN LINE RUPTURE FIGURE 15. 0-26
AMENDMENT 76 MAY 1, 1989 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 GWPS GAS DECAY TANK RUPTURE FIGURE 15.0-27
FEBRUARY 20, 1981 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 FLOOR DRAIN TANK FAILURE FIGURE 15.0-28
AMENDMENT 76 MAY 1, 1989 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 FUEL HANDLING ACCIDENT IN FUEL BUILDING FIGURE 15.0-29
AMENDMENT 76 MAY 1, 1989 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT FIGURE 15.0-30
AMENDMENT 87 DECEMBER 18, 1992 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 SPENT FUEL CASK DROP ACCIDENT FIGURE 15.0-31
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
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CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
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CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.1-1A.B thru 15.1-20 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.2-1A.B thru 15.2-26A have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Flgures 15.3-1A,B thru 15.3-24 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
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CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.4-1A.B thru 15.4-30 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.5-1 thru 15.5-3 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.5-1 thru 15.5-3 have been deleted 92 August 1. 1996
CPSES/FSAR Figures 15.5-1 thru 15.5-3 have been deleted 92 August 1. 1996
Comanche Peak Unit 1 ASTRUM BELOCA Analysis Temeprature (F) ROD 1 PEAK CLADDING TEMPERATURE Elevation (ft)
- - - - - PCT Location 14oo...-----------------------......-,2 1200 1000
(]) 1.-
- 1 c 0
~ BOO :.;:.
CL 0 (]) > (]) E LLJ ~ 600 4 400 200~._~~~~~~~~._~~~~~~~~~~~-+2 0 100 200 300 400 500 Time After Break (s) 607628075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case PCT and PCT Location Figure 15.6-1 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis VESSEL SIDE BREAK FLOW 7oooo-r--------------------------. f-f- f-6oooo-soooo-U) E 4oooo-
...0
_. Q.) 0 0::: 3oooo-3= 0 l.J..._ U) U) 0 2oooo-
~
100oo-f-
~
o- ~ ~~~~--~~~~~----~~~------~~~~ I ...... ........... _.. .I.I.I.Ll. ........ r-r- r--
-10000 I I I I I I I I I I I I I I I I I I I I 0 100 200 300 400 500 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Vessel Side Break Flow Figure 15.6-2 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis PUMP SIDE BREAK FLOW 30000.,.---------------------------. 25ooo-200oo-(/) E
....0
..::::::.- 15ooo- _.Q.) 0 0::::
- =
0 LL 10ooo-(/) (/) 0
~
5ooo-o-
-5000-I-..~..-.J..-.~--~-...~..-..~..--~.-_.._-,--...~.-..~..-.J..-.~.-...-,r--~o-...~..-..~..--~.--r--~.-...~.-..~..-..l..-.j 0 50 100 150 200 250 Time After Break (s) 807828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Loop Side Break Flow Figure 15.6-3 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis Intact Loop
-----Broken Loop
,r r
I i I 1 I o.s- 1 I I 1 I I c o.s-1 0 I ~ u 0 I-I.J_ I
- a
""'0 I 0.4-: 0
....,...._..1____.1____.1____.1___,____.1___.1____.1____.1__,;----'1____.1_1'--1.____,,--1......_.__1......_1.__1.--.__1.__1.__1~1 0 50 100 150 200 250 Time After Break (s) 1211220936 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Broken and Intact Loop Pump Void Fraction Figure 15.6-4 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis VAPOR FLOW RATE IN CORE HOT ASSEMBLY CHANNEL 15 10 Cf) E
....CI 5
Q) 0 0::: 3: 0 LL.. I.... 0 0 Cl... 0
-5
-10;-~~~,_~~~~~~~-r~~~-r~~~-r~~~~
0 5 10 15 20 25 30 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Hot Assembly Top Third of Core Vapor Flow Figure 15.6-5 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis PRESSURIZER PRESSURE 2soo~-------------------------. 2ooo- ---a 15oo-
*cn0... <J.) ~
(/) (/)
~
o.... woo-soo-Q~-L~~==~~~CI~~=c~CI~~=c~ 0 50 100 150 200 250 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Pressurizer Pressure Figure 15.6-6 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis LOWER PLENUM COLLAPSED LIQUID LEVEL 10 -+-' '+--- 8 Q) Q) __J ~
- 1 cr 6
- ..::J
""'Cl Q) Cf) CL 0 0 u 4 2 o~~~~~~._._._~~~~~~~~~~~_._.~~~ 0 100 200 300 400 500 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Lower Plenum Collapsed Liquid Level Figure 15.6-7 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis VESSEL LIQUID MASS 200000 150000 E ...Cl ~ U) U) a
- 2:
100000 50000 04-~~~~~~~~~~~~~~~~~~~~~~ 0 100 200 300 400 500 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Vessel Fluid Mass Figure 15.6-8 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis INTACT LOOP 2 ACCUMULATOR MASS FLOW RATE Jooo-.---------------------------. 25oo-2ooo- ~ (J) E
....c
. : : : :., 15oo- _.(]) 0 0:::: 3:: 10oo-0 l.J..._ r.n (J) 0
~
5oo-o--
-500~~~~~~~~~~~~~~~~~~~~~~~~
0 50 100 150 200 250 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Loop 2 Accumulator Flow Figure 15.6-9 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis INTACT LOOP 2 Sl MASS FLOW RATE 1200 1000 E CL 0"'1 (I) 800
-+--'
0 0::: 3= 0 l...i.... 600 en en 0
- 2:
400 200 a~~~~~~~~~--~~~~--~~~~~~~~_, 0 50 100 150 200 250 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Loop 2 Safety Injection Flow Figure 15.6-10 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis COLLAPSED LIQUID LEVEL IN AVERAGE CHANNEL 13 10 ....__.... 8
-+-'
Q) Q) __J
~
- I cr 6
- .:J
""0 Q)
(f) a.. 0 0 (_) 4 2 o~~~~~~~~~~r-~~~_,~~~~~~~~~~ 0 100 200 300 400 500 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Core Average Channel Collapsed Liquid Level Figure 15.6-11 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis LIQUID LEVEL IN INTACT LOOP 2 DOWNCOMER 30 25 Q) ~ 20 -o cr
- ..:::J
-o
~ 15 a_
0 0 (_) 10 5 o+-~~~~~~~~~~~~~~~~~~~~~~~~ 0 50 100 150 200 250 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Loop 2 Downcomer Collapsed Liquid Level Figure 15.6-12 Amendment No. 103
PBOT/PMID Box for the Comanche Peak Units 1 and 2 BELOCA Project 0.45 I= 0.332, 0.418 0 co c.. G) 0 0.40 (,) Q) 0.310, 0.380 s::. 0
't:J
- E 0.35 E
=
0 0
.Q G) s::.
