ML16180A428
| ML16180A428 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| 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 FILL PROCESS IN TYPICAL DEMINERALIZER ARRANGEMENT < RESIN DISPOSAL PROCESS OUT SPENT NITROGEN RESIN STORAGE TANK WASTE HOLDUP TANK RESIN SLUICE FILTER
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SPENT RESIN SLUICE PUMP COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 RESIN SLUICE AMENDMENT 87 WATER REUSE SYSTEM DECEMBER 18, 1992 FIGURE 12.3-1
120 100 ~80 c a Cl.. ....0 s.. 41 ~:;, 60 z 40 20 0.05 o. l 0.15 0.20 0.25 0.30 0.35 0.40 0.45 Cobalt Concentration (W/0) COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 87 CORE CRUD DEPOSITS DECEMBER 18, 1992 FIGURE 12.3-2
16 14 ~12 8 6 4 2 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 87 CORE CRUD DEPOSITS DECEMBER 18, 1992 FIGURE 12.3*3
I CPE A B c D t E G H REV DWN CHKI APVD BP BES TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE CP-1 o;~~~ 07-01 FDA-2002-002945-01-00 PER SK-0012-02-002945-01-00 RADIATION ZONES MAXIMUM DESIGN NOTE ZONE NO DESCRIPTION AND EXPLANATION DOSE RATE(MREM/HR) 1 THESE DRAWINGS INDICATE" AS-BUILT" SHIELDING THICKNESS AND PLANT RADIATION ZONE DESIGNATIONS BASED ON DESIGN BASES UNCONTROLLED,UNRESTRICTED ACCESS AREA RADIATION SOURCES CD LESS THAN 0.25 NON-RADIATION PERSONNEL & VISITORS OCCUPANCY: 40 HRS/WK, 50 WKS/YR 2 THESE DRAWINGS ARE ISSUED FOR INFORMATION ONLY ACTUAL RADIATION LEVELS AND INFORMATION PERTAINING TO ACCESS SHOULD BE OBTAINED FROM RADIATION CONTROLLED,OCCUPATIONAL ACCESS AREA PROTECTION GROUP 0 LESS THAN 2.5 RADIATION WORKERS & AUTHORIZED VISITORS OCCUPANCY: MAXIMUM 40 HRS/WK, 50 WKS/YR 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 0 LESS THAN 25.0 CONTROLLED,LIMITED ACCESS AREA CONTROLLED,RESTRICTED ACCESS AREA WITH LIMITED OCCUPANCY LEGEND 8 MORE THAN 25.0 NORMALLY EQUIPPED WITH LOCKABLE DOOR/GATE SH ST SHIELDING STRUCTURAL H.C HEAVY CONCRETE "1'" I CONTROLLED,RESTRICTED ACCESS AREA,NORMALL Y INACCESSIBLE M G NO LIMITATION ACCESS IS VIA LOCKABLE DOOR 0i
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CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE N---- 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 ICJ--== 10 PLAN AT EL. 790'-6" 62 RM# ROOM NAME 153 8 2'-6" 153 63 SH FL. EL. 781'-7" 64 65 lf) 66 I FOR ROOM NAMES M 67 PLAN AT EL 773'-0" 68 SEE Al-0413 SERIES DRAWINGS 0i 69 70
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CPE A B c D t E G H 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 FOR ROOM NAMES 154H SEE Al-0413 SERIES 154I DRAWINGS 154) 154K 154L 154A 154B 154C 154D 68 69 77A 77B 78 79 80 FOR ROOM NAMES 81 SEE Al-0413 SERIES 82 DRAWINGS 83 84 85 85A 85B 85C PARTIAL PLAN AT EL 800'-6" 75 } FOR ROOM NAMES SEE 76 Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL 819'-6" 155A PARTIAL PLAN AT EL 821 '-0" 86 } FOR ROOM NAMES SEE 87 Al-0413 SERIES DRAWINGS PARTIAL PLAN AT EL 822'-9" 155B FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS NON-SAFETY LUMINANT 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 me754600.dgn B c D E G H FINAL PRINT
CPE A B c D t E 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 FOR ROOM NAMES 155G SEE Al-0413 SERIES 88 DRAWINGS 89 90 91 92 93 94 95A&B 96 96A 96B 99A 99B 99C 99D PARTIAL PLAN AT EL. 841'-6" 97 FOR ROOM NAMES 98 SEE 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 Ml-3500-05 G H A FINAL PRINT
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
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CPE A B c D t 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.# RM.NAME
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CPE A B c D t 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 FOR ROOM NAMES 161A SEE Sl-0413 SERIES DOME DRAWINGS 111 112 0,........ 246A I M 0i
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CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0020-02-002945-01-00 NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0506 I M 0i
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I CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA 2000-003261-02-00 PER SK-0067-00-003261-02-00 N FL. EL. 785'-6" NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWINGS Al-0508 S-0700 S-0703 PLAN AT EL. 778'-0" & 790'-6" RM.# RM. NAME 113 114 115 115A 115B 115C 115D 130 162 163 164 165 166 167 168 169 FOR ROOM NAMES 170 SEE Al-0413 SERIES DRAWINGS 171 172 173 174 D 175 176 180 0 177 178 FL. EL. 790'-6" 179 180 181
~1_16_~ [tjj ,~_1_17~ 181A 181B 182 184 185 D 118 DD 119 D D PARTIAL PLAN AT EL. 792'-0" RM.# RM. NAME C==:~B~B~1fr'=~B~B~:====;L, D 116 D D D 117 FL. EL. 778' -0" 118 122 119 0 00 [ D 120 121 D 120 D
D DD D D 121 122 FOR ROOM NAMES 123 SEE Al-0413 SERIES 123 124 DRAWINGS 124 D D D 125 D 126 127 D D D D 127 128 129 D D 130 131 D D 115 Jc:J L CTCD=1 NON-SAFETY D '------__Jc 130 LUMINANT CPS ES GLEN ROSE, TEXAS PLAN AT EL 778'-0" & 790'-6" PARTIAL PLAN AT EL 792'-0" RADIATION ZONES & SHIELD THICKNESSES ALL AREAS RADIATION ZONE PRIMARY PLANT AUXILIARY & ELECTRICAL CONTROL BUILDING FLOOR PLAN AT EL 778' -0" & 790' -6" DWG.NO Ml-3500 10 CP-2 me571700.dgn Ml-3500-10 B c D E G H A FINAL PRINT
CPE A B c D t 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 M 191 I 192 M 193 0i 194 195 196 FOR ROOM NAMES 197
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CPE A B c D t 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
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CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0023-02-002945-01-00 N 1 1 B A CD 135 Q NOTES 139 FOR LEGEND,ABBREVIATIONS,RADIATION ZONES d 141 AND GENERAL NOTES SEE Ml-3500-01
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CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0024-02-002945-01-00 N DEMINERALIZER CUBICLES SHIELD WALL THICKNESSES NORTH EAST SOUTH WEST SLAB ABOVE RM.NO WALL WALL WALL WALL &BELOW 228A 3'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228B 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228C 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" NOTES 228D 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228E 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" FOR LEGEND, ABBREVIATIONS, RADIATION ZONES 228F 2'-0" 2'-0" 2'-0" 3'-0" 2'-9" AND GENERAL NOTES SEE Ml-3500-01 228G 2'-0" 2'-0" 2'-0" 2'-6" 2'-2" 228H 2'-0" 2'-0" 2'-0" 2'-6" 2'-2" 228) 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" REFERENCEDRAWINGS Al-0511 228K 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" S-0725 228L 2'-0" 2'-0" 2'-0" 2'-0" 2'-2" 228M 2'-0" 2'-0" 2'-0" 3'-0" 2'-2" 228N 2'-0" 2'-0" 3'-0" 3'-0" 2'-2" PLAN AT EL. 842'-0" 231A 2'-9" 3'-0" 2'-0" 3'-0" 2'-2" RM.# RM. NAME 231B 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 231C 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 207A 231D 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 219A 231E 2'-0" 3'-0" 2'-0" 3'-0" 2'-9" 228A TIIRU 2280 228H TIIRU 228N 227 SEE TABLEZONEF-1 SEETABLEZONEF-1 231F 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 2'-0" 3'-0" 2'-0" 3'-0" 2'-9" 227A 231G 231H 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 228A 231J 2'-3" 3'-0" 2'-0" 3'-0" 2'-2" THRU 231K 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 228N FOR ROOM NAMES 2'-0" 3'-0" 3'-0" 2'-2" SEE Al-0413 SERIES 231L 2'-0" 230 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" DRAWINGS 231M 231A 231N 2'-0" 3'-0" 2'-0" 3'-0" 2'-2" 2'-0"SLAB,SH ABOVE & BELOW 230 G 2'-0"SLAB,SH ABOVE & BELOW 231P 231Q 2'-0" 2'-0" 3'-0" 3'-0" 2'-0" 2'-9" 3'-0" 3'-0" 2'-2" 2'-2" THRU 231Q 232 233 NOTE: ALL DEMINERALIZER CUBICLES ARE RADIATION ZONE G 233A 233A 233A 231A TIIRU231H 231J TIIRU 231Q SEE TABLEZONEF-1 SEETABLEZONEF-1 PIPE CHASE EL. 844'-6" PLAN AT EL 842'-0" NON-SAFETY LUMINANT CPS ES GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT AUXILIARY BUILDING PLAN AT EL 842'-0" Ml-3500 14 CP-1 me548400.dgn A B c D E G H Ml-3500j4 FINAL PRINT
CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0025-02-002945-01-00 N 2'-0" SH 234 0 Si ~ NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES D D D D D AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0510 235 (III) S-0728 S-0707 PLAN AT EL. 852'-6" & 854'-4" D D D D D D D @) RM.# RM.NAME 150
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CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-02945-01-00 PER SK-0026-02-002945-01-00 N NOTES
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CPE A B c D t E 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 00 PLAN AT EL. 810'-6" I RM.# RM. NAME M 247 0i 247A 248 249 249A
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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 CP-1 A G H Ml-3500-17 FINAL PRINT
CPE A B c D t 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 FOR ROOM NAMES 266 SEE Al-0413 SERIES DRAWINGS 267 268 269 270 270A 271 271A 271B 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 CP-1 me548900.dgn Ml-3500-18 B c D E G H A FINAL PRINT
CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0029-02-002945-01-00 N 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.# RM.NAME 273 272 FORROOMNAMES ROOF 272A SEE Al-0413 SERIES
}
272B DRAWINGS 2'-6" SLAB PARTIAL PLAN AT EL. 899'-6" 0 273 FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS N I M 0i 272A ROOF GD X-RE-6272 LRAM ~
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t N LOCATION B (APPROX) 1 MOVABLE RCA BOUNDARY DOORS ADMINISTRATIVELY CLOSED WHEN REQUIRED FOR LEGEND, ABBREVIATIONS, RADIATION ZONES FOR RCA BOUNDARY AND GENERAL NOTES, SEE DRAWING Ml-3500-01 (I) c::1 (I) ""~ I I
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I CPE A B c D t E G H REV DWN CHKI APVD REMARKS BP RG TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE CP-1 o;~:: o;~:: FDA-2002-002945-01-00 PER SK-0030-02-002945-01-00
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PLANT
-----NoiT'H"-- NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 I l-RE-5100 LPM REFERENCE DRAWING: Al-0408 I
PLAN AT EL. 755'-4" 1-001 1' \
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I CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0031-02-002945-01-00 N~-- l-007D D NOTES 1-007 l-007B 1-006 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0413-01 PIPE TRENCH ID I PLAN AT EL. 778'-0" RM.# RM. NAME 1-005 1-006 1-007 1-007A FOR ROOM NAMES l-007B SEE Al-0413 SERIES l-007C DRAWINGS l-007D l-007E ~ 2-282A 2-282C N () () I M 0i DD JJJ 1-005 ~
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FOR CONT SEE M2-3500-09 NON-SAFETY PLAN AT EL 778'-0" LUMINANT TURBINE BUILDING CPS ES BASEMENT FLOOR PLAN GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 1 TURBINE BUILDING PLAN AT EL 778'-0" Ml-3500 21 CP-1 me549200.dgn A Ml-3500-21 B c D E G H FINAL PRINT
CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0011-02-002945-01-00 N 1 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 FOR ROOM NAMES 39B SEE Al-0413 SERIES 39C DRAWINGS 42 42A 287 N N I M 0i
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I CPE A B c D t E G H REV DWN CHKI APVD REMARKS BP RG TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE CP-1 o;~:: o;~:: FDA-2002-002945-01-00 PER SK-0008-02-002945-01-00
~-~
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-----NoiT'H"--
NOTES FOR LEGEND,ABBREVIATIONS,RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 2-RE-5100 II REFERENCE DRAWING: Al-0408 LPM I 2-001
~
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I CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0009-02-002945-01-00 N~-- 2-282B c=i 2-282D I D 2-282 CD NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 REFERENCE DRAWING: Al-0413-01 [DJ PIPE TRENCH 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 N 0i () () N I M 0i
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FOR CONT SEE Ml-3500-21 NON-SAFETY PLAN AT EL 778'-0" LUMINANT TURBINE BUILDING CPS ES BASEMENT FLOOR PLAN GLEN ROSE, TEXAS RADIATION ZONES & SHIELD THICKNESSES PRIMARY PLANT - UNIT 2 TURBINE BUILDING PLAN AT EL 778'-0" M2-3500 09 CP-1 me546600.dgn M2-3500-09 B c D E G H A FINAL PRINT
I CPE A B c D t E G H REMARKS
- i:.~02-002945-01-00 ~032-02-002945-01-00 CORPORA TE DESIGN CHANGE RA WING REVISEDPERTO SK-1~1 DI 10
~ ~
l-RE-2959 llll 1)1 CD 11 CTQ]ll NOTES: RADIATION ZONES FOR LEGEND, ABBREVIATIONS, NOTES, SEE DRAWING Ml-3500-01 ANDGENERAL 23 REFERENCE DRAWING: Al-0401
~ 0 PLAN ATEL 803'-0" & 810'-6"
!OB Rm# RM.NAME TYP 16 10 0 JOA 8 CD !OB llA llB B FL. EL. 803'-0" 11 12 13 14 15 16 FOR SEEA DRAWINGS MNAMES RlO-00413 SERIES A(APROX) l0 LOCATION ABOUNDARY 17 MOVABLE RC RY MAY BE 18
[: RCA BOU~~'bcATION B 19 MOVEDT NDER 20 (Ml-3500-23) U E CONTROLS 21 AD MINI ST RA TIV IL8JL8JI 22 SEE Ml-3500-23 23 24 D 27A 33 41
~
43A D D NON-SAFETY 03'-0" & EL 81 O' -6" PLAN AT EL 8 PLAN MEZZANINE FLOOR me549300.dgn Ml-3500-22 B c D E G A FINAL PRINT
I CPE A B c D t E G H TIIIS DRAWING REMARKS FDA-2002-002945~~~~~~R~K~~~0~2~:~45DESIGN 00 CHANGE N I 288A (I) NOTES SEE M1~:J5~~iATION ZONES FOR LEGEND AND GENE RAL
'ABBREVIATION REFERENCE DRAWING: A2-0401 i PLAN AT EL. 803' -O " & 810'-6" RM.#
[~ i RM.NAME i 10 288B (I) 16 2-32 34
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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 ,S2-0600 ,S2-0602 PLAN AT EL. 790'-6" RM. # ROOM NAME I53 63 64 65 66 67 FOR ROOM NAMES SEE Al-0413 SERIES 68 DRAWINGS 69 N 70 M 71 NI 72 M 73 0i 74 74A
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CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0002-02-002945-01-00 N~--- NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOM 85D CONTAINS SOURCES WHICH MAY EXCEED ZONE III LIMIT DURING REFUELING WATER TRANSFER FL. EL. 810'-6" REFERENCE DRAWING: A2-0500 S2-0318 REFUELING WATER STORAGE TANK PLAN AT EL. 810'-6" & BELOW REACTOR MAKE-UP
'WATER STORAGE TANK Rm # ROOM NAME 70 } FOR ROOM NAMES SSD SEE Al-0413 SERIES DRAWINGS M
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CPE A B c D t E 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 FOR ROOM NAMES
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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 lf) M N I M 0i FOR ROOM NAMES SEE Al-0413 SERIES DRAWINGS ~
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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" RM.NAME
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CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0006-02-002945-01-00 N G 155N 155N NOTES 1 FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 (,- - - - -;re-~,~ - (~')) REFERENCE DRAWING: A2-0504 S2-0528 S2-0530 S2-0614
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CPE A B c D t E G H TIIIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0007-02-002945-01-00 N NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES 2-RE-6290B AND GENERAL NOTES SEE Ml-3500-01 HRRM REFERENCE DRAWING: A2-0505 S2-0617 PLAN AT EL. 905'-9" & 896'-4" 2-RE-6290A Rm # ROOM NAME HRRM 161E 160B 160A 161A FOR ROOM NAMES SEE Al-0413 SERIES DOME DRAWINGS 111 112 246B 00 M NI M 0i FL. FL. 900'-3"
