ML16180A428

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Comanche Peak, Units 1 and 2 - FSAR Amendment 107, Figures - Chapters 12, 13, 14, 15, 16, 17 and TMI
ML16180A428
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 02/01/2016
From:
Luminant Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16042A346 List:
References
txx-16006, CP-20160003
Download: ML16180A428 (429)


Text

{{#Wiki_filter:CPSES/FSAR DELETED FIGURE 12.1-1 I 76 AMENDMENT 76 MAY 1, 1989 < RESIN DISPOSAL TYPICAL DEMINERALIZER ARRANGEMENT -WASTE HOLDUP TANK AMENDMENT 87 DECEMBER 18, 1992 RESIN FILL PROCESS IN PROCESS OUT SPENT RESIN STORAGE TANK NITROGEN RESIN SLUICE FILTER SPENT RESIN SLUICE PUMP COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 RESIN SLUICE WATER REUSE SYSTEM FIGURE 12.3-1 120 100 c a Cl.. .... 0 s.. 41 60 :;, z 40 20 0.05 o. l 0.15 0.20 0.25 0.30 Cobalt Concentration (W/0) AMENDMENT 87 DECEMBER 18, 1992 0.35 0.40 0.45 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 CORE CRUD DEPOSITS FIGURE 12.3-2 16 14 "' 8 6 4 2 AMENDMENT 87 DECEMBER 18, 1992 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 CORE CRUD DEPOSITS FIGURE 12.3*3 I CPE A ZONE NO CD 0 0 8 G me547300.dgn A Ml-3500-01 MAXIMUM DESIGN DOSE RATE(MREM/HR) LESS THAN 0.25 LESS THAN 2.5 LESS THAN 25.0 MORE THAN 25.0 NO LIMITATION B c RADIATION ZONES DESCRIPTION AND EXPLANATION UNCONTROLLED,UNRESTRICTED ACCESS AREA NON-RADIATION PERSONNEL & VISITORS OCCUPANCY: 40 HRS/WK, 50 WKS/YR CONTROLLED,OCCUPATIONAL ACCESS AREA RADIATION WORKERS & AUTHORIZED VISITORS OCCUPANCY: MAXIMUM 40 HRS/WK, 50 WKS/YR CONTROLLED,LIMITED ACCESS AREA CONTROLLED,RESTRICTED ACCESS AREA WITH LIMITED OCCUPANCY NORMALLY EQUIPPED WITH LOCKABLE DOOR/GATE CONTROLLED,RESTRICTED ACCESS AREA,NORMALL Y INACCESSIBLE ACCESS IS VIA LOCKABLE DOOR RADIATION MONITOR SYMBOLS AND DESCRIPTIONS 0 PROCESS MONITOR 6 RL-10 D RM-80 0 AREA DETECTOR LPM LIQUID PROCESS MONITOR LRAM LOW RANGE AREA MONITOR HRAM HIGH RANGE AREA MONITOR GPM GAS PROCESS MONITOR B c D t E D E G REV DWN CHKI APVD BP BES CP-1 07-01 NOTE H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0012-02-002945-01-00 1 THESE DRAWINGS INDICATE" AS-BUILT" SHIELDING THICKNESS AND PLANT RADIATION ZONE DESIGNATIONS BASED ON DESIGN BASES RADIATION SOURCES 2 THESE DRAWINGS ARE ISSUED FOR INFORMATION ONLY ACTUAL RADIATION LEVELS AND INFORMATION PERTAINING TO ACCESS SHOULD BE OBTAINED FROM RADIATION PROTECTION GROUP 3 PLEASE REFER TO LATEST ISSUES OF STRUCTURAL AND ARCHITECTURAL DRAWINGS FOR EXACT BUILDING DETAILS AND DIMENSIONS 4 ALL ELEVATIONS ARE GIVEN TO FINISHED FLOOR LEGEND SH SHIELDING ST STRUCTURAL H.C HEAVY CONCRETE NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 & UNIT 2 GENERAL SHIELDING INFORMATION Ml-3500 G FINAL PRINT H CP-1 --"1'" I M 0i ,........ ........ µ... __. Vl µ... -::;I Si 5 "' u '" '" r:l '" "" :;i u 0 "' "' r:l "' SJ - CPE A B c N----153 8 FL. EL. 781'-7" D D 8 70 PLAN AT EL 790'-6" me547400.dgn A Ml-3500-02 B c G D G 62A EL. 780' -0" FOR CONT. SEE THIS DWG SH 03 D t 2'-6" SH E PLAN AT EL 773'-0" D PLAN AT EL 785'-6" E ICJ--== 10 62 62B 0 EL. 780'-0" G H TIIIS DRAWING CREA TED TO INCORPORATE 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 II LIMIT DURING RHR SYSTEM OPERATION REFERENCE DRAWINGs Al-0500 Sl-0600 Sl-0602 PLAN AT EL. 790'-6" RM# 153 63 64 65 66 67 68 69 70 71 72 73 74 74A ROOM NAME FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PLAN AT EL. 773'-0" 51 52 53 54 55 56A FOR ROOM NAMES 56B SEE Al-0413 SERIES 57 DRAWINGS 58 59 60 61 62 PLAN AT EL. 785' -6" 62A 62B 62C 62D 62E THRU 62H FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADlA TION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 773'-0",785'-6" & 790'-6" DWG.NO Ml-3500 02 CP-1 G FINAL PRINT H lf) I M 0i ,........ ........ µ... __. Vl µ... ::;I Si 5 "' u '" '" r:l '" "" :;i u 0 "' "' r:l "' SJ CPE A B c D t E me754600.dgn B c D E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA 2005-003364-17-00 PER SK-0004-05-003364-17-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 Al-0501 Sl-0519 Sl-0605 Sl-0618 PLAN ATEL. 808'-0" &812'-0" RM.# ROOM NAME 153 156A 154E 154F 154G 154H 154I 154) 154K 154L 154A 154B 154C 154D FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS 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 155A 819'-6" 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 CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 808'-0" & 810'-6" Ml-3500 04 CP-2 G FINAL PRINT H CPE A B c D t E A Ml-3500-05 G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0016-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOM 98 AREA NEAR ENTRANCE TO ROOM 97 MAY EXCEED ZONE III LIMIT REFERENCE DRAWINGS Al-0502 Sl-0522 Sl-0608 Sl-0618 PLAN AT EL 831 '-6" & 832' -6" RM. # RM. NAME 155B 155C 156B 158 157 155H 155I 155) 155K 155D 155E 155F 155G 88 89 90 91 92 93 94 95A&B 96 96A 96B 99A 99B 99C 99D FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 841'-6" 97 FOR ROOM NAMES 98 SEE Al-0413 SERIES 99 DRAWINGS PARTIAL PLAN AT EL. 842'-0" 154M FOR ROOM NAMES SEE 161B Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 849'-0" 159 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 831'-6" & 832'-6" Ml-3500 05 CP-1 G FINAL PRINT H CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0017-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3SOO-Ol REFERENCE DRAWINGS Al-OS03 Sl-OS2S Sl-OS28 Sl-0611 PLAN AT EL. 8S2'-6" & EL. 860'-0" RM.# RM. NAME !SSL 163 161C lSSP !SSH !SS! lSSJ lSSK !SSL lSSM ISSN 100 lOOA THRU !OOH 101 102 103 104 !OS lOSA lOSB FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 8Sl '-6" I SSL FOR ROOM NAMES SEE 161B Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 871'-6" ISSN FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 886'-0" 161D FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 852'-6" & 860'-0" Ml-3500 06 CP-1 G FINAL PRINT H 00 I M 0i ,........ CPE A B c D t E meS47900.dgn A Ml-3500-07 B c D E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0018-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3SOO-Ol REFERENCE DRAWINGS Al-OS04 Sl-OS28 Sl-OS30 Sl-0614 PLAN AT EL. 873'-0" & 880'-6" RM.# !SSL 161C,D lSSP lSSO !SSH lSSI lSSJ lSSK lSSM ISSN 106 107 108 108A THRU 108H 109A THRU 109D llOA THRU llOD RM.NAME FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 873'-6" & 880'-6" Ml-3500 07 CP-1 G FINAL PRINT H °' I M 0i ,........ ........ µ... Vl µ... __. CPE A B c D t E me548000.dgn A Ml-3500-08 B c D E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0019-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWINGS Al-0505 Sl-0617 PLAN AT EL. 905'-9" & 896'-4" RM. # ROOM NAME 161E 160B 160A 161A DOME 111 112 246A FOR ROOM NAMES SEE Sl-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 905'-9" & 896'-4" Ml-3500 08 CP-1 G FINAL PRINT H 0 ,........ I M 0i ,........ ........ µ... Vl µ... __. CPE A B c D t E me548200.dgn A Ml-3500-09 B c D E G NOTES H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0020-02-002945-01-00 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0506 NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 & UNIT 2 ROOF PLAN Ml-3500 09 G FINAL PRINT H ,........ ,........ I M 0i ,........ ........ µ... Vl µ... _. CP-1 I CPE A N me571700.dgn A Ml-3500-10 D D D D B B D D 180 0 FL. EL. 790'-6" D FL. EL. 778' -0" c 0 0 0 [ D PLAN AT EL 778'-0" & 790'-6" c FL. EL. 785'-6" D D D D D D D D D 115 Jc:J L CTCD=1 D '------__Jc D t E 130 E [tjj 118 D D 119 D D D D 122 120 D D 121 D D D D D D 123 124 127 PARTIAL PLAN AT EL 792'-0" ALL AREAS RADIATION ZONE G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA 2000-003261-02-00 PER SK-0067-00-003261-02-00 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 130 162 163 164 165 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 181 181A 181B 182 184 185 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 792'-0" RM.# RM. NAME 116 117 118 119 120 121 122 123 124 125 126 127 128 129 130 131 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY & ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL 778' -0" & 790' -6" DWG.NO Ml-3500 10 CP-2 G FINAL PRINT H CPE A B c D t E me548100.dgn A Ml-3500-11 B c D E G H TIIIS DRAWING CREATED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0021-02-002945-01-00 NOTES FOR LEGEND,ABBREVIATIONS,RADIATION 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 188 189 190 191 192 193 194 195 196 197 198 199 200 201 202 203 204 205 206 207 207A 207B 255 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 822'-0" } FOR ROOM NAMES 208 SEE Al-0413 SERIES 209 DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY & ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL 807'-0" & 810'-6" Ml-3500 11 G FINAL PRINT H M ,........ I M 0i ,........ ........ µ... _. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE A B c D t E me548300.dgn B c D E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0022-02-002945-01-00

1. FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01
2. 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.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 214 DRAWINGS 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 148C 148D 149 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY

& ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL 830' -0" & 831 '-6" Ml-3500 12 G FINAL PRINT H "1'" ,........ I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE A N d D me548500.dgn A Q CD 136 D D D EL 852'-6" EL 842'-6" EL 830'-0" EL 852'-6" EL 840'-6" EL 830'-0" I Ml-3500-13 B 137 CD 9 Bi CD 148B CD 147 CD 149A CD 142 B c B 1 CD 135 139 141 CD CD 140 142 B ENLARGED PLAN AT EL 830' -0" 9 Bi -T CD --I CD l SECTION A-A FIG. 12 AND 13 T CD 148 SECTIONB-B FIG. 12 AND 13 c D t E A 1 146 144 CD CD CD D A 9 Bi L r 135 226 I r CD 135 226 D E 147 D D D G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0023-02-002945-01-00 NOTES FOR LEGEND,ABBREVIATIONS,RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWINGS: Al-0513 S-0721 Plan at EL. 830'-0" RM. # RM. NAME 135 136 137 138 139 140 141 142 143 144 145 146 147 148 148B 149A 226 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT ELECTRICAL CONTROL BUILDING PLAN AT EL 830'-0" & SECTIONS Ml-3500 13 G FINAL PRINT H CP-1 CPE A N 233A me548400.dgn A Ml-3500j4 B 228A TIIRU 2280 SEE TABLEZONEF-1 2'-0"SLAB,SH ABOVE & BELOW 231A TIIRU231H SEE TABLEZONEF-1 B c 230 G PLAN AT EL 842'-0" c 228H TIIRU 228N SEETABLEZONEF-1 2'-0"SLAB,SH ABOVE & BELOW 231J TIIRU 231Q SEETABLEZONEF-1 PIPE CHASE EL. 844'-6" D D t 233A E DEMINERALIZER CUBICLES SHIELD WALL THICKNESSES RM.NO NORTH EAST SOUTH WEST WALL WALL WALL WALL 228A 3'-0" 2'-0" 2'-0" 3'-0" 228B 2'-0" 2'-0" 2'-0" 3'-0" 228C 2'-0" 2'-0" 2'-0" 3'-0" 228D 2'-0" 2'-0" 2'-0" 3'-0" 228E 2'-0" 2'-0" 2'-0" 3'-0" 228F 2'-0" 2'-0" 2'-0" 3'-0" 228G 2'-0" 2'-0" 2'-0" 2'-6" 228H 2'-0" 2'-0" 2'-0" 2'-6" 228) 2'-0" 2'-0" 2'-0" 3'-0" 228K 2'-0" 2'-0" 2'-0" 3'-0" 228L 2'-0" 2'-0" 2'-0" 2'-0" 228M 2'-0" 2'-0" 2'-0" 3'-0" 228N 2'-0" 2'-0" 3'-0" 3'-0" 231A 2'-9" 3'-0" 2'-0" 3'-0" 231B 2'-0" 3'-0" 2'-0" 3'-0" 231C 2'-0" 3'-0" 2'-0" 3'-0" 231D 2'-0" 3'-0" 2'-0" 3'-0" 231E 2'-0" 3'-0" 2'-0" 3'-0" 231F 2'-0" 3'-0" 2'-0" 3'-0" 231G 2'-0" 3'-0" 2'-0" 3'-0" 231H 2'-0" 3'-0" 2'-0" 3'-0" 231J 2'-3" 3'-0" 2'-0" 3'-0" 231K 2'-0" 3'-0" 2'-0" 3'-0" 231L 2'-0" 3'-0" 2'-0" 3'-0" 231M 2'-0" 3'-0" 2'-0" 3'-0" 231N 2'-0" 3'-0" 2'-0" 3'-0" 231P 2'-0" 3'-0" 2'-0" 3'-0" 231Q 2'-0" 3'-0" 2'-9" 3'-0" NOTE: ALL DEMINERALIZER CUBICLES ARE RADIATION ZONE E SLAB ABOVE &BELOW 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-9" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-9" 2'-2" 2'-9" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" 2'-2" G G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0024-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCEDRAWINGS Al-0511 S-0725 PLAN AT EL. 842'-0" RM.# RM. NAME 207A 219A 227 227A 228A THRU 228N 230 231A THRU 231Q 232 233 233A FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY BUILDING PLAN AT EL 842'-0" Ml-3500 14 G FINAL PRINT H CP-1 CPE N A ROOF PARTIAL PLAN AT EL. 873'-4" me548600.dgn A Ml-3500-15 u D D D D D 0 D X-RE-5895B GPM X-RE-5895A GPM ROOF EL 854'-2" B 2'-0" SH D D @ D D FL. EL 151B (I) B D D v TYP c 234 0 D 235 (III) D 234 @ 239 2'-0"SLAB,SH 241 (II) FL. EL. 852'-6" (I) 151 D oo PLAN AT EL. 852'-6" & 854'-4" c D D ..., @ CD Si Si 0D Si Si FL. EL 854'-4" 151A (I) D D D D @) D D D D GPM X-RE-5896B GPM ROOF EL 854'-2" D u t E 2'-4" ..., X-RE 5250 GPM Si G PARTIAL PLAN AT EL. 862' -6" E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0025-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0510 S-0728 S-0707 PLAN AT EL. 852'-6" & 854'-4" RM.# RM.NAME 150 150A 151 151A 151B 152 152A 234 FOR ROOM NAMES 235 SEE Al-0413 SERIES 238A DRAWINGS THRU 238E 239 240A THRU 240E 241 242 PARTIAL PLAN AT EL. 862'-6" 243 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADlA TION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY & ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL. 852' -6" & 854' -6" DWG.NO Ml-3500 15 G FINAL PRINT H 'Cl ,........ I M 0i ,........ I __. µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE A N me548700.dgn A Ml-3500-16 X-RE-5567B GPM 2-RE-5698 GPM B B c -------------------------------------------------



, ! -*-*-*-*-*-*-*--*-*-*-**-*-*-*-*-*-

i PARTIAL PLAN AT EL 886'-6" D GPM (NOTE 2) 2'-3" SLAB X-RE-5702 GPM t TIO rr U (ii,) 0 n tTn° ............. . l '-9" SLAB,SH

  • -*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*-*J i = = = D D p D 'I II ! I PLAN AT EL 873'-6" c 2'-3" SLAB,SH D ROOF EL 873'-4" D E 0 E X-RE-5567A GPM l-RE-5698 GPM G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-02945-01-00 PER SK-0026-02-002945-01-00 NOTES (1) FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 (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: Al-0511 Al-0506 S-0735 S-0741 PLAN AT EL. 873'-6" Rm.# 244 } FOR ROOM NAMES 245 SEE Al-0413 SERIES 246C DRAWINGS PARTIAL PLAN AT EL. 886'-6" 246 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY

& ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL 873'-6" & 886'-6" Ml-3500 16 G FINAL PRINT H I:'--,........ I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE A B c D t E A Ml-3500-17 G H TIIIS DRAWING REVISED TO INCORPORATE 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 PLAN AT EL. 810'-6" RM.# RM. NAME 247 247A 248 249 249A 249B 250 250A 250B 251 252 253 254 255 256 257 257A 258 259 260 262 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 825'-2" 254 261 262 } FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS AND 822'-6" NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT FUEL BUILDING PLAN AT EL 810'-6",822'-6" & 802'-0" Ml-3500 17 G FINAL PRINT H 00 ,........ I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE A B c D t E me548900.dgn A Ml-3500-18 B c D E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0028-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 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 264 265 266 267 268 269 270 270A 271 271A 271B FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT FUEL BUILDING PLAN AT EL 838'-9" & 841'-0" Ml-3500 18 G FINAL PRINT H CP-1 CPE N me549000.dgn A X-RE-6273 LRAM A Ml-3500-19 8 NOTE3 B B X-RE-6272 LRAM D c 212 GD PLAN AT EL 860'-0" c ROOF 272A GD X-RE-6274 LRAM NOTE3 D D t E 273 2'-6" SLAB ROOF PARTIAL PLAN AT EL 899'-6" E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0029-02-002945-01-00 NOTES 1 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 II AREA REFERENCE DRAWING: Al-0522 S-0806 S-0809 PLAN AT EL. 860'-0" RM.# 272 272A 272B RM.NAME } FORROOMNAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 899'-6" 273 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT FUEL BUILDING PLAN AT EL 860'-0" & 899'-6" Ml-3500 19 G FINAL PRINT H 0 N I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 N 1 DOORS ADMINISTRATIVELY CLOSED WHEN REQUIRED FOR RCA BOUNDARY I I I I me600300dgn A Ml-3500-23 ffi LOCATION B (APPROX) MOVABLE RCA BOUNDARY Ut ffi (I) UN ffi ffi v PLAN AT EL 810'-6" t (I) SWITCHGEAR ROOM ROOF PLAN AT EL 833'-10" FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES, SEE DRAWING Ml-3500-01 NON-SAFETY TXU POWER CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT-UNIT 1 TURBINE BUILDING PLAN AT EL. 810'-6" & 833'-0" Ml-3500 23 FINAL PRINT c::1 "" µ;:i 0 t;:: -< -r/J µ.. CP-2 I CPE A B c D t E G H REV DWN CHKI APVD REMARKS CP-1 BP RG TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0030-02-002945-01-00 --PLANT -----NoiT'H"-- NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 I l-RE-5100 REFERENCE DRAWING: Al-0408 LPM I I I PLAN AT EL. 755'-4" 1' \ 1-001 ____r RM.# RM.NAME - CD 1-001 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS b LJ V1 r---G3 G3 5' ,........ ...j """' c:: ,........ "'"' "'"' N UP----------I ll 1111111 UP M 0i ,........ FL. EL. 755'-3" m D fl___ D I _o D iD I ........ I A' µ... m Vl µ... -w I Kl IJ I Kl IJ ""-' ::;I Si 5 "' u '" ""-' '" r:l '" -< UP1n1J1r :;i u D 0 D "' "' r:l "' D D SJ -NON-SAFETY LUMINANT PART-PLAN AT EL 755'-4" CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT TURBINE BUILDING PLAN AT EL 755'-4" DWG.NO I SI2oo I REV Ml-3500 CP-1 me549100.dgn A Ml-3500-20 B c D E G FINAL PRINT H I CPE A B c 2-282C ;; 2-282A DD FOR CONT SEE M2-3500-09 me549200.dgn A Ml-3500-21 B c D t D 1-007 1-006 PIPE ID I TRENCH () () DD J J J 1-005 Oo l-007A 0 0 filgj D= DODO D D 00 lll:d lllt:ll I llw lllt:ll t [Q] [Q] t l-007C PLAN AT EL 778'-0" TURBINE BUILDING BASEMENT FLOOR PLAN D ' E l-007D l-007B CD D [IIJ D D D E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0031-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0413-01 PLAN AT EL. 778'-0" RM.# RM. NAME 1-005 1-006 1-007 1-007 A FOR ROOM NAMES l-007B SEE Al-0413 SERIES l-007C DRAWINGS l-007D l-007E 2-282A 2-282C NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 1 TURBINE BUILDING PLAN AT EL 778'-0" Ml-3500 21 G FINAL PRINT H ,........ N I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE A B c D N 1 CD 287 lfi H lfi lfi d h 42A q µ G lfi 42 (!) 39 G 38 lfi G PLAN AT EL 810'-6" me547200.dgn A M2-3500-l l B c D t E E SWITCHGEAR ROOM ROOF PLAN AT EL 833'-10" G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0011-02-002945-01-00 NOTES 1 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: A2-0403 PLAN AT EL. 810'-6" Rm.# RM. NAME 38 39 39A 39B 39C 42 42A 287 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT-UNIT 2 TURBINE BUILDING PLAN AT EL 810'-6" & 833'-0" M2-3500 11 G FINAL PRINT H N N I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 I CPE A B c D t E G H REV DWN CHKI APVD REMARKS CP-1 BP RG TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0008-02-002945-01-00 c----_ PLANT -----NoiT'H"-- NOTES FOR LEGEND,ABBREVIATIONS,RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 2-RE-5100 I REFERENCE DRAWING: Al-0408 LPM I I I 2-001 I t PLAN AT EL. 755' -4" II ___ RM.# RM.NAME 2-001 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS d LJ 772'-0" -------'-m'-6" FL. EL ,........ FL.EL 0i ----------UP N UP 1111111f11 (l I M 0i ,........ FL. EL. 755'-3" CD m D o_ I D ____fl c i§i!k I: D1 ........ µ... m Vl µ... -(I In I r1 In I ""-' ::;I Si 5 "' u '" ""-' '" r:l '" -<