c: 0.30 G) 3: 0 c.. 0.418, 0.260 0.395, 0.240 0.20 1 - - - - - - - , - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - l 0.20 0.25 0.30 0.35 0.40 0.45 0.50 Power in the middle third of the core (PMID) PBOT = integrated power fraction in the bottom third of the core PMID =integrated power fraction in the middle third of the core Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 BELOCA Analysis Axial Power Shape Operating Space Envelope Figure 15.6-13 Amendment No. 103
Comanche Peak Unit 1 (TBX) CONTAINMENT BACKPRESSURE Verification PWTR 0 0 0 COCO PRESSURE
- - - - - PN 4 1 0 WCT PRESSURE
~,--------------------------------------------------,
'\
\
40 \
\
\
\
\
\
\
35 \
\
\
0
*u; 30
0... Q)
- J
(J) (J) ' '
~ 25 ' '
0... 20 15 104-~~~~+-~~~~+-~~~~+-~~~~~~~~~ 0 100 200 300 400 500 Time (s) 1102369412 929:941 :366255/24-Moy-07 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Lower Bound Containment Pressure Figure 15.6-14 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis Temeprature (F) ROD 1 PEAK CLADDING TEMPERATURE Elevation (ft)
- - - - - PCT Location 160o-r-----------------------..,....,2 1400 I-- I----
I
-.,_1 i r T' f - -,~,
~I I I 10
- _, I~ '"II 1 II r II I ~ 4 ~;
I 'li*~ _, l I I ~~* 1200 I
- 1:11"'
.1111 J : I II 'If
'Ill* I I I c
~ 1000
!o......
- l c 0
~ :.;::;
Cl... 0 (L) > (L) E BOO w ~ 6 600 4 400 2oo+-~~~-r~~~~~~~~~~~~~~~~-+2 0 100 200 300 400 500 Time After Break (s) Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case PCT and PCT Location Figure 15.6-15 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis VESSEL SIDE BREAK FLOW 7oooo....---------------------------. 60000 50000 ...--Cf) ........... 40000 E
....0
_. Q) 0 0:::: 30000 3= 0 LL Cf) Cf) 0 20000
~
~
10000 u~ ........ lolL .JJ*. , ~ ........~~,.,& 0
-10000 +--'-1---'-1_......__
l..........,lr--'1____.1___._1___._1---,-....__ 1........._.11____.1~__._1__._1_......__ l..........,lr--'1____.1___._1__._1---1 0 100 200 300 400 500 Time After Break (s) 17061163233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Vessel Side Break Flow Figure 15.6-16 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis PUMP SIDE BREAK FLOW 300QQ-.----------------------------, 25ooo-200QQ-U) E
...c
..::::::.- 15ooo- _..Q.) 0
~
3: 0 l.J._ 10000-U) U) 0
~
sooo-o-
-5000 -+--'--...1....-.J.....-J..........,,...........----'----I...---I....--r-.....J........L..--'--...I....--r--..__'----"----l.---.----l...---L........J.........J.........
0 50 100 150 200 250 Time After Break (s) 1706863233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop Side Break Flow Figure 15.6-17 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis Intact Loop
-----Broken Loop
,r r
I I 1 I o.a-, I I l I I c: 0.6-1 0 I (.) a l..J..._ -a I
- a I Q.4-:
o~~~~~~~~~~~~~~~~~~~~~~~~~ 0 50 100 150 200 250 Time After Break (s) 120220936 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Broken and Intact Loop Pump Void Fraction Figure 15.6-18 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis VAPOR FLOW RATE IN CORE HOT ASSEMBLY CHANNEL 15 10 en E
....0 5 (J) -+-'
0 0::: 3: 0 I..J_ 0 0 CL 0
-5
-10~~~~~~~~~~~~~~~~~~~~~~~~
0 5 10 15 20 25 30 Time After Break (s) Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Hot Assembly Top Third of Core Vapor Flow Figure 15.6-19 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis PRESSURIZER PRESSURE 2500-r---------------------------, 2ooo-
~
- J U)
U)
~
o_ 1000 soo-o~~~~~~~~~~=c~==~===c~==~==~~ 0 50 100 150 200 250 Time After Break (s) 1708883233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Pressurizer Pressure Figure 15.6-20 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis LOWER PLENUM COLLAPSED LIQUID LEVEL 10 ~
........ 8 '+-
Q) Q) _J
~
- 1 cr 6
- ...::J
""0 Q)
Cf) CL a 0 (.) 4 2 a~~~~~~~~~~~~~~~~~_._.~~~~~~ 0 100 200 300 400 500 Time After Break (s) 1706883233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Lower Plenum Collapsed Liquid Level Figure 15.6-21 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis VESSEL LIQUID MASS 200000 150000 ~ E ..0 ( f) (f) 0 ~ 100000 50000 o+-~~~~~~~~~~~~~~~~~-r~~~~ 0 100 200 300 400 500 Time After Break (s) 1706883233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Vessel Fluid Mass Figure 15.6-22 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis INTACT LOOP 2 ACCUMULATOR MASS FLOW RATE 2500-r--------------------------.., 2ooo-(!.) ~ 10oo-3: 0 LL_ en en 0 ~ soo-o-- ..