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~ SAFETY ANALYSIS FEPalT' UNITS 1 and 2 AUXll:IAl!Y BUILDING PLAN AT EL.831'* a*
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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 B c D t E G H l!..1Q"-{ ~'TAl~T t I 5TEEL PLATES SHIEL.DIN~
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SECTION 3A* 3A SECTION 3-3 Amendment 102 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1and2 SECTION 3C- 3C (AS SHOWN) FUEL TRANSFER TUBE SECTION 30-30 COPP. HAND) SHIELDING PROVISIONS FIGURE 12.3-33 SH 3 OF 3 I fsOOOOl b.dgn A B c D E G H
CPE A B c D t E G H TIIIS DRAWING CREA TED TO INCORPORATE DESIGN CHANGE FDA-2002-002945-01-00 PER SK-0014-02-002945-01-00 N NOTES FOR LEGEND, ABBREVIATIONS, RADIATION ZONES AND GENERAL NOTES SEE Ml-3500-01 ROOM 85D CONTAINS SOURCES WHICH MAY EXCEED ZONE III LIMIT DURING REFUELING WATER TRANSFER FL. EL. 810'-6" REFERENCE DRAWINGS Al-0500 Sl-0318 I I REFUELING WATER STORAGE TANK I I REACTOR MAKE-UP WATER STORAGE TANK I I
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I I I I FL.EL. 800'-0" I I FL.EL. 800'-0" PLAN AT EL. 810'-6" & BELOW I I 85D I I 1----------------l-~~~-----~
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I FL. EL. 810'-6" 70 FOR ROOM NAMES SEE Al-0413 µ... I
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PLAN AT EL 810'-6" 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 me547500.dgn A Ml-3500-03 B c D E G H FINAL PRINT
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~E _.wr:. .~ OIOIJ 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 I 87 Amendment 87 December 18, 1992
CPSES/FSAR Figure 12. has been deleted. 83 AMENDMENT 83 DECEMBER 13, 1991
CPSES/FSAR FIGURE 12.5-3 HAS BEEN DELETED I a7 Amendment 87 December 18, 1992
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 Decommissioning Funding l Collections I l l Luminant
- ..................................................-~ Luminant Energy Other Luminant Generation Company LLC Companies Company LLC*
A A Power Purchase and Sale Agreement
- Note: Owner/Operator of CPSES COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1AND2 Amendment 102 LUMINANT POWER COMPANY lSimolified Oraanization Diaaraml FIGURE 13.1-1
CEO Luminant Power (1) Senior Vice President
& Chief Nuclear Officer Operations Review Committee Vice President, Site Vice Nuclear President Engineering &
Manager, Manager, Support (Vacant) Director, Organizational Regulatory Nuclear Plant Effectiveness Affairs Manager Oversight Manager, Director, Manager, Safeteam Environmental Performance Nuclear Manager Director, Director, Services Improvement Training Site Project Director, Director, Engineering Engineering Operations Maintenance Manager, Nuclear Corrective Manager, Manager, Director, Manager, Action Program Manager, Manager, Emergency System Technical Work Radiation Engineering Support Security Planning Management Protection Manager, Plant Reliability COMANCHE PEAK SES SAFETY ANALYSIS REPORT for DUAL UNIT OPERATIONS Nuclear Generation NOTE: (1) Located at Corp. Office All others located on-site Figure 13.1-2 AMENDMENT 107
Site Vice President I I Director, Manager, Environmental I Organizational Effectiveness Plant Manager Services I I I Director, Director, Director, Nuclear Performance OE Training Improvement Projects Director, Director, Maintenance Operations Manager, Radiation Protection Maintenance Maintenance Manager, Shift SMART Plant Operations Operations Team Support Support. Mgr. Managers Managers Manager, I Nuclear - Shift Chemistry. Mgr. Maintenance Support Group Ops Performance Improvement Warehouse COMANCHE PEAK SES SAFETY ANALYSIS REPORT FOR DUAL UNIT OPERATIONS NUCLEAR OPERATIONS FIGURE 13.1-3 Amendment 106
January 19, 1982 UNITED STAHS OF AMERICA NUCLEAR REGULATORY COf'MJSSION It 1s agreed that this Stipulation ls contingent upon Its acceptance BEFORE THE ATOMIC SAFETY ANO LICE:NSING 8QARO by the NRC Staff and upon dlsmhsal of Contention 1 by the licensing Board, Jn the Hatter of and shall be Incorporated In and become a part of the Final Safety Analysis TEXAS UTILITIES GENERATING COMPANY, !!. ill* Docket Nos. 50-445 and Report to Comanche Peak. 50-446 (Comanche Peak Steam Electric Station, Units 1 and 2) ST! PULA Tl ON Citizens for Fair Utility Regulation 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. DATE: January 19, 1982 Applicants hereby represent that they will assemble a qualified in-house
,, technical staff prior to fuel loading for Comanche Peak and maintain that Ci
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("") tro() staff for the duration of plant operations. Applicants further represent that c::0 :c
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A B c D t E 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 12 10 11. SEISMIC RECORDER PANEL 9 12. INCORE MOYABLE FLUX MAPPING SYSTEM
- 13. UNIT 2 RMS
- 14. UNIT 2 MAIN CONTROL BOARD 11
- 15. OPERATORCONSOLEA
- 16. OPERATOR CONSOLE B 8 13 5 7 17. SUPERVISOR CONSOLE C
- 18. EMERGENCY PLANNING CONSOLE 1
- 19. QUIET ROOM WORKSTATION
- 20. QUIET ROOM 6
13 16 15 18 14 17 20 19 17 15 16 4 Amendment 100 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1and2 AREA DESIGNATION "AT THE CONTROLS" 05-27-2004 FIGURE 13.5-1 A B c D E G H fsOOOOOl.dgn
CHAIRMAN I I OPERATIONS ENGINEERING WESTINGHOUSE (NOTE 1) (NOTE 2) NOTE 1: Design, testing, and technical support functions. NOTE 2: For all matters concerning initial startup testing performed on the NSSS and associated 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
CHAIRMAN I I I I NUCLEAR OPERATIONS ENGINEERING WESTINGHOUSE STARTUP OVERVIEW NOTE 1 NOTE 2 NOTE 1: Design and technical support functions. NOTE 2: For all matters concerning preoperatlonal testing performed on the NSSS and COMANCHE PEAK S.E.S. associated auxlUary systems. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 87 JOINT TEST GROUP DECEMBER 18, 1992 FIGURE 14.2-2
Figure 14. 2-3 PREOPERA TIONAL TEST SCHEDCLE RCS Cold Hot Hydrostatic Containmc:i;: Functional Fuel Initial 50% 100% Test Test Power SPrepar: Procedures
- ti( Be&f.n Testing >1 Test Load Criticality Power
(-IS months) (-10 months) I (-4 months) I I (-2 months) t (0 months) I I I Demineralized and Reactor Makeup Water Pressurizer Safety and Relief Valves - - - - Steam Generator Safety and Relief Valves - - - - - - - - ------------------------- Main Steam and Feedwater Isolation Valves - - - - - - - ---------~--------------. Residual Heat Removal System - - - - - - - - - - - - -----------< >-------------- Safety Injection System - - -- - - - - - - - - - - - ----------..()--------------<>-------* Auxiliary. Fuel, and Safeguards Building Ventilation - - - O - Partial completion of system Containment Ventilation - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - test. Combustible Gas Control System - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- Containment Isolation System- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Integrated Engineered Safety Features Test - - - - - - - - - - - - - - - - - Control Room Ve.atilation - - - - - - - - - - - -- - * - System test completed. Auxiliary Feedwater System - - - - - - - - - - - - - --------------------------0*-------m Electrical Area And Battery Room V e n t i l a t i o n - - - - - - - - - - - - - - - - ( ) - - - - - - - - - - - - - - < Diesel Generator Ventilation - - - - - - - - - - - - - 1-------* DC Power System- - - - - - - - - - - - - - - - - - - - - - - - - - - 1 0...------40""-------10)...-------* AC Power Distribution System - - - - - - - - - - - - -----------<>-------0\-------......joi---------* Diesel Generators - - - - - - - - - - - - - - - - --------------------------er-------* Instrument and Control Power Supply - - - - - - - - - - ---------.......c'.J-.-----.(').------0,__------** Communication Systems - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- Emergency Lighting System - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - *
=~IEKmeNoc~rln&rum~~oo------------------------------------------* Seismic Instrumentation - - Reactor Protection System - - - - - - - - - - - - - - ------------------------lJ-------* Radiation Monitoring Systems - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- Fire Protection System - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- Fuel Handling and Vessel Servicing Equipment - - - - - - -----------u---------------<.J-------*
Service Water System - - - - - - - - - - - - - - ------------------c0 Amendment 88 Component Cooling Water System - - - - - - - - - *- - - - - - - - - - - - - - - - - - - - '0 APRIL 16, 1993 Waste Processing Systems - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 0 Containment Spray System - - - - - - - - - - 0 Chemical and Volume Control System - - - - - - - - - - -----------< 1----------------- Vents And Drains-------------------------------------------~--~~~* COMANCHE PEAK S.E.S. Process Sampling System - - - - - - - - - - - - - - ---------------------------U-------* FNAL SAFETY ANALYSIS REPORT g~~:i~ f Spent Fuel Pool Cooling and Cleanup System - - - - - - - --r---------- --------------------- UNITS 1 and 2
- - -------------------------<J-------.ij*
Q423.17 IBoron Recycle System - - - - - - - - - - - - - PREOPERATIONAL TEST SCHEDULE Reactor Control System- - - - - - - - - - - - - - ----------- --
- FIGURE 14.2-3 {Sheet 1 of 2)
Figure 14.2-3 PREOPERATIONAL TEST SCHEDULE RCS Cold ~'.ot Hydrostatic Containment Functional Fuel Initial 503 1003 Power Power s Prepare Procedures ,.,
- Be9in Testing *1 Test Test Test Load Criticality
(-18 months) (-10 months) l (-4 months) I I (-2 months) I ( 0 months) I I I Boron Injection Tank ... deleted from the CPSES design Computer System--------------------------- -~----~~~---~*------~~~o~~~~-~~** Incore Thermocouples - -- - -- -- -- -- - - - -- - - - -- 0......---------* Operational Vibration Tests---------------------------------------~--------<)----------~---~- Containment Local Leak Rate T e s t s - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 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\ c.,...reial ~ation 0423.10 I Reactor T:r:ip Sy*t-- - - ------------x Approx. 5 montba I aft<>r fuel lo.d Boron Reactivity Worth*- - ---------------------x I
------------x I I l 0423.10 l Aut'*'Atie Reactor Control Sy*t... T**t- - - - -x ilaaotor Coolant Flow Ta*t - -----------x---------------------------------------------x-----------x I I Reactor Coolant Flow Coa*tdovn- - - ----~-----x I I I
- ------------x---------------------------------------------x I I Rod Po*ition Indicator*- ------------x I I I Modiarator Temperature Reactivity Coafficiant- --------------------x 1 I Control Rode R..activity North*- - - - - - - --------------------x I
0423.10 l Aurlliary Startup In*tru1Mntation- -X 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 - -x-----------------~-----x------------------------x 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 Amendment 88 Rod Control Sy*t- Te*t -----------X I I APRIL 16, 1993
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-'
X. - Te*t required to IMI perfaraed at thi* powe.r.
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 0423.10 1 -----------x I Appr0it. s -t:.ba I I attar f-1. loml Boron !lAacti.vity Worth*- - - -I - - - - - ----------------xI
- -----------x I I I 0423.10 J -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 a42a.10 I Awdliary Startup In*t~ntation- - - -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 I I I ll&diation Sw:T*Y - - - - - - - - - - -x----------------------x------------------------x I I Cora Re&ativity Ba.lane*- ---------------------------------------------------------------------x I I Lo** of Offaite Power- - - x I I
-x I
Unit Load Tranai*nts- - -x-----------x------------x I 0423.10 l Inoor* Nuo1.ar Inat~ntation -------------------------X----------------------------------X I I I I a.actor Coolant X..alt T**t -----------X I I I I I Rod Contro1 Sy*t.... Taat ------------X I I Amendment 88
~-------------------------------------------------------' April 16, 1993 X. T**t r*quired to b9 parfo.aaed at t:h.i* power.
610~*********************************************************************************************************************************************************************************************************************************************************** *w******************************* 1 600 590 LL' Q) ....:::lcu 1.. 580 1.. Q) c. E Q) 1- ~
!: 570 Q) 1..
0 (.) 560 550 f--. I 1860 psia I Overpower N-16 Trip Line 540+-----~----~------~----~----~----~----~----~ 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 1.30 Core Power {fraction of nominal) Comanche Peak Final Safety Analysis Report Units 1 and 2 Illustration of Overtemperature and Overpower N-16 Protection Figure 15.0-1 Amendment No. 103
CPSES/FSAR gure 15.0-2A has been 92 August 1. 1996
CPSES/FSAR Figure 15.0-28 has been deleted 92 August 1. 1996
---0a. 1.0 ..c: t/I co c .....0 0.9 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: st/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
0.80 .c: t:= 0
- 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
0.9 0.8 0.7 .c t:: 0 ~ 0.6 ~ co Q) et: (.) 0.5 (.) Dash pot et: "C Q) iii 0.4 E0 z 0.3 0.2 0.1 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 Normalized Rod Drop Time (Time After Drop Begins I Time to Top of Dashpot) Comanche Peak Final Safety Analysis Report Units 1and2 Normalized RCCA Bank Reactivity Worth Versus Normalized Drop Time Figure 15.0-5 Amendment No. 103
7 0 L..L. E u CL 6 Unacceptable Operation +> c (!) u 5 4-4- (!) Acceptable u 0 4 Operation Q.J I-
- i
+> 3 n:l I-Q.J c.. E Q.J f- 2 I-0 +> n:l I- 1 Q.J "O 0
- L 0
0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Moderator Temperature Coert1c1ent AMENDMENT 84 Versus Percent of FEBRUARY 28, 1992 Rated Thermal Power FIGURE 15.0-6
ABBREVIATIONS USED: AFWS - AUXILIARY FEEDWATER SYSTEM ECCS - EMERGENCY CORE COOLING SYSTEM eves - CHEMICAL AND VOLUME CONTROL HL - HOT LEG SYSTEM CL - COLD LEG ESFAS - ENGINEERED SAFETY FEATURES CCWS - COMPONENT COOLING WATEi ACTUATION SYSTEM SYSTEM FW - FEEDWATER RCS - REACTOR COOLANT SYSTEM RTS - REACTOR TRIP SYSTEM SWS - SERVICE WATER SYSTEM SIS - SAFETY INJECTION SYSTEM HPI - HIGH PRESSURE INJECTION SI - SAFETY INJECTION LPI - LOW PRESSURE INJECTION RT - REACTOR TRIP Cl - CONTAINMENT ISOLATION CS - CONTAINMENT SPRAY SG - STEAM GENERATOR NOTES: I. FOR TRIP INITIATION AND SAFETY SYSTEM ACTUATION, MULTIPLE SIGNALS ARE SHOWN BUT ONLY A SINGLE SIGNAL IS REQUIRED. THE OTHER SIGNALS ARE BACKUPS.
- 2. NO TIMING SEQUENCE IS IMPLIED BY POSITION OF VARIOUS BRANCHES.