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l "' D D SJ -NON-SAFETY LUMINANT PART-PLAN AT EL 755'-4" CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 2 TURBINE BUILDING PLAN AT EL 755'-4" DWG.NO I Soso I REV M2-3500 CP-1 me546400.dgn A M2-35QQ-Q8 B c D E G FINAL PRINT H I CPE A B c 2-282B 2-282D me546600.dgn A M2-3500-09 B c D t I c=i D 2-282 CD [DJ PIPE TRENCH () () 2-281 -------------

+ D CD D D [Il] D D u u u 00 [µIll l:dll I oO t [f:lll l:dll [Q] ' [Q] 0

  • Do 2-282C CD ;2-282A DD PLAN AT EL 778'-0" TURBINE BUILDING BASEMENT FLOOR PLAN D E D D CD l-007A rn D= FOR CONT SEE Ml-3500-21 E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0009-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0413-01 PLAN AT EL. 778'-0" RM.# RM. NAME l-007A 2-281 2-282 FOR ROOM NAMES 2-282A SEE Al-0413 SERIES 2-282B DRAWINGS 2-282C 2-282D NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 2 TURBINE BUILDING PLAN AT EL 778'-0" M2-3500 09 G FINAL PRINT H N 0i N I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 I CPE A B DI 10 llll 1)1 CD !OB B l0 [: D me549300.dgn A Ml-3500-22 B c 11 CTQ]ll IL8JL8JI c D l-RE-2959 8 CD FL. EL. 803'-0" O' 6" 03'-0" & EL 81 -PLAN AT EL 8 PLAN MEZZANINE FLOOR D t E D D E 23 16 0 0 TYP A(APROX) LOCATION ABOUNDARY MOVABLE RC RY MAY BE RCA B MOVEDT NDER (Ml-3500-23)

U E CONTROLS AD MINI ST RA TIV SEE Ml-3500-23 G H REMARKS CORPORA TE DESIGN CHANGE RA WING REVISED TO PER SK-NOTES: RADIATION ZONES ABBREVIATIONS, WING Ml-3500-01 FOR LEGEND, NOTES, SEE DRA ANDGENERAL WING: Al-0401 REFERENCE DRA 803'-0" & 810'-6" PLAN ATEL Rm# RM.NAME 10 JOA !OB llA llB 11 12 13 14 15 16 17 18 19 20 21 22 23 24 27A 33 41 43A G MNAMES FOR RlO 00413 SERIES SEEA -DRAWINGS NON-SAFETY FINAL PRINT I CPE A B c D t N I D I [: IL8JL8JI 00 B FL. EL. 803'-0" 283 (I) 285A 11(1 Ill d 2-RE-2959 10 PLAN AT EL 803'-0" & MEZZANINE EL 810'-6" FLOOR PLAN me546200.dgn A M2-35QQ-1Q B c D E D D (I) 16 E 288A (I) FL. EL 810'-6" (I) 286 32 (I) 43 (I) CORRIDOR ' i i i 288B (I) ! i i i i i i i G H TIIIS DRAWING REMARKS CHANGE 00 FOR LEGEND AND GENE 'ABBREVIATION RAL NOTES SEE ZONES REFERENCE DRA WING: A2-0401 PLAN AT EL. 803' " RM.# -O & 810'-6" RM.NAME 10 16 2-32 34 35 1-36 1-37 43 283 284 285 285A 2-286 2-286A 288A 288B NON-SAFETY G CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0001-02-002945-01-00 1 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 2 ROOMS 62A AND 62B MAY EXCEED ZONE II LIMIT DURING RHR SYSTEM OPERATION REFERENCE DRAWING: A2-0500 PLAN AT EL. 790'-6" ,S2-0600 ,S2-0602 RM. # ROOM NAME I53 63 64 65 66 67 68 69 70 71 72 73 74 74A FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PLAN ATEL. 773'-0" 5I 52 53 54 55 56A 56B 57 58 59 60 61 62 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS Plan at EL. 785' -6" 62A 62B 62C 62D 62E THRU 62H FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES 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 G FINAL PRINT H N M N I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CPE A B FL.EL. 810'-6" me546800.dgn A B c REACTOR MAKE-UP 'WATER STORAGE TANK FL. EL. 810'-6" 85D GFL.EL.800'-0" ! I I I I


1 FL. EL. 810'-6" D t I I REFUELING WATER STORAGE TANK E : L ______________________________

_ ------+--------------------------------- 85D ! I I I I GFL.EL.800'-0" 1--------------------------------- 1 I I I I I I I I r------------------------------- 1 I I I I I I 85D CONDENSATE STORAGE TANK I I I I i /= G 10 FL. EL. 790'-6" PLAN ATEL 810'-6" c D E FOR CONT SEEMZ-3500-01 G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0002-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOM 85D CONTAINS SOURCES WHICH MAY EXCEED ZONE III LIMIT DURING REFUELING WATER TRANSFER REFERENCE DRAWING: A2-0500 S2-0318 PLAN AT EL. 810'-6" & BELOW Rm # ROOM NAME 70 } FOR ROOM NAMES SSD SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 810'-6" & BELOW M2-3500 02 G FINAL PRINT H M M N I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE A B c D t E A M2-3500-03 G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA 2005-003364-07-00 PER SK-0007-05-003364-07-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SE Ml-3500-01 DELETED 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 154I 154) 154K 154L 154A 154B 154C 154D FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS 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 76 SERIES PARTIAL PLAN AT EL 819'-6" 155A FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL 821 '-0" } FOR ROOM NAMES 86 SEE Al-0413 SERIES 87 DRAWINGS PARTIAL PLAN AT EL 822'-9" 155B FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT-UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLAN AT EL 808'-0" & 810'-6" M2-3500 03 G FINAL PRINT H "'1": M N I M 0i ,........ ........ µ... __. Vl µ... """' ::;I Si 5 "' u '" """' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-2 CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0004-02-002945-01-00 1 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 2 ROOM 98 AREA NEAR ENTRANCE TO ROOM 97 MAY EXCEED ZONE III LIMIT REFERENCE DRAWING: A2-0502 S2-0608 S2-0522 S2-0618 PLAN AT EL. 83I '-6" & 832' -6" RM NAME FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 84I'-6" FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 842'-0" FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 849'-0" FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL. 831'-6" & 832'-6" M2-3500 04 CP-1 G FINAL PRINT H lf) M N I M 0i ,........ ........ µ... __. Vl µ... """' ::;I Si 5 "' u '" """' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0005-02-002945-01-00 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" 100 lOOA THRU !OOH 101 102 103 104 105 RM.NAME FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 851'-6" } FOR ROOM NAMES SEEAl-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 871 '-6" FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL. 886'-0" FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 852'-6" & 860'-0" M2-3500 05 CP-1 G FINAL PRINT H 'Cl M N I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CPE A N ROOF EL. 873' -4" G me547100.dgn A M2-3500-06 G 155M 2-RE-2326 MSLM B 2-RE-2326A B c G 155N 155P X-RE-5570B WRGM 2-RE-2325 MSLM 2-RE-2328 108G 108F 0 0 2-RE-2328A 2-RE-2325A PLAN AT EL. 873'-6" c 106 G MSLM 2-RE-6259 LRAM 2-RUK-2326A/2328A 2-RUK-2325A/2327A 2-RE-2326/2328 MSLM 2-RE-2325/2327 MSLM D D EL. 897'-6" (TYP) t 155M E 155N B.O.CEL 881 '-6" 155P llOC G PLAN AT EL. 880'-6" E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0006-02-002945-01-00 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" Rm.# RM. NAME 155L 161C,D 155P 1550 155H 155I 155) 155K 155M 155N 106 FOR ROOM NAMES 107 SEE Al-0413 SERIES 108 DRAWINGS 108A THRU 108H 109A THRU 109D llOA THRU llOD LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 873'-6" & 880'-6" DWG.NO M2-3500 06 G FINAL PRINT H I:'--M N I M 0i ,........ ........ µ... __. Vl µ... ::;I Si 5 "' u '" '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 CPE N me546500.dgn A B PLAN AT CONTAINMENT DOME PLATFORM AT EL. 1000'-6" A M2-3500-07 B c 2-RE-6290A HRRM c D t ROOF EL. 896'-4" DD[ PLAN AT EL. 905'-9" & 896'-4" D E E 2-RE-6290B HRRM 2-RE-6297 HRAM FL. FL. 900'-3" G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0007-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: A2-0505 S2-0617 PLAN AT EL. 905'-9" & 896'-4" Rm # ROOM NAME 161E 160B 160A 161A DOME 111 112 246B FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT -UNIT 2 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL. 905'-9" & 896'-4" DWG.NO M2-3500 07 G FINAL PRINT H 00 M N I M 0i ,........ ........ µ... __. Vl µ... """' ::;I Si 5 "' u '" """' '" r:l '" "" :;i u 0 "' "' r:l "' SJ CP-1 UNITS 1 and 2 CCllPOllT£ -COllTAl*M£11T Pl.AN 1£1.0W fl..90IJ**,- FQJIE llLll