-500~~~~~r-~~~~~~~~~~~~~~~~~~
0 50 100 150 200 250 Time After Break (s) 1706863233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop 2 Accumulator Flow Figure 15.6-23 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis INTACT LOOP 2 Sl MASS FLOW RATE 1200 1000 E CL CTI Q) 800
-+-'
0 0:::
~
0 LL (/) 600 (/) 0
~
400 200 04-~~~~~~~~~~~~~~~~~~~~~~~ 0 50 100 150 200 250 Time After Break (s) 1706883233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop 2 Safety Injection Flow Figure 15.6-24 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis COLLAPSED LIQUID LEVEL IN AVERAGE CHANNEL 13 10 Q) 8 Q) __J
~
- 1 cr 6
- ...::J
""0 Q)
(/) CL 0 0 u 4 2 o~~~~~~~~~~r-~~~~r-~~~_,~~~~_, 0 100 200 300 400 500 Time After Break (s) 17061183233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Core Average Channel Collapsed Liquid Level Figure 15.6-25 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis LIQUID LEVEL IN INTACT LOOP 2 DOWNCOMER 30 25 Q) ~ 20 ~
- I c:r
- ...::J
""t:l
~ 15 a..
0 0 (_) 10 5 o+-~~~~~~~~~~~~~~~~~~~~~~~~ 0 50 100 150 200 250 Time After Break (s) 171l686323J Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop 2 Downcomer Collapsed Liquid Level Figure 15.6-26 Amendment No. 103
PBOT/PMID Box for the Comanche Peak Units 1 and 2 BELOCA Project 0.45 g 0.332, 0.418 1:0 a.
~ 0_40 0
(.)
~ 0.310, 0.380 0 £ "0
0~~~~~~~~~~~~~~-~~~~~~~~--1.~~~~~~~~~--1 E
=
0 0
.Q Q)
- 5 0_418, 0.260 0.395, 0.240 0.20 '------......-------,-------,----------------l 0.20 0.25 0.30 0.35 0.40 0.45 0.50 Power in the middle third of the core (PMID)
PBOT =integrated power fraction in the bottom third of the core PMID =integrated power fraction in the middle third of the core Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 BELOCA Analysis Axial Power Shape Operating Space Envelope Figure 15.6-27 Amendment No. 103
Comanche Peak Unit 2 (TCX) CONTAINMENT BACKPRESSURE Verification PWTR 0 0 0 COCO PRESSURE
- - - - - PN 4 1 0 WCT PRESSURE
~~----------------------------------------------~
40 35
\
\
0
*en 30 0...
20 15 104-~~~._+-~~~~~~~~~~~~~-+_._.~~~ 0 100 200 300 400 500 Time (s) 1928949020 929:943:366829/25-May-07 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Lower Bound Containment Pressure Figure 15.6-28 Amendment No. 103
CORE PRESSURE, CORE FLOW, MIXTURE LEVEL, AND FUEL ROD POWER N HISTORY O<TIME<CORE COVERED 0 L T 0 R u ....... c u T M A p COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-29 CODE INTERFACE DESCRIPTION FOR SMALL BREAK MODEL Amendment No. 103
12 10 ~ 3=
...::£ L...
Q) 3= 0 a... L... 0 Q) c:
- .:::i 4 ............................................. .
2;-~~~~~~~~~~~-r~~~-r~~~~~~~-; 0 2 4 6 8 10 12 Elevation (ft) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-30 HOT ROD AXIAL POWER SHAPE UNIT 1 AND 2 Amendment No. 103
Injecting Intact Loop Flow Rate Sp1 I I ing Broken Loop Flow Rate 2500-r--------------------------, 2000 c*en 1500 -ec...
- s en en e
a... 1000 500 o~~~~,_~~~~~~~-r~~~-r~~~~~~~~ 0 100 200 300 400 500 600 Safety Injection Flowrate (lbm/s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-31 PUMPED SAFETY INJECTION FLOW RATE, FAULTED LOOP SPILL TO RCS PRESSURE UNITS 1 AND 2 Amendment No. 103
Injecting Intact Loop Flow Rate Sp1 I I ing Broken Loop Flow Rate 2~0~--------------------------------------------~ I I I I I 2ooo- ........ : ......... : ......... : ......... : ......... : . J . ..... . I I I I I I
. . . . . I
~ 1~0- * * * * * * * * : * * * * * * * * * : * * * * * * * * * : * * * * * * * * * : * * * * * * * * * :
- I ...... .
o I
*en ,_ I c..
f- .
- 1
~ : I
- l ,_ : I en en ,_ :1
~ . . . . :I a.. 1ooo- . . . . . ............................................ *I* ...... .
. . . . : I
- I
- I
\ :I
- I
,_ :I
~o- ......... ~ ......... ~ ......... ~ ......... ~ ......... ~ I....... .
,_ . . . . :I
- I
- I
- I
- I 0 jf-~l-~ll_~l::l::l:~ll~-t*~~-;.l~-i*I-~.~~~~T~~=-~*-;;-~-~-~-;;~~~I~I-~I 0 100 200 300 400 ~0 600 Safety Injection Flowrate (lbm/s)
COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-32 PUMPED SAFETY INJECTION FLOW RATE, FAULTED LOOP SPILL TO CONTAINMENT PRESSURE UNIT 1 AND 2 Amendment No. 103
2~0~--------------------------------------------~ 2200 2000 0
- Ci5 1800 c...
~
- 1 en en
~ 1600 a...