REFER TO EVENT TIMING SEQUENCES PRESENTED IN TABULAR FORM IN PfPTINENT ACCIDENT ANALYSIS SECTION OF CHAPTER 15.0 OF THE FSAR. DIAGRAM SYMBOLS: ( ) - EVENT TITLE 0 - BRANCH POINT FOR DIFFERENT PLANT CONDITIONS I'---------'I - SAFETY SYSTEM
< ) - SAFETY ACTION fi"
\ )
- SYSTEM REQUIRED TO MEET SINGLE-FAILURE CRITERIA 1-;\ - MANUAL ACTION REQUIRED DURING SYSTEM OPERATION FEBRUARY 20, 1981
\ )
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 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
COMANCHE PE AK S. E. S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 DEPRESSURIZATION OF MAIN STEAM SYSTEM AMENDMENT 78 JANUARY 15, 1990 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 15.0~14
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MARCH 31, 1981 LOSS OF FORCED REACTOR COOLANT FLOW FIGURE 1 5 . 0-1 5
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 UNITS 1 and 2 FEBRUARY 20, 1981 I NCONTROLLEO ROD CLUSTER CONTROL SSEMBLY BANK WITHDRAWAL FIGURE 15. 0-16
COMANCHE PEAK S.E.S. Fl NAL SAFETY ANALYSIS REPORT UNIT 1 AND 2 Amendment 94 DROPPED ROD CLUSTER August 1, 1996 CONTROL ASSEMBLY Fl GURE 15.0-17 TLJF150170.DGN
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 I 7a AMENDMENT 78 JANUARY 15, 1990
AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK SES FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 BORON DILUTION FIGURE 15.0-20
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 RUPTURE OF CONTROL ROD DRIVE MECHANISM HOUSING AMENDMENT 54 JANUARY 21, 1985 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 .... CXl 0 OF REACTOR COOLANT SYSTEM FIGURE 15. 0-2 3
~
N
COMANCHE PEAK S.E.S. FINAL SAFE TY ANALYSIS REPORT UNITS 1 and 2 Amendment 70 April 22, 1988 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 76 MAY 1, 1989 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT FIGURE 15.0-30
AMENDMENT 87 DECEMBER 18, 1992 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 SPENT FUEL CASK DROP ACCIDENT FIGURE 15. 0-31
CPSES/FSAR Figures 15.1-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
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CPSES/FSAR Figures 15.1-lA.B thru 15.1-20 have been deleted 92 August 1. 1996
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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
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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
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CPSES/FSAR Figures 15.4-lA.B thru 15.4-30 have been deleted 92 August l, 1996
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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
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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)
- - - - - P C T Location 1400 12 1200 1000 Cl) 1.-
- i c 0
~ 800 :.;:;
CL 0 Cl) > Cl) E LLI ~ 600 4 400 200 2 0 100 200 300 400 500 Time After Break (s) 607628075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case PCT and PCT Location Figure 15.6-1 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis VESSEL SIDE BREAK FLOW 70000 60000 50000 U) ........... 40000 E
...0
_. Q.) 0 0::: 30000 3= 0 l..J..._ U) CJ') 0 20000
~
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 PUMP SIDE BREAK FLOW 30000 25000 20000 (/) E
....0
..::::::.- 15000 _.Q.) 0 0::::
- =
0 LL 10000 (/) (/) 0
~
5000 0
-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 Intact Loop Broken Loop
-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_
....,._.....1___.1___.1___.1___,,___.1___.1____.1____.1___,,,.........1____.1_1....__1..........,,.--1......_..__1..__1..__1.--,..__1..__1..__1..........
1 0 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
....Cl 5
Q) 0 0::: 0 u._ I.... 0 0 CL 0
-5
-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 PRESSURIZER PRESSURE 2500.....--------------------------. 2000-Q.)
~
(/) (/)
~
0.... 1000-500-0 j_~'--L'_::r:,::L,==:::::::r::::c:::r::~.:::c::I:::r:::r::~.;::::::J::::I::::r:::c:::::;::,=::::c::r:::::c~ 0 50 100 150 200 250 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Pressurizer Pressure Figure 15.6-6 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis LOWER PLENUM COLLAPSED LIQUID LEVEL 10 -+-' '+--- Q) 8 Q) __J ~
- I er 6
- ..::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 o---~~~----.-~~~~....-~~~--r-~~~~ ..... ~~~~ 0 100 200 300 400 500 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Vessel Fluid Mass Figure 15.6-8 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis INTACT LOOP 2 ACCUMULATOR MASS FLOW RATE 3000 2500 2000 ~ en E
....c
..:::::::, 1500 _.(]) 0 0:::: 3:: 0 l..J._ 1000 500 0
-500 0 50 100 150 200 250 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Loop 2 Accumulator Flow Figure 15.6-9 Amendment No. 103
Comanche Peak Unit 1 ASTRUM BELOCA Analysis INTACT LOOP 2 SI MASS FLOW RATE 1200 1000 E CL CTI (I) 800
-+--'
0 0::: 3= 0 LL.. 600 en en 0
- 2:
400 200 o-+-_..__.._......_.........,,..........__..__.__._-.-_.__..__.__._~_..__.._...__.........,,..........__..__.__._-t 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 er 6
- .: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 LIQUID LEVEL IN INTACT LOOP 2 DOWNCOMER 30 25 Q.) ~ 20 -0 er
- ..:::J
-0
~ 15 a_
0 0 (_) 10 5 o--_.__.__.__._~...._...._...._..__~..__..__"---'___,___.___.___.___.~---'----'--'--'---1 0 50 100 150 200 250 Time After Break (s) 607828075 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 1 Limiting PCT Case Loop 2 Downcomer Collapsed Liquid Level Figure 15.6-12 Amendment No. 103
PBOT/PMID Box for the Comanche Peak Units 1and2 BELOCA Project 0.45 I=' 0.332, 0.418 0 co c.. Cl) 0 0.40 (,) Q) 0.310, 0.380 s::. 0
't:J
- E E
0 0.35
=0 .Q -Cl) s::.
c: Cl) 0.30 3: 0 c.. 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
'\
\
40 \
\
\
\
\
\
\
35 \
\
\
0
*u; 30
CL 20 15 10~~~~~---t~~~~~--~~~~---t~~~~~--~~~~---1 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)
- - - - - P C T Location 1600------------------------12 1400 I - - I - - -
I
- -.,_ 1i 11 I~ '"II r
111 T' I II f - ri I I
-,~,
~I I
~ 4 ~;
I lO I 'Iii~ _, l I I ~~I 1200 I
- i:ll"'
.1111 J : I II 'If
'Ill* I I I c
~ 1000
- l c 0
~ :,+:::;
Cl... 0 (L) > (L) E BOO w ~ 6 600 4 400 200-+-....._...._..........___,.__..__..._._........__..............____.........,,.........__..__..._._....,...._.__....._....._............... 2 0 100 200 300 400 500 Time After Break (s) Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case PCT and PCT Location Figure 15.6-15 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis VESSEL SIDE BREAK FLOW 70000 60000 50000 ...--Cf) ........... 40000 E
...Cl
_. Q) 0 0:::: 30000 3= 0 LL Cf) Cf) 0 20000
- 2:
10000 0
-10000 _....__...__...........----..__.___.___.__.__-.--....__...__...........----..___.___.___.__.__-.--_.__......__......_........._.
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 PUMP SIDE BREAK FLOW 25000 20000 U) E
...c
..::::::.- 15000 _..Q.) 0
~
3: 0 l..J_ 10000 U) U) 0
- ?:
5000 0
-5000 0 50 100 150 200 250 Time After Break (s) 1706863233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop Side Break Flow Figure 15.6-17 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis Intact Loop Broken Loop r I
-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 I I I I I I I I I I I I I I I I I I I I 0 I I I I 0 50 100 150 200 250 Time After Break (s) 120220936 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Broken and Intact Loop Pump Void Fraction Figure 15.6-18 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis VAPOR FLOW RATE IN CORE HOT ASSEMBLY CHANNEL 15 15 10 en E
....Cl 5 Cl) -+-'
c 0::: 3: 0 LL
"- 0 0
CL c
-5
+-......_.__.__._......-..........__.__.___..........._._....._.,........._.__._....._.,..........__.__.._...._,..........__.__._""'""--'
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-o--~1~1_-r~-1---.~~~~-..-~~~~...--~~~---.-~~~-----. 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 er 6
- ...::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 C f) 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 INTACT LOOP 2 ACCUMULATOR MASS FLOW RATE 2000 en 1500 _c E _,(!.)
~ 1000 3:
0 LL-cn en a
~ 500 0
-500 0 50 100 150 200 250 Time After Break (s) 1706863233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop 2 Accumulator Flow Figure 15.6-23 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis INTACT LOOP 2 SI MASS FLOW RATE 1400 1200 1000 E CL CTI Cl) 800
-+-'
0 0:::
~
0 LL CJ) 600 CJ) 0
- 2:
400 200 o--~~~~-r-~~~~~~~~---.-~~~~-.-~~~~ 0 50 100 150 200 250 Time After Break (s) 1706883233 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop 2 Safety Injection Flow Figure 15.6-24 Amendment No. 103
Comanche Peak Unit 2 ASTRUM BELOCA Analysis COLLAPSED LIQUID LEVEL IN AVERAGE CHANNEL 13 10 Q) 8 Q) __J
~
- l er 6
- ...::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 LIQUID LEVEL IN INTACT LOOP 2 DOWNCOMER 35 30 25 Q) ~ 20 ~
- I c:r
- ...::J
""t:l
~ 15 0...
0 0 (_) 10 5 o--~~~~....-~~~~.--~~~--r~~~~--.-~~~~~ 0 50 100 150 200 250 Time After Break (s) 171l686323J Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Limiting PCT Case Loop 2 Downcomer Collapsed Liquid Level Figure 15.6-26 Amendment No. 103
PBOT/PMID Box for the Comanche Peak Units 1and2 BELOCA Project 0.45 g 0.332, 0.418 co -a.