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"" c; ... --... -f.l!_ --: ... -::i .. , o. * / -,-::it. .. ' ,_, .. *e1--: aL.. .;.. .. ,,, .,..l!!".t..M Dli!Ao!IJ -.. 2>--Alfi ..... _:;,_, ,,,_,_ I [_. *, ' I..,: 0..*f p, ........... '-" A-! -J. COMANCHE PEAK S.E.S FNAL SAFETY ANALYSIS REPORT .UNITS 1 and 2 COMPOSITE PIP1NG AUXILIARY BUILDING P!.AN ELOW .8 '- .,...: IT\.1-fV * ... -..-F..T .... <1..5 """r DWlll> "" --c '1."'-r.. 'Al,.>Jlt <:::Lkt"IO f;-z,, : .... "' "*' * ......, * :>>..-*----'!-...... t< --.... nn "' ::.103.? ._ O'"CQ RU.*JH ,<...-1£ l.OWl SI.'£ c1t .. o'!.* COMANCHE PE AK S E S FNAL SAFETY ANALYSIS UNITS 1 and 2 AUXILIARY BUILDING PLAN AT EL.151'-*" NORTH SIDE FG.AE 12.3-ct t-!iii Pl4 .... n-n-.... 1-ol06 1-______r__:-* -....... r*** .... _.,. ,;xi ...... . ,, ****-** . I I l'.+-i--1

  • I I j ! ' --* *<>.-:i .. ot.JC> _.,!-,,. r* $t1*-*c. *---1-oa>** .._ ......

c.o* .... '"

  • --......._ '"=--..... c

...... 1 tt.?A- "*"* -:e* :s.o*.t*t f """ f ' l -*-* COMANCHE PE AK S. E S SAFETY ANALYSIS FEPalT' UNITS 1 and 2 AUXll:IAl!Y BUILDING PLAN AT EL.831'* a* SOUTH SIDE Fu.ff 12.5

  • 30

r---"-** ........ -"°I.& ... ,...,... -..... ._ ff1*1Sla*e ._ ..... .. '1'1*1*$ -4+q---M ci:.*z ,*1 *M 1. I 1 *u--- ... -,,.. **

  • *-\\'t:

t rrJ."l:J , .. .:.._1 .... '?*" :< ?'.$**1'i

l'*o* A.ff :n., 11111*01\,>*

,.oc:; & :.1t.c.J 1 o y
  • n -n
  • H . ..:1*<>1:04 .Ot c:* '"°Tft ... , 0-..<to ..... ......
  • COMANCHE PEAK S.E.S AIW. SNETY NW.YSIS UNITS 1 and 2 CONl"OSlft:

1"11'1111 AUXILIARY IUILOllll SIECTIOlll A'.lllE U!.J-JI Sii.Ct<"-*

,4 M .,.,,. ... , .. , .. "." .. ..,_"" __ ,,,, ..... ,.., .. _ , .... <i'"ll .... t .. -** , .....

,., .. ,. '\ .. .. I ____ .,.._ --;-----+ ** ,,. ---_ _JI ,...... .... l' ... i ! ""'"" ,...*""-.._ .. .. 1u,,_ .* -.,,. ......... , ..... , CO-'t1h'"-"'*.:;l \ C (.

>t;i:..t

")t-.. 1a-*ra r .... ..........

  • -** "-..._ 1.-1) COMANCHE PEAK S. E S FNAL SAFETY ANALYSIS l£l'OOT UNITS 1 and 2 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 4 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 I fsOOOOl b.dgn A B c l!..1Q"-{

SECTION 3-3 SECTION 3C-3C (AS SHOWN) SECTION 30-30 COPP. HAND) B t I c D t D E 5TEEL PLATES SECTION 3A* 3A E G H Amendment 102 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1and2 FUEL TRANSFER TUBE SHIELDING PROVISIONS FIGURE 12.3-33 SH 3 OF 3 G H CPE N me547500.dgn A A Ml-3500-03 B FOR CONT. SEE TIIISDWG,SH02 B -I I REFUELING WATER STORAGE TANK I I I I I c I I ------i----r-1 I I : I : I I I I I _I _______________________ _!_ ----_ _! I I I D FL. EL. 810'-6" t REACTOR MAKE-UP WATER STORAGE TANK I I I I I I I I I I FL.EL. 800'-0" 85D FL.EL. 800'-0" ---------------------------------1 CONDENSATE STORAGE TANK c I I I I I I I I I I I I I I I I 85D FL. EL. 810'-6" PLAN AT EL 810'-6" D E FL. EL. 810'-6" E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0014-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOM 85D CONTAINS SOURCES WHICH MAY EXCEED ZONE III LIMIT DURING REFUELING WATER TRANSFER REFERENCE DRAWINGS Al-0500 Sl-0318 PLAN AT EL. 810'-6" & BELOW RM.# 70 85D ROOM NAME } FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES UNIT 1 CONTAINMENT & SAFEGUARD BUILDING PLANS AT EL 810'-6" & BELOW Ml-3500 03 CP-1 G FINAL PRINT H ,........ lf) I M 0i ,........ ........ µ... __. Vl µ... ""' ::;I Si 5 "' u '" ""' '" r:l '" "" :;i u 0 "' "' r:l "' SJ .,, .. ,.__ .... .,.. __ _ -'+ ..... t,..>::."'£ L ' ... ... ... ... I* *1 1 " ' , . ""'" £( &Jj '<> ;;; t-wrt f<JK. , .iif_N. j Gt::"lfRAL l-01E5 _.wr: .. OIOIJ 5 -O!CfJ swrrcHGtAR &.O.::. .w1r 2 Clft -TElr' ""'"""" TzJNNEr.,,:;. - 50 _)/\,1/},.VMEVI llN!TtlV.J 2 11 J) . - "-3 -5:' ,.,, "'-" I I ,, !1 \' ... I I I , I '} : I i*

  • 1 I ..,I I QI "'"' j I COMANCHE PE AK S E S FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 CONSTRUCTION WORKER OOSE l!UILDlNG COlllPLEX LAYOUT FQJRE. 12 4-1 CPSES/FSAR FIGURE 12.5-1 HAS BEEN DELETED Amendment 87 December 18, 1992 I 87 CPSES/FSAR Figure 12. has been deleted. 83 AMENDMENT 83 DECEMBER 13, 1991 CPSES/FSAR FIGURE 12.5-3 HAS BEEN DELETED Amendment 87 December 18, 1992 I a7

-************************************************** > Decommissioning Funding Collections

  • .................................................. Energy Future Holdings Corp. Energy Future Energy Future Intermediate Competitive Holding Company Holdings Company LLC l 1 Oncor Electric Texas Competitive Delivery Holdings Electric Holdings Company LLC Company LLC I I Oncore Electric Luminant Holding Delivery Company Company LLC LLC l I l Luminant Luminant Energy Generation Company LLC Company LLC* A A Power Purchase and Sale Agreement
........................................................ . l Other Luminant Companies COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT
  • Note: Owner/Operator of CPSES UNITS 1AND2 Amendment 102 LUMINANT POWER COMPANY lSimolified Oraanization Diaaraml FIGURE 13.1-1

I Manager, Environmental Services I I I Director, Organizational Effectiveness I I Director, Nuclear Training Director, Director, Performance OE Improvement Projects Site Vice President Director, Maintenance Maintenance SMART Team Managers Maintenance Plant Support Managers Maintenance Support Group Warehouse Manager, Director, Operations Plant Manager Shift Manager, Radiation Protection Operations Operations Support. Mgr. Manager, I Nuclear -Shift Chemistry. Mgr. Ops Performance Improvement COMANCHE PEAK SES SAFETY ANALYSIS REPORT FOR DUAL UNIT OPERATIONS NUCLEAR OPERATIONS FIGURE 13.1-3 Amendment 106 ,, -I t () .,, rn ro Ci ("") c (./) :c ::0 -I z m ....... ....... c ,, )> -0 n zmZ c )::> ........ r-r--() w )::> -< :c ........ -I .0 en)> m ...... c I 0 )::> z .;:::,. 21 -'"tJ ....... Q) m -::J )> n c.. ..,, n ;::::i;;: c )::> N ;:o -I ..................

0 0 m rn z a :0 UNITED STAHS OF AMERICA NUCLEAR REGULATORY COf'MJSSION January 19, 1982 BEFORE THE ATOMIC SAFETY ANO LICE:NSING 8QARO Jn the Hatter of TEXAS UTILITIES GENERATING COMPANY, !!. ill* (Comanche Peak Steam Electric Station, Units 1 and 2) Docket Nos. 50-445 and 50-446 ST! PULA Tl ON On the basis of negotiations between Citizens for fair Utll ity Regulation

("CfUR") and Texas Utilities Generating Company,!!. tl* ("Applicants") and the representations below, CFUR hereby withdraws Contention l from litigation in this proceeding. Applicants hereby represent that they will assemble a qualified in-house technical staff prior to fuel loading for Comanche Peak and maintain that staff for the duration of plant operations. Applicants further represent that the technical staff will itself be qua1 !fled to deal with normal operations, unusual occurrences, and accident conditions, to assure that the plant can operate safely both initially and for the duration of plant operations. These representations do not, however, preclude Applicants from consulting with or retaining consultants as deemed appropriate. It 1s agreed that this Stipulation ls contingent upon Its acceptance by the NRC Staff and upon dlsmhsal of Contention 1 by the licensing Board, and shall be Incorporated In and become a part of the Final Safety Analysis Report to Comanche Peak. Citizens for Fair Utility Regulation DATE: January 19, 1982

A B c D t E 12 9 10 11 8 13 5 7 6 13 16 18 14 17 20 19 15 4 05-27-2004 A B c D E fsOOOOOl.dgn 17 G H I. UNIT 1 MAIN CONTROL BOARD 2. NOTUSED 3. NOTUSED 4. SWITCHYARD CONSOLE 5. UNIT 1 RMS 6. UNITS 1 & 2 NIS 7. HVAC PANELS 8. FIRE DETECTION PANEL & COMMON ELECTRICAL SYSTEMS PANEL 9. HVAC PANELS 10. INCORE MOVABLE FLUX MAPPING SYSTEM 11. SEISMIC RECORDER PANEL 12. INCORE MOY ABLE FLUX MAPPING SYSTEM 13. UNIT 2 RMS 14. UNIT 2 MAIN CONTROL BOARD 15. OPERATORCONSOLEA

16. OPERATOR CONSOLE B 17. SUPERVISOR CONSOLE C 18. EMERGENCY PLANNING CONSOLE 1 19. QUIET ROOM WORKSTATION
20. QUIET ROOM 15 16 Amendment 100 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1and2 AREA DESIGNATION "AT THE CONTROLS" FIGURE 13.5-1 G H I OPERATIONS CHAIRMAN I 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 auxiliary systems. AMENJM:NT 83 DECEMBER 13, 1991 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TEST REVEW GROUP FIGURE 14.2-1 I I NUCLEAR OPERATIONS OVERVIEW CHAIRMAN I ENGINEERING WESTINGHOUSE NOTE 1 NOTE 2 NOTE 1: Design and technical support functions. NOTE 2: For all matters concerning preoperatlonal testing performed on the NSSS and associated auxlUary systems. AMENDMENT 87 DECEMBER 18, 1992 I STARTUP COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JOINT TEST GROUP FIGURE 14.2-2 Figure 14. 2-3 PREOPERA TIONAL TEST SCHEDCLE RCS Cold Hot Hydrostatic Containmc:i;: Functional S Prepar: Procedures