1~0 1000t_J__L_...L_~_L_...L__J__~...L__J_=::~~~~~d 0 2000 ~00 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-33 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 2-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,-----------------------------------------------,
;:::= 28 24 22~~~~~~~~~~~~~~~~~~~~~~~~~
0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-34 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 2-INCH BREAK Amendment No. 103
660.----------------------------------------------. 640 .............................................................. . 620 'G:"
~
- 1 c 600
-+-'
Q) a.. E
~
580 560 5404-~--~~--~~--~~--~~--~~--~-L--~~~ 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-35 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 2-INCH BREAK Amendment No. 103
2500-----------------------------------------------, 2000 -e 0
- en c..
15oo
- 1 en en e
c... 1000 5004-~~~--~~~~~~--~~~~~~--~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-36 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 3-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,---------------------------------------------~ 30 .......................................................... . 28 26 Q) _3
~
- 1
-+-' 24 ....... .
X
~
22 20 18~-L~--~~~~--~~~~~~~~~~~~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-37 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 3-INCH BREAK Amendment No. 103
750.----------------------------------------------. 700 ....................... . 650 .................................... .
~
- 1
""§ 600 Q) a.. E ~ 550 ....................................... . 500 ........................................... .
~04-~~~--~~~~~--~~~~~~--~~~~~~
0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-38 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 3-INCH BREAK Amendment No. 103
1000-r-------------------------, 900 800 LL...
~
- 1
-+-' ~
700 Q) c... E Q) 1-600 500
~o;-~~~~~~~~~,_~~~~~~~~~,_~~~
500 1000 1500 2000 2500 3000 3500 ~00 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-39 CLAD TEMPERATURE TRANSIENT AT PEAK CLAD TEMPERATURE ELEVATION UNIT 1: 3-INCH BREAK Amendment No. 103
0.15E-01
~
en en Q) c
~
0.1E-01
- c
(..) 1-- Q)
*x ""'C 0
0.5E-02 0~~--~LL~~LL~~~~Lr~~Lr~-L~~-L~ 500 1000 1500 2000 2~00 3000 3500 4000 Time (sJ COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-40 MAXIMUM LOCAL ZR02 THICKNESS UNIT 1: 3-INCH BREAK Amendment No. 103
2500-----------------------------------------------, 2000 c*en 1500 -ec...
- 1 en en e
a... 1000 500 04--L~~~~~-L~--~~~-L~--~~~~~--~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-41 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 4-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32~----------------------------------------------~ 30 .......................................................... . 28 .......................................................... .
;:::=
26 Q)
~ ~
- 1
-+-' 24 . . . . . ..
X
~
22 -------------------- 18~-L~--~~~~--~~~~~~~~~~~~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-42 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 4-INCH BREAK Amendment No. 103
sooooo....-------------------------, 500000 ..c ~ E 400000 en en 0
- 2:
100000 -+---'----L---'-----'-r--.....___.___.___._----r____,----'.___..__.....__-r-__.___._----L____.'----1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-43 TOTAL REACTOR COOLANT SYSTEM MASS UNIT 1: 4-INCH BREAK Amendment No. 103
900,----------------------------------------------. 800 'G:' 700 500
~04-~~~--~~~~~--~~~~~~--~~~~~~
0 1000 2000 3000 ~0 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-44 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 4-INCH BREAK Amendment No. 103
0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-45 TOP CORE STEAM MASS FLOW RATE UNIT 1: 4-INCH BREAK Amendment No. 103
Total Break Flow Total ECCS Flow 3000~---------------------------------------------, 2500 en 2ooo E
....c <I) ~ 1500 3:
0 LL... en en c
- ?! 1000 o~~~--~~-r~--~~~~--~~~~--~~~~--~
0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-46 TOTAL BREAK FLOW AND TOTAL SAFETY INJECTION FLOW UNIT 1: 4-INCH BREAK Amendment No. 103
10~~--------------------------------------------~ 8~ -LL... I N
-+-'
I
..c
............ 6~
- 1
-+-'
CD (1,) 0 (._) (1,) en 4000 c:
~
I-
-+-'
c(1,)
- r::
2~ 0~~~~--~~~LL~-L~~~~LL~-L~~~~~ 500 1000 1500 2000 2500 3000 3500 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-47 CLAD SURFACE HEAT TRANSFER COEFFICIENT AT PEAK CLAD TEMPERATURE ELEVATION UNIT 1: 4-INCH BREAK Amendment No. 103
800,----------------------------------------------. 750 700 650 LL...
~
- 1
-+-' ~
600 Q) c... E
~
550 500 450
~04-~~~~~~~~~~~~~~~~~~~~~~~
500 1000 1500 2000 2500 3000 3500 ~0 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-48 FLUID TEMPERATURE AT PEAK CLAD TEMPERATURE ELEVATION UNIT 1: 4-INCH BREAK Amendment No. 103
1100~---------------------------------------------, 1000 900 LL... Q.) 800
- 1 c
Q.) c... E Q.) 700 t-600 500
~~~~~~~~~~~,_~~~~~~~~~,_~~~
500 1000 1500 2000 2500 3000 3500 ~0 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-49 CLAD TEMPERATURE TRANSIENT AT PEAK TEMPERATURE ELEVATION UNIT 1: 4-INCH BREAK Amendment No. 103
0.14E-01
~ :r
~
t-0.12E ~
~
~
0.1E -- t-t-
~ ~
en O.BE en Q) ~ c
....::.t:.
(.) r
- .c I-t-
Q) 0.6E *x
""'C
~
0
~
~
0.4E t-t-
~
0.2E ~ I I I I
- I I I I
- I I I I
- I I I I
- I I I I 500 1000 1500 2000 2~00 3000 3500 4000 Time (sJ COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-50 MAXIMUM LOCAL ZR02 THICKNESS UNIT 1: 4-INCH BREAK Amendment No. 103
2500-----------------------------------------------, 2000 0 1500 -e
- en c..