~
0 0.40 (.)
~ 0.310, 0.380 0 "O
- c E
0 0.35+-~~~~~~~~~~~-.-~~~~~~~~-1*~~~~~~~~~-1
=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 100 200 300 400 500 Time (s) 1928949020 929:943:366829/25-May-07 Comanche Peak Final Safety Analysis Report Units 1 and 2 Comanche Peak Unit 2 Lower Bound Containment Pressure Figure 15.6-28 Amendment No. 103
CORE PRESSURE, CORE FLOW, MIXTURE LEVEL, AND FUEL ROD POWER N HISTORY O<TIME<CORE COVERED 0 L T 0 R u ~
~
c u T M A p COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-29 CODE INTERFACE DESCRIPTION FOR SMALL BREAK MODEL Amendment No. 103
12 10 ........................... . ~ ~ L... Q) 3= 8 ..... . 0 a... L... cQ) c::
- .:::i 6 ..
4 ............................................. . 2 0 2 4 6 8 10 12 Elevation (ft) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-30 HOT ROD AXIAL POWER SHAPE UNIT 1AND2 Amendment No. 103
Injecting Intact Loop Flow Rate Sp1 I I ing Broken Loop Flow Rate 2500....---------------------------. 2000 c* en 1500 -e c....
- s en en e
a... 1000 . I. . . . ................................................... . I 500 I I
--- =~:::----~---~----~
~
o~ . . . . . . . . . . . . . . __......_........_._-T-....._.........___._....,........_........................................_...............-=....._.........---1 0 100 200 300 400 500 600 Safety Injection Flowrate (lbm/s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-31 PUMPED SAFETY INJECTION FLOW RATE, FAULTED LOOP SPILL TO RCS PRESSURE UNITS 1AND2 Amendment No. 103
Injecting Intact Loop Flow Rate Sp1 I I ing Broken Loop Flow Rate 2500 I I I I I I 2000 ********:*********:*********:*********:*********:*1******* I I I I I
. . . . . I
,_ 1500 ....... : ......... : ......... : ......... : ......... : . I ...... . 0
- rn I c... . I
...__ : I
~ : I
- J : I rn rn : I
~ . . . . : I a... 1000 * * * * * * * * .* * * * * * * * * * .* * * * * * * * * * .* * * * * * * * * * .* * * * * * * * * * :**I*
I *******
- I
- I
- I
- I
- I 500 ................................................. :: iI ....... .
- I
- I
- I
- I
- I o_[.LJL.l_:_::::~::;:~;:;~;:c~~~~=-~*-;;-~-;-~-~-;*~.LJL.lj 0 100 200 300 400 500 600 Safety Injection Flowrate (lbm/s)
COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-32 PUMPED SAFETY INJECTION FLOW RATE, FAULTED LOOP SPILL TO CONTAINMENT PRESSURE UNIT 1AND2 Amendment No. 103
2400 2200 2000 -0 -Ci5 c....
~
- I 1800 en en
~ 1600 a...
1400 1200 ........ :-,.~~""""'""" .......................................... . 1000 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-33 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 2-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .............................................................. .
~ 28 Q) -3 ~
- I
~
x 26 ........ . 24 .................. . 22-F-.=.,i=..;;;;;;....=.-=...;=.,;;;;~-=...;=..;;;;;;,..=L,.=..,=.,;;~;.,=-.=..i;;~;....=...=....i=..;;;;;;_;;;;;.-=...;=..;;;;"-=-=...;=...;;;;;,,.;;;;;i 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-34 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 2-INCH BREAK Amendment No. 103
640 .............................................................. . 620 'G:"
~
- I c 600
-+-"
Q) a.. E
~
580 560 540--~~~~~-r-~~~~~....-~~~~~-r-~~~~----t 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-35 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 2-INCH BREAK Amendment No. 103
2000 -0 -e
- en c...
1500
- I en en e
c.... 1000 500--~~~~~....-~~~~~..--~~~~----.~~~~~---1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-36 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 3-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... . 28 26 ....... . Q)
-3 ~
- I
-+-' 24 ....... .
x
~
22 20 18 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-37 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 3-INCH BREAK Amendment No. 103
700 ....................... . 650 .................................... .
~
- I
""§ 600 Q) a.. E ~ 550 ....................................... . 500 ........................................... . 450--~~~~~-r--~~~~~....-~~~~~-r-~~~~----t 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-38 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 3-INCH BREAK Amendment No. 103
1000--------------------------. 900 800 L L.
~
- I
-+-' ~
700 Q) c.... E Q) I-600 500 400-+-..........__,_.........,_._,_..........__,_,.........__._. . . . . . .-.-.. . . . . . _._. . . . . . ._._..........__,_,.........__._. . . . . . .-.-.. . . . . . _._~ 500 1000 1500 2000 2500 3000 3500 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-39 CLAD TEMPERATURE TRANSIENT AT PEAK CLAD TEMPERATURE ELEVATION UNIT 1: 3-INCH BREAK Amendment No. 103
0.2E-01 0.15E-01
~
en en Q) c: _.:::,i:. (.) 0.1E-01
- c I-Q)
""'C *x 0
0.5E-02 0 500 1000 1500 2000 2~00 3000 3500 4000 Time (sJ COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-40 MAXIMUM LOCAL ZR02 THICKNESS UNIT 1: 3-INCH BREAK Amendment No. 103
2000 c*en 1500 -ec....
- I en en e
a... 1000 500 o--~~~~~-r-~~~~~-r-~~~~~-r-~~~~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-41 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 4-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32 30 .......................................................... . 28 .......................................................... .
~
26 Q)
~ ~
- I
-+-' 24 . . . . . ..
x
~
20 ........... . 18 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-42 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 4-INCH BREAK Amendment No. 103
sooooo-r--------------------------, 500000 -E ..c ~ 400000 300000 ... 200000 .... 1OOOOO-+-__.___.___._____._...--....___..___.___._---.-____.____.,___..__.....__....,......__.___.____..____...___. 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-43 TOTAL REACTOR COOLANT SYSTEM MASS UNIT 1: 4-INCH BREAK Amendment No. 103
800 .............. . 'G:' 700
~
- I
-+-' ~
Q) c.... E
~ 600 ........................................................ .
500 .................... . 400--~~~~~-r-~~~~~..--~~~~~...-~~~~----1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-44 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 4-INCH BREAK Amendment No. 103
300 - Cf) E
....c Q) -+-'
0 a::: 200 3:: 0 LL. Cf) Cf) 0
- ii:
100 o---~~~~~--r-~~~~~---.-~~~~~---r-~~~~~---1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-45 TOP CORE STEAM MASS FLOW RATE UNIT 1: 4-INCH BREAK Amendment No. 103
Total Break Flow Total ECCS Flow 3000 2500 <n 2000 E
....c <L> ~ 1500 3::
0 LL. en en 0
- ?! 1000 500 ....
0 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-46 TOTAL BREAK FLOW AND TOTAL SAFETY INJECTION FLOW UNIT 1: 4-INCH BREAK Amendment No. 103
8000 -L L. I N
-+-' ..c I
- I 6000
-+-'
CD
<L>
0 (._) I-
<L>
en c:
~
4000
-+-'
c
<L>
- r::
2000 0 500 1000 1500 2000 2500 3000 3500 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-47 CLAD SURFACE HEAT TRANSFER COEFFICIENT AT PEAK CLAD TEMPERATURE ELEVA TION UNIT 1: 4-INCH BREAK Amendment No. 103
750 700 650 LL..
~
- I
-+-' ~
600 Q) c.... E
~
550 500 450 400--~~...........~~~......-.~~-r-~~.........,.~~~........-~~.......,....~~............. 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 ELEVA TION UNIT 1: 4-INCH BREAK Amendment No. 103
1100 1000 900 L L.
<L>
800
- 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
0.12E-01 0.1E-01
~
en en Q) O.BE-02 c:
...::.i:.
(..)
- .c I-Q)
""'C 0.6E-02 *x 0
0.4E-02 0.2E-02 0 500 1000 1500 2000 2~00 3000 3500 4000 Time (sJ COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-50 MAXIMUM LOCAL ZR02 THICKNESS UNIT 1: 4-INCH BREAK Amendment No. 103
2000 0 1500 -e
- en c...
- I en en e
a.. 1000 .... 500 ........ o--~~~.....-~~~ ..... ~~~ ..... ~~ ..... ~~~ ......~~~---1 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-51 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 6-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... . 28 -26 ~ Q) ~ 24 ..