  • ti( Be&f.n Testing >1 Test Test Test I I I (-IS months) (-10 months) (-4 months) (-2 months) 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 ------------


<

>-------------- Fuel Load t (0 months)

  • Safety Injection System ---------------

..()--------------<>-------*

Auxiliary. Fuel, and Safeguards Building Ventilation ---Containment Ventilation -------------


Combustible Gas Control System -------------------------------* Containment Isolation System------------


Integrated Engineered Safety Features Test -----------------Control Room Ve.atilation


Auxiliary Feedwater System ---------------------------------------0*-------m Electrical Area And Battery Room Ventilation----------------()--------------<

Diesel Generator Ventilation


1-------*

DC Power System----------------


10

... ------40""-------10)...-------* AC Power Distribution System ------------


<>-------0\-------......joi---------*

Diesel Generators ----------------


er-------*

Instrument and Control Power Supply -------------------.......c'.J-.-----.(').------0,__------** Communication Systems ---------------------------------------------* Emergency Lighting System ---------------------------------------------* Seismic Instrumentation --Reactor Protection System --------------


lJ-------*

Radiation Monitoring Systems ---------------------------------------------* Fire Protection System ---------------


*

Fuel Handling and Vessel Servicing Equipment -----------------u---------------<.J-------* Service Water System --------------------------------c Component Cooling Water System ---------*--------------------' 0 0 Waste Processing Systems ------------- Containment Spray System ----------0 *

  • 0 Chemical and Volume Control System ---------------------<

1-----------------

  • Vents And Process Sampling System -----------------------------------------U-------*

f Spent Fuel Pool Cooling and Cleanup System ---------r----------


Q423.17 I Boron Recycle System ----------------------------------------<J-------.ij* Reactor Control System------------------------- --Initial 50% 100% Criticality Power Power I I I

  • O -Partial completion of system test. * -System test completed.

Amendment 88 APRIL 16, 1993 COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 PREOPERATIONAL TEST SCHEDULE FIGURE 14.2-3 {Sheet 1 of 2) s Prepare Procedures ,.,

  • Be9in Testing *1 (-18 months) (-10 months) Boron Injection Tank ... deleted from the CPSES design Figure 14.2-3 PREOPERATIONAL TEST SCHEDULE RCS Cold Hydrostatic Test l (-4 months) Containment Test I Functional Test I (-2 months) Fuel Load I ( 0 months) Computer System---------------------------

Incore Thermocouples


0......---------*

Initial Criticality I 503 Power I 1003 Power I Operational Vibration Containment Local Leak Rate 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 2) FIGURE 14.2-4A INITIAL STARTUP TEST SCHEDULE (Unit 1) ro:&L PRl:OR '1'0 INITIAL Lew> CIU'J.'ICAJ.ITr LOlf PO'ltll:R DST O' 10, 20\ 30\ (0, 50\ 60\ 70\ 80\ 90\ 100\ 0423.10 I Reactor T:r:ip Sy*t----------------x c.,...reial Approx. 5 montba aft<>r fuel lo.d 0423.10 l Boron Reactivity Worth*--Aut'*'Atie Reactor Control Sy*t ... T**t--I ---------------------x


x I I I l ---x ilaaotor Coolant Flow Ta*t ------------x---------------------------------------------x-----------x I I Reactor Coolant Flow Coa*tdovn-

-- I I I -------------x---------------------------------------------x I I Rod Po*ition Indicator*-


x I I I Modiarator Temperature Reactivity Coafficiant-


x 1 Control Rode R..activity North*------I ---------------------x 0423.10 l Aurlliary Startup In*tru1Mntation--X I I I I --x----------x---------------------------------------------x-----------x------------x I I I l'lwi: Di*trihution Hlta*ur .... ant* --x I I I -x I I Cal.i.bration of Nuclear Instruaantation

---x----------x--------------------X------------------------X-----------x------------X I I I Radiation Survey - I I Proo*** ... d &ffluent Monitorinq-


x I I Core Reactivity Ba.lane*------------------------------------------------------------------------x I I Lo** of Of f*it* Pow*r--:x: I I Turbin* Trip ---------x I Core Ptrfocaane-9

&valuation


x-----------x------------x I Unit Load Tran*ient3--X---------X-----------X------------X I 0423.10 l Incor* Nuclear Inatrut11entation


x-----------------------------------X I I I I Reactor Coolant IAak Te*t -----------X I I I I I Rod Control Sy*t-Te*t -----------X I I X. -Te*t required to IMI perfaraed at thi* powe.r. Amendment 88 APRIL 16, 1993 0423.10 1 0423.10 J a42a.10 I 0423.10 l FIGURE 14.2-48 NTIAL STARTUP TEST SCHEDULE (Unit 2) mu. PIUOll 'l'O nf.tTUL POWD ASCllNSICM LOID ClUTIClU'.I'l!T LOlf POlll&ll l'SS'f o' 10' 20' 30' *o' sot 60t 1ot eot 90t 1oot ---------________ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I Cc:.motrcial.

Op<aratiOD


x I Appr0it. s -t:.ba I I attar f-1. loml Boron !lAacti.vity Worth*-------------------------x I I ------------x I I I -x !lAactor Coolant flow T**t ---------X-------------------------------------------------x------------X I I I llaactor Cool.ant i'l.ow Coaatdown-


X I I I I I Control Rod Drive Teat*------------X------------------------------------------X I I I I l1od l?o*it.ion Indicator*-


X I I I I I Moderator T...,.ratur*

a.activity Coaffici*nt-


X I I I I Control Roda Reectivity Wortha---------------------------X I I I I Awdliary Startup ---X I I I I I -x----------x--------------------------------------------x----------x------------x I I I --------------


x---------x-----------x------------x Cora Parfoz:manoa

&valuationa I I I I -------------x I I Call.brat.ion of Nucl.*ar InatrUIMlll.t&t.ion ---X----------x-----------------X------------------------X-----------x------------X ll&diation Sw:T*Y Cora Re&ativity Ba.lane*-Lo** of Offaite Power--Unit Load Tranai*nts-I I I -----------x----------------------x------------------------x I I ---------------------------------------------------------------------x I I -x I I -x I --x-----------x------------x Inoor* Nuo1.ar


X----------------------------------X I I I I I I I I a.actor Coolant X..alt T**t -----------X I I I Rod Contro1 Sy*t.... Taat ------------X I