- 1 en en e
c... 1000 .... 04-~~~~~-L~~~~~~-L~~~~~~-L~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-51 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 6-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,-----------------------------------------------,
.,...*.~~,-.~ .*.~,...,,...*. ~.~~.,...*.~!"'f~.,...*.,.,.~,-.*.*.~
16;-~~~-.~~~--~~~--~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-52 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 6-INCH BREAK Amendment No. 103
700~--------------------------------------------~ 650 .......................................................... . 600 .......................................................... . 'G:' -550
~
- 1
~
Q) a.. E 500
~
450 .......................................................... . 400 350~~~~~~~~~~~~~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-53 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 6-INCH BREAK Amendment No. 103
2500~---------------------------------------------, 2000 0 1500
- cn a..
~
- J
(/) (/)
~
c... 1000 . o~~~~~~-L~~~~~~-L~~~~~~-L~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-54 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 8.75-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,---------------------------------------------~
;:::::::: 28 22~~~~~~~~~~~~~~~~~~~~~~
0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-55 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 8.75-INCH BREAK Amendment No. 103
7oo.----------------------------------------------. 650 .......................................................... . 600 .......................................................... . 550 'G:"
~
- 1 15
.._ 500 Q) a..
E
~
450 350 3004-~~~~~~~~~~~~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-56 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 8.75-INCH BREAK Amendment No. 103
2~-----------------------------------------------, 2200 2000 -e 0
- en c..
1800
- 1 en en e
c... 1soo 1~ 10004-~--~~--~~--~~--~~~~~~--~~--~~ 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-57 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 2-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,---------------------------------------------~ 30 .............................................................. .
;:::::::: 28 Q)
_3
~
- 1
-+-'
X
~ 26 ...... .
24 22~~~~~~~~~==~~~~==~~~~~~~~~ 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-58 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 2-INCH BREAK Amendment No. 103
660.----------------------------------------------. 640 .............................................................. . 620 'G:"
~
- 1 c 600
-+-'
Q) a.. E
~
580 560 5404-~--~~--~~--~~--~~--~~--~-L--~~~ 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-59 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 2-INCH BREAK Amendment No. 103
2500-----------------------------------------------, 2000 -e 0
- en c..
15oo
- 1 en en e
c... 1000 5004-~~~--~~~~~~--~~~~~~--~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-60 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 3-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,---------------------------------------------~ 30 .......................................................... . 26 Q) _3
~
- 1
-+-' 24 ...... .
X
~
22 ----------------- 18~-L~--~~~~--~~~~~~~~~~~~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-61 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 3-INCH BREAK Amendment No. 103
a5o.----------------------------------------------. 800 750 700 'G:"
~
- 1 15
.._ 650 Q) a..
E
~
600 550 ..................................... . 500 ........................................ .
~04-~~~--~~~~~--~~~~~~--~~~~~~
0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-62 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 3-INCH BREAK Amendment No. 103
1100-r--------------------------. ~o~~~~~~~~~~~~~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 3500 ~00 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-63 CLAD TEMPERATURE TRANSIENT AT PEAK CLAD TEMPERATURE ELEVATION UNIT 2: 3-INCH BREAK Amendment No. 103
0.5E-01-r-------------------------. 0.4E-01
~
0.3E-01 en en Q.) r:::::
~
.u ....r::::: t-Q.) ""0
- x 0.2E-01 0
0.1E-01 o~~~~~~~~~~~~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 3500 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-64 MAXIMUM LOCAL ZR02 THICKNESS UNIT 2: 3-INCH BREAK Amendment No. 103
2500-----------------------------------------------, 2000 c*en 1500 -ec...
- 1 en en e
a... 1000 ...... . 04-~~~--~~~~~~--~~~~~~--~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-65 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 4-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32~----------------------------------------------~ 30 .......................................................... . 28 -26
- =
Q) ~ 24 ...
~
- 1
-+-' X ~ 22 16~-L~--~~~~--~~~~~~~~~~~~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-66 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 4-INCH BREAK Amendment No. 103
500000-r-------------------------, 400000 ..c E -;;; 300000 en 0
- 2:
200000 100000 -+---'----L---'-----'-r--.....___.___.___._----r____,----'.___..__.....__-r-__.___._----L____.'----1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-67 TOTAL REACTOR COOLANT SYSTEM MASS UNIT 2: 4-INCH BREAK Amendment No. 103
goo.----------------------------------------------. 'G:" 700
~
- 1
-+-' ~
Q) c... E
~ 600 ....................................................... .
~04-~~~--~~~~~--~~~~~~--~~~~~~
0 1000 2000 3000 ~00 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-68 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 4-INCH BREAK Amendment No. 103
0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-69 TOP CORE STEAM MASS FLOW RATE UNIT 2: 4-INCH BREAK Amendment No. 103
Total Break Flow Total ECCS Flow 3ooo~-------------------------. 2500 en 2ooo E
....c Q) -+-'
ci2 1500 3: 0 LL... en en c
- ?! 1000 o~~~~~._~~~--~._~~~--~._~~~--~._~
0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-70 TOTAL BREAK FLOW AND TOTAL SAFETY INJECTION FLOW UNIT 2: 4-INCH BREAK Amendment No. 103
10000~--------------------------------------------~ 8000 .. . .. . .... . . 'G:" I N
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2000 .. . .. . .... . . o4-~-L~--~~~L-~~~-L~~~L-r-~~~-L~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-71 CLAD SURFACE HEAT TRANSFER COEFFIENT AT PEAK TEMPERATURE ELEVATION UNIT 2: 4-INCH BREAK Amendment No. 103
1ooo....--------------------------, 500 .......................................................... . ~04--L~~~~~-L~--~~~~~--~~~~~--L-~~ 0 1000 2000 3000 ~00 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-72 FLUID TEMPERATURE AT PEAK CLAD TEMPERATURE ELEVATION UNIT 2: 4-INCH BREAK Amendment No. 103
1~0~----------------------------------------------~ 1-1- 12oo- * * * * * * * * * * * * ~ ~ * * * * * * * * * * * * * * ~ * * * * * * * * * * * * * * ~ * * * * * * * * * * * * *
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0 0 1000 2000 3000 ~00 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-73 CLAD TEMPERATURE TRANSIENT AT PEAK CLAD TEMPERATURE ELEVATION UNIT 2: 4-INCH BREAK Amendment No. 103
0.7E-01-r-------------------------. I-I- I-I- 0.6E * * * .. * * * * * * .. 1-I- I-I- 0.5E-o1- * * * * * * * * * * * *
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I-1- O~~----~L_I,-_L_I~I~IL_L_I,-_L_I~I~I__L_I,__IL_~I~I--~1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-74 MAXIMUM LOCAL ZR02 THICKNESS UNIT 2: 4-INCH BREAK Amendment No. 103
2500-----------------------------------------------, 2000 0 1500 -e
- en c..