~
- I x
~ * "9* * * ~.~
'P9. . . . . ~ , -* * * * *~ ,..., ,... **~ .~ ~ .,... **~ !"'f ~ .,... . . . . ~ , -. . . . . . . .
22 20 ....... . 18 ....... . 16-+-......_.._..........---T_.__.__._....._-.-....................._._--T"'_._....._......_.._,........___.__.__._-r-......_.._..........' - I 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-52 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 6-INCH BREAK Amendment No. 103
700 650 .......................................................... . 600 .......................................................... . 'G:' - 550
~
- I
~
Q) a.. E 500
~
450 .......................................................... . 400 ................................. . 350 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-53 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 6-INCH BREAK Amendment No. 103
2500 2000
- c. 1500
(./) a..
~
- J
(./) (./)
~
a.. 1000 . 500 ... 0 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-54 REACTOR COOLANT SYSTEM PRESSURE UNIT 1: 8.75-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... .
;:::::::: 28 24 ........... .
22 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-55 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 1: 8.75-INCH BREAK Amendment No. 103
650 .......................................................... . 600 .......................................................... . 550 'G:"
~
- I 15
.._ 500 Q) a..
E
~
450 400 ...... 350 ................ . 300--~~~-.-~~~-r-~~~-r---'~~~ ..........~~~...-~~--i 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-56 TOP CORE EXIT VAPOR TEMPERATURE UNIT 1: 8.75-INCH BREAK Amendment No. 103
2200 2000 -0 1800 -e
- en c...
- I en en e
c.... 1soo 1400 1200 ........~..~.~
..~."'!"'"**~.":'".!"'!'
** "'!"'.~
** t._ * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 1000--~~~~~....-~~~~~..--~~~~----.~~~~~---1 0 2000 4000 6000 8000 Time (s)
COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-57 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 2-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .............................................................. .
;:::::::: 28 Q) -3 ~
- I
-+-' ~
x 26 ...... . 24 22 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-58 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 2-INCH BREAK Amendment No. 103
640 .............................................................. . 620 'G:"
~
- I c 600
-+-"
Q) a.. E
~
580 560 540--~~~~~-r-~~~~~....-~~~~~-r-~~~~----t 0 2000 4000 6000 8000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-59 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 2-INCH BREAK Amendment No. 103
2000 -0 -e
- en c...
1500
- I en en e
c.... 1000 500--~~~~~....-~~~~~..--~~~~----.~~~~~---1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-60 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 3-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... . 26 ..... . Q)
-3 ~
- I
-+-' 24 ...... .
x
~
22 -~-~-~- 20 ........... . 18 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-61 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 3-INCH BREAK Amendment No. 103
800 ....................... . 750 700 ............ . 'G:"
~
- I 15
.._ 650 Q) a..
E
~
600 550 ..................................... . 500 ........................................ . 450--~~~~~-r--~~~~~....-~~~~~-r-~~~~----t 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-62 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 3-INCH BREAK Amendment No. 103
1100 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.............U....,.-J-J....L...J....,.....L...1....L..L...,-.L.J......L..L....,...J....L..L.J....,....L..J....L....L..,.-J-J....L..~ 0 500 1000 1500 2000 2500 3000 3500 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-64 MAXIMUM LOCAL ZR02 THICKNESS UNIT 2: 3-INCH BREAK Amendment No. 103
2000 c*en 1500 -ec....
- I en en e
a... 1000 ...... . 500 ............ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . o--~~~~~....--~~~~~....-~~~~----.~~~~~---1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-65 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 4-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 32 30 .......................................................... . 28 -26 ~ Q) ~ 24 ...
~
- I
-+-' x ~ -~- 22 20 .......... . 18 . . . . ...... . 16 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-66 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 4-INCH BREAK Amendment No. 103
500000.........--------------------------, 400000 - E ..c -;;; 300000 en 0 200000 1OOOOO-+-__.___.___._____._....--....___..___.___._---.-____.____.,___..__.....__....,......__.___.____..____...___. 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-67 TOTAL REACTOR COOLANT SYSTEM MASS UNIT 2: 4-INCH BREAK Amendment No. 103
800 .......... . 'G:" 700
~
- I
-+-' ~
Q) c.... E
~ 600 ....................................................... .
500 ................... . 400--~~~~~-r--~~~~~--~~~~~-r-~~~~----t 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-68 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 4-INCH BREAK Amendment No. 103
400 ... -_§ Cf) 300 100 ........... . o---~~~~~--r-~~~~~---.-~~~~~---r-~~~~~---1 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-69 TOP CORE STEAM MASS FLOW RATE UNIT 2: 4-INCH BREAK Amendment No. 103
Total Break Flow Total ECCS Flow 3000 2500 en 2000 E -....c Q)
-+-'
ci2 1500 31:: 0 LL. en en 0
- ?! 1000 500 ...
0 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-70 TOTAL BREAK FLOW AND TOTAL SAFETY INJECTION FLOW UNIT 2: 4-INCH BREAK Amendment No. 103
8000 .. . .. . .... . . 'G:" I N
-+-'
I I....
..c:
- I 6000 .. . .. . .... . .
-+-'
CD u Q ,) 0 I-I.... Q,) (/) c:
~
4000 .. . .. . .... . .
-+-'
0 Q,)
- r::
2000 .. . .. . .... . . 0 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-71 CLAD SURFACE HEAT TRANSFER COEFFIENT AT PEAK TEMPERATURE ELEVATION UNIT 2: 4-INCH BREAK Amendment No. 103
1000~------------------------. 900 ........... . 800 ............ . 700 ......... . 600 ....... . 500 .......................................................... . 400--~~~~~"""T"'""~~-~~"""T"'""~~-~~--r-~~-~~~ 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-72 FLUID TEMPERATURE AT PEAK CLAD TEMPERATURE ELEVA TION UNIT 2: 4-INCH BREAK Amendment No. 103
1200 ............ . a:;:- 1000
~
- I
-+-'
~
Q) c.... E ~ 800 ........ . 600 ...... . 4QO-+--'--'-__.~..._--.....__.__.___.~...-_.__.....__.__._----.~...__.__.....__._-I 0 1000 2000 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-73 CLAD TEMPERATURE TRANSIENT AT PEAK CLAD TEMPERATURE ELEVATION UNIT 2: 4-INCH BREAK Amendment No. 103
0.7E-01 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 3000 4000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-74 MAXIMUM LOCAL ZR02 THICKNESS UNIT 2: 4-INCH BREAK Amendment No. 103
2000 0 1500 -e
- en c...
- I en en e
a.. 1000 500 .......................................................... . o--~~~-.-~~~ ..... ~~~ ..... ~~ ..... ~~~ ......~~~---1 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-75 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 6-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... . 28 -26 Q) ~ 24 .....
~
- I
-+-' x ~ . . . .
* ~. **~. * * ~* * *~ ~ ~* . , * * *~ !lll't ~. **~ .~ flllt ~. **~ !""t ~ ~* * *~,..., ~. ~ * * *~
- 22 20 ....... .
18 .......................................................... . 16 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-76 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 6-INCH BREAK Amendment No. 103
650 .......................................................... . 600 .......................................................... . 'G:" - 550
~
- I
-+-" ~
Q) a.. E 500
~
450 ....... . 400 ......................................................... . 350--~~~-.-~~~-r-~~~-r---'~~~ ..........~~~...-~~--i 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-77 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 6-INCH BREAK Amendment No. 103
2000 0 1500 -e
- en c...
- I en en e
a.. 1000 . 500 .......................................................... . o--~~~.....-~~~ ..... ~~~ ..... ~~ ..... ~~~ ......~~~---1 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-78 REACTOR COOLANT SYSTEM PRESSURE UNIT 2: 8.75-INCH BREAK Amendment No. 103
Core Mixture Level Top of Core (22.0778 ft) 30 .......................................................... . 28 24 ... 20 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-79 CORE MIXTURE HEIGHT AND TOP OF CORE UNIT 2: 8.75-INCH BREAK Amendment No. 103
650 .......................................................... . 600 .......................................................... . 550 'G:"
~
- I 15
.._ 500 Q) a..