X. T**t r*quired to b9 parfo.aaed at t:h.i* power. Amendment 88 April 16, 1993

CPSES/FSAR gure 15.0-2A has been 92 August 1. 1996 CPSES/FSAR Figure 15.0-28 has been deleted 92 August 1. 1996 ---1.0 0 a. ..c: t/I co c 0.9 ..... 0 a. 0 I-.8 0.8 Q) u c: co ti i5 0.7 1J Q) a. a. 0 ..... c 0.6 Q) u c: s t/I 8. o.5 c: 0 :;::; *;;; 0 ll.. 0.4 <( (..) (..) 0:: 1J 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 1and2 Normalized RCCA Position Versus Normalized Drop Time Figure 15.0-3 Amendment No. 103 .c: t:= 0 0.80 ;:: 0.60 *:;; :;:::; (.) cu & 'O Cl) .!::! (ij E 0.40 i.... 0 z 0.20 o.oo L ........... --=;:::::::;::::::;::::::;::::::::=:_-.--....---,..........,.---.----.---.---.--.,..........,----.----.----.-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 1and2 Normalized Rod Worth Versus Fraction Inserted Figure 15.0-4 Amendment No. 103 .c t:: 0 :,: 0.9 0.8 0.7 0.6 *:;: co Q) et: < 0.5 (.) (.) et: "C Q) .!:::! iii 0.4 E 0 z 0.3 0.2 0.1 0.0 Dash pot 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 1and2 Normalized RCCA Bank Reactivity Worth Versus Normalized Drop Time Figure 15.0-5 Amendment No. 103 L..L. 7 0 -E u CL 6 +> c (!) .,_. 5 u 4-4-(!) 0 4 u Q.J I-::::i +> 3 n:l I-Q.J c.. E Q.J 2 f-I-0 +> n:l 1 I-Q.J "O 0 :L 0 0 10 20 Unacceptable Operation Acceptable Operation 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power AMENDMENT 84 FEBRUARY 28, 1992 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Moderator Temperature Coert1c1ent Versus Percent of Rated Thermal Power FIGURE 15.0-6 ABBREVIATIONS USED: AFWS -AUXILIARY FEEDWATER SYSTEM eves -CHEMICAL AND VOLUME CONTROL SYSTEM ESFAS -ENGINEERED SAFETY FEATURES ACTUATION SYSTEM FW -FEEDWATER RTS -REACTOR TRIP SYSTEM SIS -SAFETY INJECTION SYSTEM SI -SAFETY INJECTION RT -REACTOR TRIP CS -CONTAINMENT SPRAY NOTES: ECCS -EMERGENCY CORE COOLING SYSTEM HL -HOT LEG CL -COLD LEG CCWS -COMPONENT COOLING WATEi SYSTEM RCS -REACTOR COOLANT SYSTEM SWS -SERVICE WATER SYSTEM HPI -HIGH PRESSURE INJECTION LPI -LOW PRESSURE INJECTION Cl -CONTAINMENT ISOLATION SG -STEAM GENERATOR 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 SYMBOLS: ( ) -EVENT TITLE 0 -BRANCH POINT FOR DIFFERENT PLANT CONDITIONS I '---------'I -SAFETY SYSTEM < fi" \ ) 1-;\ \ ) -) -SAFETY ACTION -SYSTEM REQUIRED TO MEET SINGLE-FAILURE CRITERIA -MANUAL ACTION REQUIRED DURING SYSTEM OPERATION FEBRUARY 20, 1981 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 ABBREVIATIONS 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 REMOVAL DUE TO FEEDWATER SYSTEMS MALFUNCTION FIGURE l 5. 0-8 18000-10 AMENDMENT 15 FEBRUARY 20, 1981 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 EXCESSIVE LOAD INCREASE FIGURE 15. 0-9 AMENDMENT 78 JANUARY 15, 1990 COMANCHE PE AK S. E. S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 *---------------- DEPRESSURIZATION OF MAIN STEAM SYSTEM FIGURE ] 5 0--1 O COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 LOSS OF EXTERNAL LOAD FIGURE 1 5 . 0-11 AMENDMENT 15 FEBRUARY 20, 1981 COMANCHE PEAK S.E.S. FINAL SAFETY Ai\il-\LYSIS REPORT UNITS 1 and 2 LOSS OF OFFSITE POWER TO STATION AUXILIARIES (BLACKOUT FIGURE AMENDMENT 15 FEBRUARY 20, 1981 COMANCHE PEAK S.E.S. FINAL SAFETY AN.A; lSIS REPORT UNITS 1 and 2 LOSS OF NORMAL FEEDWATER FIGURE 1 5. 0-1 3 18000-14 COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS t and 2 MAJOR RUPTURE OF A MAIN FEEDWATER LINE FIGURE MARCH 31, 1981 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 LOSS OF FORCED REACTOR COOLANT FLOW FIGURE 1 5 . 0-1 5 AMENDMENT 15 FEBRUARY 20, 1981 I COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 NCONTROLLEO ROD CLUSTER CONTROL SSEMBLY BANK WITHDRAWAL FIGURE 15. 0-16 TLJF150170.DGN Amendment 94 August 1, 1996 COMANCHE PEAK S.E.S. Fl NAL SAFETY ANALYSIS REPORT UNIT 1 AND 2 DROPPED ROD CLUSTER CONTROL ASSEMBLY Fl GURE 15.0-17 18000-1 AMENDMENT 15 FEBRUARY 20, 1981 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 AMENDMENT 78 JANUARY 15, 1990 I 7a AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK SES FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 BORON DILUTION FIGURE 15.0-20 AMENDMENT 54 JANUARY 21, 1985 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 RUPTURE OF CONTROL ROD DRIVE MECHANISM HOUSING FIGURE 15. 0-21 18000-3 AMENOMENT 15 FEBRUARY 20, 1981 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 HJADVERTENT ECCS OPERATION AT POWER FIGURE 15. 0-22 AMENDMENT 15 FEBRUARY 20, 1981 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS P.U:lQRT UNITS 1 and 2 ACCIDENTAL DEPRESSURIZATION OF REACTOR COOLANT SYSTEM FIGURE 15. 0-2 3 .... CXl 0 N Amendment 70 April 22, 1988 COMANCHE PEAK S.E.S. FINAL SAFE TY ANALYSIS REPORT UNITS 1 and 2 STEAM GENERATOR TUBE RUPTURE FIGURE 15. 0-24 FEBRUARY 20, 1981 COMANrHE PEAK 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 7 6 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-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR Figures 15.2-lA.B thru 15.2-26A have been del 92 August 1 . 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR F1gures 15.3-lA.B thru 15.3-24 have been deleted 92 August 1. 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996 CPSES/FSAR Figures .5-1 thru 15.5-3 have been deleted 92 August 1. CPSES/FSAR Figures .5-1 thru 15.5-3 have been deleted 92 August 1. CPSES/FSAR Figures .5-1 thru 15.5-3 have been deleted 92 August 1. Comanche Peak Unit 1 ASTRUM BELOCA Analysis Temeprature (F) ROD 1 PEAK CLADDING TEMPERATURE Elevation (ft) -----PCT Location Cl) :::::i 1400 1200 1000 _. 800 CL Cl) E 600 400 200 0 100 200 300 Time After Break (s) 607628075 400 12 4 2 500 Comanche Peak c 0 :.;:; 0 > Cl) LLI 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 70000 60000 50000 .,........._ U) ........... 40000 E ...0 ...__... Q.) _. 0 30000 0::: 3= 0 l..J..._ U) CJ') 20000 0 10000 0 -10000 _.....__.....__......._ ........... ___.___.___.___._-.--........._......__.....__..........,,..........___.___.___._.....,...._.__......._......__ ............ 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 (/) ........... E ....0 30000 25000 20000 ..::::::.- 15000 Q.) _. 0 0:::: :;= 0 LL 10000 (/) (/) 0 5000 0 PUMP SIDE BREAK FLOW -5000----...._-.__.__..__..__..__..__,,_...._...__...._..__,,........__..__..__.._-,..-_._...._....__"'""--t 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 -r I i I 1 I 0.8-I I I l I l I 0.5-I § I :.;::::; t g I I.... r l.J_ Intact Loop Broken Loop 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) 120220936 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 ....---.. en ............ E 5 ....Cl ..__... Q) ......... 0 0::: :;:: 0 u._ I.... 0 0 CL 0 > 10 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 Q.) (/) (/) PRESSURIZER PRESSURE 2500.....--------------------------. 2000-0.... 1000-500-0 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 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 :::I 6 er :..::J ""'Cl Q) Cf) C.L 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 CJ) CJ) a :::2: 100000 50000 .......... 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 en .............. E ....c 3000 2500 2000 ..:::::::, 1500 (]) _. 0 0:::: 3:: 0 l..J._ 1000 500 0 -500 0 INTACT LOOP 2 ACCUMULATOR MASS FLOW RATE 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 SI MASS FLOW RATE 1200 1000 .....--... E CL CTI ......__, 800 (I) -+--' 0 0::: 3= 0 LL.. 600 en en 0 :::2: 400 200 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 12 10 ....--8 -+-' -....__... Q) > Q) __J :::I 6 er :.:J ""C Q) Cf) a.. 0 0 (_) 4 2 100 200 300 400 500 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 Q.) > 30 25 20 -0 .:::; er :..:::J -0 15 a_ 0 0 (_) 10 5 LIQUID LEVEL IN INTACT LOOP 2 DOWNCOMER 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 I=' 0 co c.. -Cl) ... 0 (,) Q) s::. --0 't:J ... :E -E 0 = 0 .Q Cl) s::. -c: ... Cl) 3: 0 c.. 0.45 0.40 0.35 0.30 PBOT/PMID Box for the Comanche Peak Units 1and2 BELOCA Project 0.332, 0.418 0.310, 0.380 0.418, 0.260 0.395, 0.240 0.20 ---------------------------------< 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 ..--0 40 35 *u; 30 CL ..__ 20 15 '\ \ \ \ \ \ \ \ \ \ \ \ ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ..... ' ' ..... ..... 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 1600------------------------12 1400 1200 I c 1000 !...... ::l _. Cl... (L) E BOO 600 400 I --I -----.,_ 1 i r T' f - I I 1 1 111 ** I -_, '"II I II r i I I 4 lO I _, l I I : i:ll"' : I I 'If .1111 J I 'Ill* I I I 6 4 200-+-....._...._ .......... ___,.__..__..._._ ........ __ ......... ....._ ___ .........,,.........__..__..._._....,...._.__....._....._ ............... 2 0 100 200 300 400 500 Time After Break (s) c 0 :,+:::; 0 > (L) w 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 70000 60000 50000 ...--Cf) ........... 40000 E ...Cl .......__.... Q) _. 0 30000 0:::: 3= 0 LL Cf) Cf) 20000 0 ::::2: 10000 0 -10000 _....__...__ ...........


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..___.___.___.__.__-.--_.__......__......_........._.

0 100 200 300 400 500 Time After Break (s) 1706863233 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 25000 20000 ............. U) ........... E ...c ..::::::.- 15000 Q.) _.. 0 3: 0 l..J_ 10000 U) U) 0 ::::?: 5000 0 -5000 PUMP SIDE BREAK FLOW 0 50 100 150 Time After Break (s) 1706863233 200 250 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 -r I -r I 1 I a.a-, l I l I ! I Q.5-I § I :;:::; t g I LZ r I r I Q.4-1 0 0 Intact Loop Broken Loop r I I I I I I I I I I I I I I I I I I I I I I I I I 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 15 10 ,-----. en ............. E 5 ....Cl ...___... Cl) -+-' c 0::: 3: 0 LL "-0 0 CL c > 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.....----------------------------. 2000-500-0 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 :::I 6 er :...::J ""C Q) Cf) CL a 0 (.) 4 2 0----------.....-..._..._ ________ ......._. ________ __._ _________________ _ 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 250000 200000 150000 E _Q --Cf) Cf) 0 ::::::?! 100000 50000 0 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 2000 en 1500 ............ E _c ....__.... (!.) _, 1000 3: 0 LL-cn en a 500 0 -500 0 INTACT LOOP 2 ACCUMULATOR MASS FLOW RATE 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 SI MASS FLOW RATE 1400 1200 1000 ...--E CL CTI ..___.. 800 Cl) -+-' 0 0::: 0 LL 600 CJ) CJ) 0 ::::::2: 400 200 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 ,..._ 8 ......... -"--"" Q) > Q) __J :::::l 6 er :...::J ""'Cl Q) (/) CL 0 0 u 4 2 100 200 300 400 500 Time After Break (s) 1706ll83233 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 Q) > 35 30 25 20 :::I c:r :...::J ""t:l 15 0... 0 0 (_) 10 5 LIQUID LEVEL IN INTACT LOOP 2 DOWNCOMER 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 0.45 PBOT/PMID Box for the Comanche Peak Units 1and2 BELOCA Project g 0.332, 0.418 co a. -0.40 0 (.) 0.310, 0.380 --0 "O ... :c -E 0 = 0 .Q Cl> :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 CL __... CL> I... ::J CJ') CJ') 25 o_ 20 15 ' ' \ \ ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' 10---------- ....... o 100 200 300 Time (s) 400 500 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 N 0 T R u M p CORE PRESSURE, CORE FLOW, MIXTURE LEVEL, AND FUEL ROD POWER HISTORY O<TIME<CORE COVERED L 0 u c T A COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-29 CODE INTERFACE DESCRIPTION FOR SMALL BREAK MODEL Amendment No. 103 ...__... L... Q) 12 10 ........................... . 3= 8 ..... . 0 a... L... c Q) c:: :.:::i 6 .. 4 ............................................. . 2 0 2 4 6 Elevation (ft) 8 10 COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-30 HOT ROD AXIAL POWER SHAPE UNIT 1AND2 Amendment No. 103 12 Injecting Intact Loop Flow Rate Sp1 I I ing Broken Loop Flow Rate 2500....---------------------------. 2000 c 1500

  • en c.... -e ::::s en en e ' ' ' ' ' a... 1000 . I. . . . ................................................... . ' I ' ' ' ' ' 500 .. '.... . ................................................. . ' ' I I ---........ . .... ........ ..... ............................