- 1 en en e
c... 1000 500 04-~~~~~-L~~~~~~-L~~~~~~-L~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-75 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 6-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,---------------------------------------------~
~* * *~ ~ ~* . , * * *~ !llllt ~. **~ .~ flllllt ~. **~ !""t ~ ~ * * * ~,..., ~. ~ * * *~
16~~~~~~~~-r~~~~~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-76 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 6-INCH BREAK Amendment No. 103
7oo.----------------------------------------------. 650 .......................................................... . 600 .......................................................... . 'G:" -550
~
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~
400 3504-~~~~~~~~~~~~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-77 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 6-INCH BREAK Amendment No. 103
2500-----------------------------------------------, 2000 0 1500 -e
- en c..
- 1 en en e
c... 1000 . 500 .......................................................... . 04-~~~~~-L~~~~~~-L~~~~~~-L~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-78 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 8.75-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32,---------------------------------------------~ 0 0
**************** 0.
0 ********* 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-79 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 8.75-INCH BREAK Amendment No. 103
7oo.----------------------------------------------. 650 .......................................................... . 600 .......................................................... . 550 'G:"
~
- 1 15
.._ 500 Q) a..
E
~
450 350 3004-~~~~~~~~~~~~~~~~~~~~~~~ 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-80 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 8.75-INCH BREAK Amendment No. 103
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 1 92 February 2. 1998
CPSES/FSAR APPENDIX 15A HAS BEEN DELETED 1 84 15A-1 Amendment 84 February 28, 1992
CPSES/FSAR APPENDIX 15A HAS BEEN DELETED 1 84 15A-1 Amendment 84 February 28, 1992
CPSES /FSAR Figure 17.2-3 has been deleted.
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
t COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS I ond 2 POST LOCA ACCESS ROUTE lA FIGURE 11.8.2-25
A B c 0 E F G H 3 5 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 18 FIGURE 11.8.2-26 IIB22GOOO A B c 0 E F G I H
B c 0 t E c H 2: COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE lC FIGURE 11.6.2-27 II 822 700C A B c 0 H
B c D t [ H 2 3 3 5 5 COMANCHE PEAK S£.~ FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 2 FIGURE 11.8.2-30 116230000 B c D [ r c H
A 8 c D t E f H 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 3 &4 FIGURE 11.6.2-31 11!3231000 A B c 0 E F H
A B c D E F H 3 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 5 FIGURE 11.8.2-32 118232000 8 c D E F H
B c D t E r H 5 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 6 FIGURE 118.2-33
-~ 118233100 A B c D [ c H
A B c D E H I I 2 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 1 &8 FIGURE 11.8.2-34 118234000 A B c [) E H
8 c 0 t E F G H 2 2 s COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 f ' POST LOCA ACCESS ROUTE 9 IIBZ35000 A B c 0 E F F I GURE 11.8.2-35 H
8 c D t E G H 3
).
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 10 & 11 SHEET 1 OF 2 FI CURE I 1.8.2- 36 118236000 A 8 c 0 E f H
A B c 0 E F c H 2 3 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 POST LOCA ACCESS ROUTE 10 & 11 SHEET 2 OF 2 FIGURE 11.8.2-36 116236100 A B c D E F G H
B c D t E F 0 H 5 COt.tANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 12 FIGURE 11.8.2-37 II 6237000 B c D £ F H
CPSES/FSAR FIGURE II.B.2-38 THIS FIGURE HAS BEEN DELETED Amendment 93 February 1, 1995
-I A B c D t E G H s COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 6 POST LOCA ACCESS ROUTE 14 SHEET 1 OF 3 FIGURE 11.8.2-39 118239000 A B c D 0 H I
B c D E F c H 2 2 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 6 POST LOCA ACCESS ROUTE 14 SHEET 2 OF 3 F I CURE 11.8.2-39 116239100 A B c 0 E F H
~-------------------------------------------------------------------------------------------------------------------------------1 8 c 0 E C H RM.
- RM. NO.