E
~
450 400 ..... 350 ................ . 300--~~~-.-~~~-r-~~~-r---'~~~ ..........~~~...-~~--i 0 500 1000 1500 2000 2500 3000 Time (s) COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-80 TOP CORE EXIT VAPOR TEMPERATURE UNIT 2: 8.75-INCH BREAK Amendment No. 103
CPSES/FSAR Figures 15.6-7A.B.C.D thru 15.6-89 have been deleted 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 I 84 15A-l Amendment 84 February 28, 1992
CPSES/FSAR APPENDIX 15A HAS BEEN DELETED I 84 15A-l Amendment 84 February 28, 1992
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 In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
CPSES/FSAR FIGURES II.B.2-1 THROUGH II.B.2-24 THESE FIGURES HAVE BEEN DELETED In AMENDMENT 77 SEPTEMBER 8, 1989
t COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS I ond 2 POST LOCA ACCESS ROUTE IA FIGURE 11.B.2*25
I I COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 18 FIGURE 11.8.2-26 0 E G 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
COMANCHE PEAK S£.~ FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 2 FIGURE 11.8.2-30 c H
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 3 & 4 FIGURE 1l.B.2-31 I 1!3231000 A B c 0 E F H
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS t and 2 POST LOCA ACCESS ROUTE 5 FIGURE I l.B.2-32 D H
5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 6 FIGURE I IB.2-33 c ti
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 1 & 8 FIGURE 1l.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
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 I 11B2~6100 A B c D E F
5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT 6 UNITS 1 and 2 POST LOCA ACCESS ROUTE 12 FIGURE 1l.B.2-37
£ F H
CPSES/FSAR FIGURE II.B.2-38 THIS FIGURE HAS BEEN DELETED Amendment 93 February l, 1995
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 6 POST LOCA ACCESS ROUTE 14 SHEET 1 OF 3 FIGURE I 1.B.2-39 118239000 A B c D 0 H
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 6 POST LOCA ACCESS ROUTE 14 SHEET 2 OF 3 F IOURE 1l.B.2-39 116239100 B I) E F H
I i 2 3 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 6 POST LOCA ACCESS ROUTE 14 SHEET 3 OF 3 FIGURE ll.B.2-39 B c 0 E F c H
B c D t E F G H 2 5 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 118240100 A B c D E F H
B C D £ F C H -~'~~~~~~~~~~----~------------------~--------~-----------------------~~---------~~~--~--------~~~~----~--------------------------------------~~----.;I_ t 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 118240200 A 8 c E F H
A B 0
* [ H J
5 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 A B c 0 E G H
c 0 ll COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POST LOCA ACCESS ROUTE 17 SHEET 1 OF 1 FIGURE 8 c
A B c 0 E H RM. NO. 2 4 5 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 6 POST LOCA ACCESS ROUTE 19 SHEET 1 OF 3 FIGURE 11.8.2-42.1 I IIB242100.0<~N A e c 0 E H
A t E I I 2 3 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 ond 2 POST LOCA ACCESS ROUTE 19 SHEET 2 OF 3 FIGURE 118242200.DGN A I c
- I
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
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 ANO 2 POST LOCA ACCESS ROUTE IA FIGURE 11.6.2-43 118243000
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IA FIGURE 1l.B.2-44 118244000
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IB FIGURE 11.B.2-45 118245000
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IB FIGURE 11.B.2-46
CPE COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE IC FIGURE 11.B.2-47 116247000
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 2 FIGURE ll.B.2-50
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 POST LOCA ACCESS ROUTE 2 FIGURE 11.B.2-51 118251000
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;--------------------- w~cc I I I I I I I I I
-----------------------------J
__________@ :::J 1-"'-"~""- 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 '~--l_
,,~
1---l"""'L-------=f ..:: ~lJ**-1 FAJ- . . Tank
~ For Unit 2 Only - - -
-...P..
F.O. -f t- L.O. f Al f.O; . F.O. For Unit 2 Only - COMANCHE PEAK S.E.S. FNAL SAFET'( ANALYSIS REPORT UNITS 1 and 2 Auxilfary Feedwater System S1mplf f1ed flow Dtagra_m_ _ _ Amendment 102 Fl(UlE IJ.E.1.1-1
NON- INDEPENDENT FAILURES J INDEPENDENT FAILURE OF TRAINS TEST OR MAINTEl'AriCE ASSOC!ATEJ S:JPPl Y 110 TRAlN TRAIN TU?B!NE LINE STA;\ TRAIN VALVES SIGMLS FldL FA!~ FAILS pk Note 1 J I CL~;rn J NO l l?V>iPl FAIL I VALVES
']
rnIL
~
AUTC FAILS TO I EL~~KEO S!Gi;f1L RUt*f: 8 p d Pb "r
,/I",
Q See Sheet 5
/l~
Sheet 4 v Val.H:S d'<>Sign-ed are shown on Note l ( CONTROL \ C!RCUIT COMANCHE PEAK S. E. S
~~ FINAL SAFETY ANALYSIS REPORT pi UNITS 1 and 2
?j pc pd ?e p9 Ph JANUARY 30, 1981 FIGURE ll.E.Ll-2 {S,eet 1 of 5)
!NSUFF!CENT
- FLOW TO THREE OF FO:J'R SHAM GrnrnATORS l~~DEPLNDE~T TEST OR NON-INDEPENDENT MA t NTENJ'.NCE FAILURE ASSOCIATED FAILURES OF TRAINS FAllURES SLlPPL Y NO TRAIN TRldll TURBINE OTllER LINE TWD START A TRAIN VALVES TR,.\H*S SIGNALS FAIL FAll fArLS BLOCKED FA!l Note 3 J
Pt;MP VAl'llS VALVLS PUMP NO TRftJN FAJL CLOSED CLOSEO FA!l Au:o TO OR OR TO FtdlS SIGtiAL Rl'i RliN Note Note 2 See Sfleet 5 Sheet 4 probabii ities Pa thru Pr l !. £ '1.1-1. ( NO
\. STEAM COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AFWS Tree loss JANUARY 30, 1981 FIGURE n.E.l :-2 (Sheet 1 d Si
INSUfflCENT FLOW TO THREE OF FOUR STEAM GENERATORS NON-INDEPENDENT I!lDEPENDENT FAILURE FAILURE OF TURBINE TURElNE TRAIN TRAHi VALVES PUMP NO CLOSED FAIL START OR TO SIGNALS BLOCKED RUfi JANUARY 30, 1981 Values assigned to probabilities Pa thru Pr See Sheet 4 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 A~ P. FIGURE LE. l. l-2 (Sheet of 5) J
3 Of 4 l!NES BLOCKED l, 2 ~ 3 I, 2 & 4 BLOCKED BLOCKED Note 4 Nott> 4 tlcte 4 ONE BLOCKED Note 5 Note 5 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) Po Pc ?p ?p P, pn Pm
VALVES CLOSED MOTOR TRAIN l OF 2 LHlES BLOCKED l OR 3 2 OR 4 BLOCKED BLOCKED I r1ote 6 p 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 AF~S Simplified Fault Tree JANUARY 30, 1981 FIGURE ILE.1.1-2 (Sheet 5 of 5)
CONTAINMENT HIGH RANGE RADIATION MONITOR (TYP) IRE6290A (EL.917'-9") I RE 62 908-----+-~-J (EL.910'-9")
-------+---
¢.CONTAINMENT---
-S EL. 905'-9 11 NOTE: UNIT 1 MONITORS SHOWN SAME FOR UN IT 2
REFERENCE:
- 1. FSAR FIG. 1.2-15 DECEMBER 10, 1982 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 CONTAINMENT HIGH RANGE RADIATION MONITOR LOCATIONS FIGURE II.F - 1
CPSES/FSAR Figure III.A.1.2-1 has been deleted I 95 Amendment 95 February 2. 1998
A B 0 E F G H INTEGRATED ERF COMPUTER SYSTEM SENSOR SIGNALS FROM ONSI METEOROl_OGICAI DATA 2 SAFETY SYSTEM 2 SIGNf.! S 3 3 UNIT EOF TECHNICAL" SUPPORT CF'JTER 5 5 OISPI AY DI SPLA "* AMEIOJIENT 83 DECEMBER 13, 1991 FIGURE GENERATED rGR FSAR O"lL"' BASED O~ ORAW:NG 6 COMANCHE PEAK S.E.S. 6 FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 INTEGRATED ERF COMPUTER SYSTEM FIGURE 111.A.l.2-2 I FIG03A122.DGN A B c D
- E F G H
CPSES/FSAR Figure III.A.1.2-3 has been deleted I 95 Amendment 95 February 2. 1998
CPSES/FSAR Figure III.A.l.2-4 has been deleted I 95 Amendment 95 February 2. 1998
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 ing. 1 NOTE 6 - The probability of steam generator 2 being blocked is the same as that for stearn generator 1. JANUARY 30, 1981}}