__ ......_ ........ _._-T-....._ ......... ___._....,........_ .................................. ......_ ............... -=....._ ......... ---1 0 100 200 300 400 Safety Injection Flowrate (lbm/s) 500 600 COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-31 PUMPED SAFETY INJECTION FLOW RATE, FAULTED LOOP SPILL TO RCS PRESSURE UNITS 1AND2 Amendment No. 103 2500 Injecting Intact Loop Flow Rate Sp1 I I ing Broken Loop Flow Rate I I I I I I 2000 ********:*********:*********:*********:*********:*1******* ,_ 1500 0

  • rn c... ...__ I I I I I . . . . . I ....... : .........
.........
.........
......... : . I ...... . I . I : I : I :::::J : I rn rn : I . . . . : I a... 1000 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * **I* * * * * * * * . . . . : I : I : I : I : I : I : I 500 .................................................
i ....... . : I : I : I : I : I 0 100 200 300 400 Safety Injection Flowrate (lbm/s) 500 600 COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-32 PUMPED SAFETY INJECTION FLOW RATE, FAULTED LOOP SPILL TO CONTAINMENT PRESSURE UNIT 1AND2 Amendment No. 103

-0 2400 2200 2000 -Ci5 1800 c.... -::::I en en 1600 a... 1400 1200 ........ :-,. .......................................... . 1000 0 2000 4000 Time (s) 6000 COMANCHE PEAK 8000 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) 30 .............................................................. . Q) > -3 ::::I .......... x 26 ........ . 24 .................. . 0 2000 4000 Time (s) 6000 COMANCHE PEAK 8000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-34 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 2-INCH BREAK Amendment No. 103 'G:" -:::I -+-" c .._ Q) a.. E 640 .............................................................. . 620 600 580 560 0 2000 4000 Time (s) 6000 COMANCHE PEAK 8000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-35 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 2-INCH BREAK Amendment No. 103 -0 *en c... -2000 e 1500 ::::I en en e c.... 1000 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-36 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 3-INCH BREAK Amendment No. 103 -;:::::::: -Q) > -3 Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... . 28 26 ....... . ::::I -+-' 24 ....... . x 22 20 18 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-37 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 3-INCH BREAK Amendment No. 103 700 ....................... . 650 .................................... . :::I ""§ 600 Q) a.. E 550 ....................................... . 500 ........................................... . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-38 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 3-INCH BREAK Amendment No. 103 1000--------------------------. 900 800 -LL. -::::I -+-' 700 Q) c.... E Q) I-600 500 400-+-..........__,_.........,_._,_..........__,_,.........__._ ............. -.-............. _._ ............. _._..........__,_,.........__._ ............. -.-............. 500 1000 1500 2000 2500 Time (s) 3000 3500 4000 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 --en en Q) c: _.:::,i:. (.) :c I-Q) ""'C *x 0 0.2E-01 0.15E-01 0.1E-01 0.5E-02 0 500 1000 1500 2000 Time (sJ 3000 3500 4000 COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-40 MAXIMUM LOCAL ZR0 2 THICKNESS UNIT 1: 3-INCH BREAK Amendment No. 103 2000 c 1500 *en c.... -e ::::I en en e a... 1000 500 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-41 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 4-INCH BREAK Amendment No. 103 --Q) > Core Mixture Level Top of Core (22.0778 ft) 32 30 .......................................................... . 28 .......................................................... . 26 ::::I -+-' 24 . . . . . .. x 20 ........... . 18 0 1000 -------------------- .................................... 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-42 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 4-INCH BREAK Amendment No. 103 -E ..c sooooo-r--------------------------, 500000 400000 300000 ... 200000 .... 1 OOOOO-+-__.___.___._____._...--....___..___.___._---.-____.____.,___..__.....__....,......__.___.____..____...___. 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-43 TOTAL REACTOR COOLANT SYSTEM MASS UNIT 1: 4-INCH BREAK Amendment No. 103 800 .............. . 'G:' 700 -::::I -+-' Q) c.... E 600 ........................................................ . 500 .................... . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-44 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 4-INCH BREAK Amendment No. 103 -Cf) ............ E ....c .::::::..- Q) -+-' 0 a::: 3:: 0 LL. Cf) Cf) 0 :::::::ii: 300 200 100 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-45 TOP CORE STEAM MASS FLOW RATE UNIT 1: 4-INCH BREAK Amendment No. 103 3000 2500 <n 2000 ........... E ....c .:::::::.. <L> .......... 1500 3:: 0 LL. en en 0 :::::::?! 1000 Total Break Flow Total ECCS Flow 500 .... 0 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-46 TOTAL BREAK FLOW AND TOTAL SAFETY INJECTION FLOW UNIT 1: 4-INCH BREAK Amendment No. 103 -LL. I N -+-' -I ...... ..c ............

I -+-' CD ---<L> 0 (._) ...... <L> -en c: I--+-' c <L> :::r:: 8000 6000 4000 2000 0 500 1000 1500 2000 2500 3000 Time (s) 3500 4000 COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-47 CLAD SURFACE HEAT TRANSFER COEFFICIENT AT PEAK CLAD TEMPERATURE ELEV A TION UNIT 1: 4-INCH BREAK Amendment No. 103 750 700 650 -LL.. -::::I -+-' 600 Q) c.... E 550 500 450

........... ............. 500 1000 1500 2000 2500 3000 3500 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-48 FLUID TEMPERATURE AT PEAK CLAD TEMPERATURE ELEV A TION UNIT 1: 4-INCH BREAK Amendment No. 103 1100 1000 900 -LL. -800 <L> ...... ::::I ......... c ...... <L> CL E 700 <L> t-600 500 400 __ ........... __ ........,... __ ........... __ .,......... __ ........... ....,..... ........... __ ........,... __ ........... __ .,......... __ ........... ....,..... ........... __ ._ 500 1000 1500 2000 2500 3000 3500 4000 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 --en en Q) c: ...::.i:. (..) :.c I-Q) ""'C *x 0 0.12E-01 0.1E-01 O.BE-02 0.6E-02 0.4E-02 0.2E-02 0 500 1000 1500 2000 Time (sJ 3000 3500 4000 COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-50 MAXIMUM LOCAL ZR0 2 THICKNESS UNIT 1: 4-INCH BREAK Amendment No. 103 2000 0 1500 *en c... -e ::::I en en e a.. 1000 .... 500 ........ .......... .......... .......... ........... 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 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) 30 .......................................................... . 28 Q) > 24 .. ::::I .......... x 22 * "9 *** 20 ....... . 18 ....... . . . . . 'P9 ..... ,-***** ,..., ,... .,... !"'f .,.. ..... ,-....... . 16-+-......_.._ .......... ---T_.__.__._....._-.- ..................... _._--T"'_._....._......_.._,........___.__.__._-r-......_.._ .......... '-I 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 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 ::::I _.. Q) a.. E 500 450 .......................................................... . 400 ................................. . 350 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-53 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 6-INCH BREAK Amendment No. 103 2500 2000 c 1500 . (./) a.. -:::J (./) (./) a.. 1000 . 500 ... 0 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 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) 30 .......................................................... . -;:::::::: 28 -24 ........... . 22 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-55 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 8.75-INCH BREAK Amendment No. 103 650 .......................................................... . 600 .......................................................... . 550 'G:" -:::I 15 500 .._ Q) a.. E 450 400 ...... 350 ................ . .......... 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-56 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 8.75-INCH BREAK Amendment No. 103 -0 2200 2000 *en 1800 c... -e ::::I en en e 1soo c.... 1400 1200 ........ .. ..

!"'!' ** "'!"'. ** t._ ************************************** 0 2000 4000 Time (s) 6000 COMANCHE PEAK 8000 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) 30 .............................................................. . -;:::::::: 28 -Q) > -3 ::::I -+-' x 26 ...... . 24 22 0 2000 4000 Time (s) 6000 COMANCHE PEAK 8000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-58 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 2-INCH BREAK Amendment No. 103 'G:" -:::I -+-" c .._ Q) a.. E 640 .............................................................. . 620 600 580 560 0 2000 4000 Time (s) 6000 COMANCHE PEAK 8000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-59 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 2-INCH BREAK Amendment No. 103 -0 *en c... -2000 e 1500 ::::I en en e c.... 1000 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-60 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 3-INCH BREAK Amendment No. 103 -;:::::::: -Q) > -3 Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... . 26 ..... . ::::I -+-' 24 ...... . x ----------------- ............................... 22 20 ........... . 18 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-61 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 3-INCH BREAK Amendment No. 103 800 ....................... . 750 700 ............ . 'G:" -:::I 15 650 .._ Q) a.. E 600 550 ..................................... . 500 ........................................ . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-62 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 3-INCH BREAK Amendment No. 103 1100 1000 .... 900 .... 800 .... 700 .... 600 .... 500 .... 400----......... .....---.................


.........


.................

-..,,.._ ................... --.................


""-1 0 500 1000 1500 2000 2500 3000 3500 4000 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 0.4E-01 --0.3E-01 en en Q.) c: .u ...c: t-Q.) -0 *x 0.2E-01 0 0.1E-01 0-4--J....L..L-L.

............ 0 500 1000 1500 2000 2500 3000 3500 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-64 MAXIMUM LOCAL ZR0 2 THICKNESS UNIT 2: 3-INCH BREAK Amendment No. 103 2000 c 1500 *en c.... -e ::::I en en e a... 1000 ...... . 500 ............ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 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 Q) > 24 ... ::::I -+-' x 22 20 .......... . 18 . . . . ...... . 16 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-66 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 4-INCH BREAK Amendment No. 103 500000.........--------------------------, 400000 -E ..c -;;; 300000 en 0 ::::::!! 200000 1 OOOOO-+-__.___.___._____._....--....___..___.___._---.-____.____.,___..__.....__....,......__.___.____..____...___. 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-67 TOTAL REACTOR COOLANT SYSTEM MASS UNIT 2: 4-INCH BREAK Amendment No. 103 800 .......... . 'G:" 700 -::::I -+-' Q) c.... E 600 ....................................................... . 500 ................... . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-68 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 4-INCH BREAK Amendment No. 103 400 ... -Cf) ............ _§ 300 .::::::..- 100 ........... . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-69 TOP CORE STEAM MASS FLOW RATE UNIT 2: 4-INCH BREAK Amendment No. 103 3000 2500 en 2000 ........... E ....c -Q) -+-' ci2 1500 31:: 0 LL. en en 0 :::::::?! 1000 Total Break Flow Total ECCS Flow 500 ... 0 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-70 TOTAL BREAK FLOW AND TOTAL SAFETY INJECTION FLOW UNIT 2: 4-INCH BREAK Amendment No. 103 8000 .. . .. . .... . . 'G:" I N -+-' -I I.... ..c: ............ 6000 .. . .. . .... . . :::I -+-' CD ---Q,) 0 u I.... Q,) -4000 .. . .. . .... . . (/) c: I--+-' 0 Q,) :::r:: 2000 .. . .. . .... . . 0 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 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

900 ........... . 800 ............ . 700 ......... . 600 ....... . 500 .......................................................... . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-72 FLUID TEMPERATURE AT PEAK CLAD TEMPERATURE ELEV A TION UNIT 2: 4-INCH BREAK Amendment No. 103 1200 ............ . a:;:-1000 -::::I -+-' Q) c.... E 800 ........ . 600 ...... . 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 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 0.6E-01 * * * .. * * * * * * .. 0.5E-01 --en 0.4E-01 en Q) c: ..::ii:. (..) :.c I-Q) 0.3E-01 * * * * * * * * * * * * ""'C *x 0 0.2E-01 0.1E-01 * * * * * * * * * *

  • 0 0 1000 2000 Time (s) 3000 COMANCHE PEAK 4000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-74 MAXIMUM LOCAL ZR0 2 THICKNESS UNIT 2: 4-INCH BREAK Amendment No. 103 2000 0 1500 *en c... -e ::::I en en e a.. 1000 500 .......................................................... .