N< 94 CORRIDOR UlQJ 95 PERSONNEL AIR LOCK AREA 96 ELECTRICAL EQUIPMENT AREA I , 96A STAIR S-1 968 STAIR S-5 226 CORRIDOR FOR CONT. SEE FIG. 11.8.2-39 SH. 2 ZONE F -2 2 2 LEGEND
-*-*-*- VITAL ACCESS ROUTE TO DE-ENERGIZE UGTHING DURNING LOSS OF NON-SAFEGUARD VENTILATION 1\
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0 i I 94 ~*J - * - * - * - * - * - * - * - * - * - * - * - * - * - * - *-*-*-*-*-*-*-*-*-*-*-*-*~*-*-*-*-*-*-*-*-*-*-*-*-*-*- ~ 1. E *-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-DD-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-CC-*-*
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5 5 Amendment96 August 2, 1999 0 0 0 0 0 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 6 PLAN AT EL. 831'-6" POST LOCA ACCESS ROUTE 14 SHEET 3 OF 3 FIGURE 11.8.2-39 8 c 0 E F c H
B c D E G H 2 2 s COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 6 POST LOCA ACCESS ROUTE 15 SHEET 1 OF 2 FIGURE I 1.8.2-40 118240100 B c D E F G H
-r'----~~~------------J- __________:a___________L__________~c~_________J__________~D___________1t__________~[~_________J___________:F___________!__________~c~_________J__________~H----------~I_ 3 3 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 15 SHEET 2 OF 2 FIGURE 11.8.2-40 118240200 A B c D E F H
A B 0
* [ H 5
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 16 FIGURE 11.8.2-41 A B c 0 E G H
- B c 0 F' H Y
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT
- UNITS 1 and 2
~--------------------------1
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r------------A----------~------------B------------~-----------C----------~------------0------------~t------------E----------~~----------------------~-----------G------------~-----------H-----------~ 2 2 G 3 3 5 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 6 POST LOCA ACCESS ROUTE 19 SHEET 1 OF 3 FIGURE 11.8.2-42.1 l!BZ42100.DGN A B c D E G H
A a c D t G H 2 3 I I 5 5 i COUANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 6 POST LOCA ACCESS ROUTE 19 SHEET 2 OF 3 FIGURE 11.8.2-42.2 I 118242200.DGN A a 0 G
CPE COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 19 SHEET 3 OF 3 FIGURE 11.8.2-42.3 II B242300.DGN
I CPE A COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 20 FIGURE !1.8.2-42.4
CP£ COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE lA FIGURE 11.6.2-43 118243000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE lA FIGURE II.B.2*44 118244000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IB FIGURE 11.9.2-45 II 8245000
CPf. COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE IB FIGURE 11.8.2-46 II
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IC FIGURE 11.6.2-47 118247000
CPf. COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 2 FIGURE 11.6.2-50 116250000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 2 FIGURE 11.6.2-51 IIB251000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 3 AND 4 FIGURE 11.6.2-52 c _ __ _ _II_B2_5_2_0_0_0____ - - - - - - - - - - - - - - - ..,, ____________________
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 3 AND 4 FIGURE 11.6.2-53 II B253000
--~-------------------------*--------- -----------------------
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 5 FIGURE 11.8.2-54 II 8254000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 5 FIGURE 11.8.2-55 118255000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 6 FIGURE 11.8.2-56 116256000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE 6 FIGURE 11.8.2-57 118257000
CPf COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 7 AND 8 FIGURE 11.8.2-58 t
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1AND 2 POST LOCA ACCESS ROUTE 1 AND 8 FIGURE 11.62-59 118259000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 9 FIGURE 11.6.2-60 118260000
CP£ COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 9 FIGURE 11.8.2-Gl 118261000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 10 AND 11 FIGURE 11.6.2-62 118262000
CPE COMANCHE PEAK S E S FINAL SAFETY ANAL YSI S REPORT UNITS 1 AND 2 POST LOCA ACCESS ROU TE 10 AND II FIGURE ll.S.2-GJ 118263000
CM' COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE 10 At<<> II FIGURE II.B.Z-64 118264000
CPSES/FSAR FIGURE II.B.2-66 93 1 THIS FIGURE HAS BEEN DELETED Amendment 93 February 1, 1995
CPSES/FSAR FIGURE II.B.2-67 93 1 THIS FIGURE HAS BEEN DELETED Amendment 93 February 1, 1995
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE 14 FIGURE 11.8.2-68 116268000
- - - - - ------------------ --------- - - - - - --- -------- ------------------------~ CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE 14 FIGURE 11.6.2-69 118269000
CP£ COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 14 Fl GURE 11.8.2-70 II 8270000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 14 FIGURE 11.8.2-71 118271000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 14 Fl GURE I I.B.2-72 118272000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE 14 FIGURE 11.6.2-73 IIB273QOO
.-------------------------------------~--------------------------------------------------------------------------- Cf'£ COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 15A FIGURE 11.6.2-74 118274000
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE ~B FIGURE 11.8.2-75 IIB27500f21
COMANCHE PEAK S E S FINAL SAFE TY ANALYSIS REPORT UNITS I AND 2 POST LOCA A( CESS ROUTE 156 FIGURE 11.6.2-76 !IB276000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1AND 2 POST LOCA ACCESS ROUTE 58 FIGURE 11.8.2-77 IIB277000
I r-------------------------------------------------------------------------------------------------------------, CPE I I I COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 16 FIGURE 11.8.2-78 118218000
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE 17 FIGURE 11.6.2-79 118279000
(pt COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I ANO 2 POST LOCA ACCESS ROUTE 11 FIGURE 11.6.2-80 118280000
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UN! TS 1 AND 2 POST LOCA ACCESS ROUTE 19 SHEET 1 OF 4 FIGURE 11.8.2-81 II B281000.0GN
r----------A----------~---------B--------~----------C----------~---------0----------t~---------E--------~--------------------~---------G----------~---------H--------~~ 2 3 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS I and 2 6 POST LOCA ACCESS ROUTE 19 SHEET 2 OF 4 FIGURE 11.8.2-82 A B 0 E G H
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS1AND2 POST LOCA ACCESS ROUTE 19 SHEET 3 OF 4 FIGURE 11.8.2-83 I i B283000.DGN
CPE COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 19 SHEET 4 OF 4 FIGURE 11.8.2-84 II 8284000,DGN
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 20 FIGURE I!.B.2-85
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 20 FIGURE II.B.2-86
_________________________________ -:r;--------------------- w~cc 1 I I I I I I I I
-----------------------------J
__________@ :::J 1-"'-"~""- 1 I Amendment 100 FTNAL SAFETY ANALYSIS REPORT UNITS 1AND2
Refer to FSAR Figure 9.4-6 AMENDMENT 52 AUGUST 27, 1984 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 CONTAINMENT VENTILATION AND CA PASS FLOW DIAGRAM FIGURE I I. 8. 3-2
FAJ'-- ----f"" ..::. VJ*--.