.......... .......... .......... ........... 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 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) 30 .......................................................... . 28 -26 ;:::::::: -Q) > 24 ..... ::::I -+-' x . . . . 22 *

  • * *** * ., *** !lll't flllt !""t *** ***
  • 20 ....... . 18 .......................................................... . 16 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-76 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 6-INCH BREAK Amendment No. 103 650 .......................................................... . 600 .......................................................... . 'G:" -550 :::I -+-" Q) a.. E 500 450 ....... . 400 ......................................................... .

.......... 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-77 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 6-INCH BREAK Amendment No. 103 2000 0 1500 *en c... -e ::::I en en e a.. 1000 . 500 .......................................................... . .......... .......... .......... ........... 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 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) 30 .......................................................... . 28 24 ... 20 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-79 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 8.75-INCH BREAK Amendment No. 103 650 .......................................................... . 600 .......................................................... . 550 'G:" -:::I 15 500 .._ Q) a.. E 450 400 ..... 350 ................ . .......... 0 500 1000 1500 Time (s) 2000 2500 COMANCHE PEAK 3000 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 I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted I 92 February 2. 1998 CPSES/FSAR APPENDIX 15A HAS BEEN DELETED 15A-l Amendment 84 February 28, 1992 I 84 CPSES/FSAR APPENDIX 15A HAS BEEN DELETED 15A-l Amendment 84 February 28, 1992 I 84 CPSES /FSAR Figure l 7.2M3 has been deleted. CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED I n AMENDMENT 77 SEPTEMBER 8, 1989 t .L COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS I ond 2 POST LOCA ACCESS ROUTE IA FIGURE 11.B.2*25 I I 0 E G COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 18 FIGURE 11.8.2-26 H COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE lC FIGURE I l.B.2-27 H c COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 2 FIGURE 11.8.2-30 H I 1!3231000 A B c 0 E F COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 3 & 4 FIGURE 1 l.B.2-31 H D COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS t and 2 POST LOCA ACCESS ROUTE 5 FIGURE I l.B.2-32 H 5 c COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 6 FIGURE I IB.2-33 ti COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 1 & 8 FIGURE 1 l.B.2-34 H COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 9 F I GURE 11.8.2-35 ' ,- A 8 c [l t E F ) G H 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.B.2-36 c H I A B c D E F COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 POST LOCA ACCESS ROUTE 10 & 11 SHEET 2 OF 2 F I GURE 11.8.2-36 5 6 £ F COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 12 FIGURE 1 l.B.2-37 H CPSES/FSAR FIGURE II.B.2-38 THIS FIGURE HAS BEEN DELETED Amendment 93 February l, 1995 118239000 A B c D 0 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 14 SHEET 1 OF 3 FIGURE I 1.B.2-39 H 6 116239100 B I) E F COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 POST LOCA ACCESS ROUTE 14 SHEET 2 OF 3 F IOURE 1 l.B.2-39 H 6 I i 2 3 5 6 B c 0 E F c COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 14 SHEET 3 OF 3 FIGURE ll.B.2-39 H B c D t 2 5 118240100 A B c D E F G E F H COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 15 SHEET 1 OF 2 FIGURE 11.8.2-40 H B C D £ F C H t 118240200 A 8 c E F COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 15 SHEET 2 OF 2 FIGURE I l.B.2-40 H A B 0 * [ J 5 ' A B c 0 E H FIGURE GENERATED FOR FSAR ONLY BASED ON DRAWING COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 16 FIGURE 11.8.2-41 G H ' * ' c ' ll

  • 8 c 0 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 17 SHEET 1 OF 1 FIGURE A B c 0 2 4 5 I A e c 0 E E H RM. NO. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 POST LOCA ACCESS ROUTE 19 SHEET 1 OF 3 FIGURE 11.8.2-42.1 H 6 A t 2 3 118242200.DGN A I c
  • E I I I COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 POST LOCA ACCESS ROUTE 19 SHEET 2 OF 3 FIGURE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNI TS 1 AND 2 POST LOCA ACCESS ROUTE 19 SHEET 3 OF 3 FIGURE ll.B.2-42.3 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 20 FIGURE !I.B.2-42.4 118243000 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 ANO 2 POST LOCA ACCESS ROUTE IA FIGURE 11.6.2-43 118244000 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IA FIGURE 1 l.B.2-44 118245000 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IB FIGURE 11.B.2-45 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IB FIGURE 11.B.2-46 CPE 116247000 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IC FIGURE 11.B.2-47 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 2 FIGURE ll.B.2-50 118251000 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 2 FIGURE 11.B.2-51 CPt COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS I AND 2 POST LOCA ACCESS ROUTE 3 ANO 4 FIGURE ll.B.2-52

CPSES/FSAR FIGURE II.B.2-66 93 I THIS FIGURE HAS BEEN DELETED Amendment 93 February 1, 1995 CPSES/FSAR FIGURE II.B.2-67 93 I THIS FIGURE HAS BEEN DELETED Amendment 93 February l, 1995

_________________________________ -:r;--------------------- I I I I I I I I -----------------------------J I @ __________

J I

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 Condensate Storage Tank -f t-L.O. f Al F.O. _..,_ --l"""'L-------=f ..:: --....... FAJ-. . ' F.O. f.O; . -...P.. ---For Unit 2 Only -For Unit 2 Only COMANCHE PEAK S.E.S. FNAL SAFET'( ANALYSIS REPORT UNITS 1 and 2 Auxilfary Feedwater System Amendment 102 S1mplf f1ed flow Dtagra_m __ _ Fl(UlE IJ.E.1.1-1 S:JPPl Y LINE VALVES p d NON-INDEPENDENT J FAILURES '-----.--110 STA;\ SIGMLS NO AUTC S!Gi;f1L Pb pc pd TRAlN FldL Note 1 l?V>iPl ! FAIL J l TO RUt*f: Q "r ,/I", ? e p 9 INDEPENDENT FAILURE OF TRAINS TRAIN I VALVES I J I 8 See Sheet 5 Sheet 4 ( CONTROL \ C !RCUIT Ph TU?B!NE TRAIN FAILS '] rnIL v pi ?j JANUARY 30, pk 1981 TEST OR MAINTEl'AriCE ASSOC!ATEJ FAILS Val.H:S d'<>Sign-ed are shown on Note l COMANCHE PEAK S. E. S FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 FIGURE ll.E.Ll-2 {S,eet 1 of 5) NON-INDEPENDENT FAILURES SLlPPL Y LINE VALVES BLOCKED NO START SIGNALS NO Au:o SIGtiAL TRAIN FAIL Note 3 Pt;MP FAJL TO RliN !NSUFF!CENT

  • FLOW TO THREE OF FO:J' R SHAM GrnrnATORS TRldll A FAll FAILURE OF TRAINS VAl'llS CLOSED OR See Sfleet 5 VALVLS CLOSEO OR Sheet 4 TURBINE TRAIN fArLS PUMP FA!l TO Rl'i ( NO \. STEAM JANUARY 30, 1981 TEST OR MA t NTENJ'.NCE ASSOCIATED FAllURES TRftJN FtdlS Note 2 OTllER TWD TR,.\H*S FA!l J Note probabii ities Pa thru Pr l !. £ '1.1-1. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AFWS loss Tree FIGURE n.E.l :-2 (Sheet 1 d Si NON-INDEPENDENT FAILURE OF TURElNE TRAIN NO START SIGNALS INSUfflCENT FLOW TO THREE OF FOUR STEAM GENERATORS VALVES CLOSED OR BLOCKED See Sheet 4 I!lDEPENDENT FAILURE TURBINE TRAHi P. J PUMP FAIL TO RUfi JANUARY 30, 1981 Values assigned to probabilities Pa thru Pr are shown on Table !l.E.l.l-1.

COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 t1rwS Simplified Fault Tree Loss of All FIGURE LE. l. l-2 (Sheet of 5) Po l, 2 3 BLOCKED Note 4 ONE BLOCKED Note 5 Pc Pm I, 2 & 4 BLOCKED ? p 3 Of 4 l!NES BLOCKED ?p Nott> 4 Note 5 P, tlcte 4 JANUARY 30, 1981 Pa thru Pr COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AFWS Simplified Fault Tree FIGURE ll.Ll.!-2 (Sheet 4 of 5) p n l OR 3 BLOCKED p ,., VALVES CLOSED MOTOR TRAIN l OF 2 LHlES BLOCKED 2 OR 4 BLOCKED I r1ote 6 JANUARY 30, 1981 p n Values assigned to probabilities Pa thru Pr are shown on Table rI.E.1.1-1. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Simplified Fault Tree FIGURE ILE.1.1-2 (Sheet 5 of 5) I RE 62 (EL.910'-9")


+---

¢.CONTAINMENT--- NOTE: UNIT 1 MONITORS SHOWN SAME FOR UN IT 2

REFERENCE:

1. FSAR FIG. 1.2-15 -S EL. 905'-9 11 CONTAINMENT HIGH RANGE RADIATION MONITOR (TYP) IRE6290A (EL.917'-9")

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.1.2-1 has been deleted Amendment 95 February 2. 1998 I 95 A B SENSOR SIGNALS FROM ONSI 2 ,, ,, 3 TECHNICAL" SUPPORT CF'JTER 5 OISPI AY 6 I FIG03A122.DGN A B SAFETY SYSTEM SIGNf.! S , UNIT c 0 D E INTEGRATED ERF COMPUTER SYSTEM ,,

  • E F G METEOROl_OGICAI DATA ,, ,, EOF DI SPLA "* F G H AMEIOJIENT 83 DECEMBER 13, 1991 FIGURE GENERATED rGR FSAR O"lL"' BASED ORAW:NG COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 INTEGRATED ERF COMPUTER SYSTEM FIGURE 111.A.l.2-2 H 2 3 5 6 CPSES/FSAR Figure III.A.1.2-3 has been deleted Amendment 95 February 2. 1998 I 95 CPSES/FSAR Figure III.A.l.2-4 has been deleted Amendment 95 February 2. 1998 I 95 CPS ES/APR Notes to Figure II.E.1.1-2 NOTE 1 -The Motor trains are identical a failure probability of x 10-l 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 tht.' same a failure probability of 1x10-1 is assigned using coup 1 ing. NOTE 6 -The probability of steam generator 2 being blocked is the same as that for stearn generator

1. JANUARY 30, 1981}}