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Amendment 102
INSUFFICENT FLOW TO THREE OF FOUR STEAII GENERATORS J
!~DEPENDENT TEST OR MA.INTENANCE FAILURE ASSUCIATE0 FAILURES OF TRAINS FAILURES
'----r--
TR.~H: TRAW TURBINE TRAIN OTHER OUT FOR T\IQ START TRAIN l TRAI::s SIGNALS FAIL FAIL FAILS
~0~ :T. FAIL pk Note 1
~---, ALVE PUMP FAIL J VALVES CLOSED I VALVES CLOS£0 PUMP F.~IL T~t\IN TRAIN FAILS OR TO FAILS 006 TO OR LOCKED GLOCKEO 8 HUN BLOCKED p a pb pf --~ See Sheet 5 See Sheet 4 Note 2 Note 1 Values assigned to probabilities Pa thru Pr are showf1 on Table IT.£.1.1-1. MECHArl-IC.~L FAILURE Qr'~:RCUIT AlLURE COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 pd pg ph pc ?e AFWS Simplified Fault Tree Loss of H:*edwater JANUARY 30, 1981 FIGURE II.E.l.l-2 (Sheet 1 of 5)
!NSUFF!CENT FLOW TO THREE OF FOUR STEAr1 GENERATORS I~DEPCNDE~T TEST OR NON- INDEPENDENT 1"1A I NTENANC£ FAILURE ASSOCIATED FAILURES OF TRAINS FAILURES SUPPLY NO TRA!r: TRAlN TURBINE TR,\11:
LINE OUT FOR TWO START TRAIN TEST 0~ VALVES TRA!IIS FAIL
~v SIGNALS FAIL FAilS BLOCKED FAIL pk Note 3 VALVLS TRAIN TRAIN CLOSED FAIL FAILS FAILS OR TO BLOCkrD RUr{
Note 3 Note 2 See Sheet 4 Values assigned to probabilities Pa thru Pr arc shown on Table IL£.1.1-L COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AFWS Simplified Fauit Tree loss of Offsite AC JANUARY 30, 1981 FIGURE II.E.l.l-2 (Sheet 2 of 5)
INSUFFICENT FLOI4 TO THREE OF FOUR STEAM GENERATORS NON-INDEPENDENT INDEPENDENT FAILURE FAILURE OF TURBINE TURBINE TRAIN TRAHi VALVES PUMP NO CLOSED FAIL START OR TO SIGNALS BLOCKED RUN JANUARY 30, 1981 Values assigned to probabilities Pa thru Pr See Sheet 4 are shown on Table Il.E.l.l-l. COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AtWS Simplified Fault Tree Loss of All AC P. FIGURE I.E .1. 1-2 (Sheet 3 of 5) J
VAL YES CLOSED STEM~ TRAIN 3 OF 4 CHECK LINES VALVE
/
BLOCKED I, 2 & 3 !, 2 & 4 l, 3 & 4 2, 3 & 4 BLOCKED BLOCKED BLOCKED BLOCKED Note 4 Note 4 Note li
VALVES CLOSED MOTOR TRAIN I OF 2 ur:Es cLOCKED 1 OR 3 2 OR 4 BLOCKED BLOCKED Note 6 p p n m Values assigned to probabilities Pa thru Pr are shown on Table II.E.l.l-1. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AFWS Simplified Fault Tree JANUARY 30, 1981 FIGURE ILE.Ll-2 (Sheet 5 of 5)
CONTAINMENT HIGH RANGE RADIATION MONITOR (TYP) IRE6290A (EL.917'-9") IRE6290B------~'-~-_.J (EL.910'-9")
------,.--+ - - -
¢.CONTAINMENT-~---~
-S EL. 905'-9" NOTE: UNIT 1 MONITORS SHOWN SAME FOR UN IT 2
REFERENCE:
- 1. FSAR FIG. 1.2-15 DECEMBER 10, 1982 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 CONTAINMENT HIGH RANGE RADIATION MONITOR LOCATIONS FIGURE II.F- 1
CPSES/FSAR Figure III.A.l.2-1 has been deleted 1 95 Amendment 95 February 2. 1998
A B 0 E F G H INTEGRATED ER~ COMPUTER SYSTEM 1 1 - SENSOR SIGNALS FROM ONSI 1-r~-~ - ~ ~- ~ ~~-
- ~-------------*~--
METEOROI_OGICAI DATA 2 SAFETY SYSTEM 2 S!GNf.! S f----- CONTROL t~00M 3 I 3 UN!T
--~
ERF- DAH I EOF TECHNICAL~ SUPPORT CF'JTER
~ ---~
5 5 DISPI AY Dl SPLA"
- i AMEI<<)MENT 83 DECEMBER 13, 1991 FiGURE GENERATED roR FSAR O"lL"'
BASED 0~ ORAW:NG 6 COMANCHE PEAK S.E.S. 6 FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 INTEGRA TED ERF COMPUTER SYSTEM FIGURE III.A.1.2-2 I FIG03A122.DGN A I B I c I 0 E I F I G I H .I
CPSES/FSAR Figure III.A.l.2-3 has been deleted 1 95 Amendment 95 February 2. 1998
CPSES/FSAR Figure III.A.l.2-4 has been deleted 1 95 Amendment 95 February 2. 1998
CPSES/APR Notes to Figure II.E.l.l-2 NOTE 1 - The Motor trains are identical a failure probability of 1 x 10-1 is assigned to Train Busing coupling. NOTE 2 - The Turbine Train out for test or maintainence is the most conservative case, so the failure probability is the same as Train A. NOTE 3 -Train B failure probability is the same as Train A. NOTE 4 - The probability of any three steam generators being blocked is the same as steam generators 1, 2, and 4 being blocked. NOTE 5- Since the valve alignment for each steam generator is thE' same a failure probability of 1 x 10-1 is assigned using coup-~ing. NOTE 6 - The probability of steam generator 2 being blocked is the same as that for steam generator 1. JANUARY 30, 1981}}