ML22038A174
| ML22038A174 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/01/2022 |
| From: | Luminant, Vistra Operations Company |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CP-202200007, TXX-22004 | |
| Download: ML22038A174 (547) | |
Text
{{#Wiki_filter:CPE A B C D E F G H REV DWN CHKDAPVD REMARKS VALVE ACCESSORIES, DEFINITIONS PIPE AND EQUIPMENT ACCESSORIES DLK GAW THIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE CP-28 09-25 09-25 VALVE BODY TYPE AND ABBREVIATIONS (CONTINUED) EQUIPMENT (CONTINUED) VALVE LOCATION NUMBER IDENTIFICATION SYSTEM 2018 2018 FDA 2018-000081-01-00 PER SK-0001-18-000081-01-00. CLASSIFICATIONS 152 303 1CS-0001 2CS-0001 XCS-0001 GATE VALVE STEM LEAKOFF PRESSURE CLASS TRANSITION UNIT 1 UNIT 2 UNIT COMMON ACCUMULATOR SYSTEM SYSTEM SYSTEM INDICATES "ANS" SAFETY CLASS (1, 2 AND DOUBLE DISC GATE VALVE BELLOWS SEAL BLENDER LOCATION NUMBER LOCATION NUMBER LOCATION NUMBER 3) OR CPSES PIPING CLASS 5 (NON-NUCLEAR SAFETY) ITEM LINE DESIGNATIONS INDICATES CPSES PIPING CLASS G 1 GLOBE VALVE CAPPED STEM PENETRATION (ANS NON-NUCLEAR SAFETY) 1 6-CC-1-01-152 R-3 (R=POTENTIALLY RADIOACTIVE NUCLEAR PIPING) 6-CC-1-02-152G R (R=POTENTIALLY RADIOACTIVE NON-NUCLEAR PIPING) NOTES: EXTENSION STEM M NEEDLE VALVE BASKET STRAINER NOMINAL SIZE INDICATES CHANGE IN ANS OR PIPING CLASS THROUGH SHIELD WALL OR FLOOR 1. THESE NOTES INDICATE GENERAL REQUIREMENTS APPLICABLE TO ALL V MIXER SYSTEM UNIT NUMBER DESIGN DRAWINGS. EXCEPTIONS AND AMENDMENTS TO THESE NOTES
-151R-5 WILL BE INDICATED ON THE APPLICABLE DRAWINGS.
EXTENSION STEM S SEPARATOR UNIT NUMBER (TYP) 1 -UNIT 1 2. ALL PIPING SHALL BE IN ACCORDANCE WITH THE REQUIREMENTS OF THE PLUG COCK VALVE NO WALL OR FLOOR PENETRATION LINE NUMBERS 2 -UNIT 2 LATEST ISSUE OF THE APPLICABLE WESTINGHOUSE SPECIFICATION 6678864 PIPING CATEGORIES AND G & H SPECIFICATIONS 2323-MS-43A, 43B, 44A, 44B AND 100. DOUBLE X -COMMON FC FAIL CLOSED SAFETY CLASS NOTE BASKET STRAINER 3. FIELD WELD END PREPARATION FOR PIPING SHALL BE IN ACCORDANCE (NUCLEAR PIPING ONLY) 19 BALL VALVE -151R-5 WITH THE APPLICABLE GIBBS & HILL DWGS XB-2323-M-555 THROUGH 560. (TYP) D EITHER INDICATES CHANGE IN SAFETY FO FAIL OPEN 4. PIPING AND EQUIPMENT SHALL BE INSULATED IN ACCORDANCE WITH V CLASS FOR VENT, DRAIN, TEST AND T STEAM TRAP SHAFT SEAL LINE CODING SAMPLE CONNECTIONS ON SAFETY G & H SPECIFICATIONS 2323-MS-30 AND MS-31. PUMP DIAPHRAGM VALVE FAI FAIL AS IS CLASS PIPE. 5. ALL DIMENSIONS SHOWN ARE IN FEET AND INCHES. PIPE SIZES ARE MAIN PROCESS FLOW LINES INDICATED BY THEIR NOMINAL DIAMETER, IN INCHES, UNLESS OTHERWISE JOHNSON SCREEN (OUT OF SYSTEM AND UNIT TWO DASHED) NOTED. LC LOCKED CLOSED SEE NOTE 22 AND 23 6. FOR PLUMBING SYMBOLS AND NOTES SEE DRAWINGS M1-0236 AND M1-0236-A. NOTE HERMETICALLY SEALED VALVE 19 7. LOCATIONS, ELEVATIONS, DIMENSIONS, ETC. SHOWN ON DESIGN DRAWINGS LOCKED CLOSED DURING SECONDARY PROCESS FLOW LINES LC-2 SEE NOTE 24 Y-STRAINER D ARE FOR PIPES IN COLD AND ERECTED POSITION. CONSIDERATION HAS UNIT 2 CONSTRUCTION (OUT OF SYSTEM AND UNIT TWO DASHED) (TYP) BEEN GIVEN AND PROVISIONS HAVE BEEN MADE FOR THERMAL EXPANSION POSITIVE DISPLACEMENT UNDER OPERATING CONDITIONS. ANGLE VALVE LO LOCKED OPEN SEE NOTE 23 PUMP
- 8. THE PIPING FABRICATOR SHALL MAKE ALLOWANCES FOR GASKET F FILTER PNEUMATIC INSTRUMENT LINES LINE SYMBOLS THICKNESSES AND WELDING GAPS NOT INDICATED ON THESE DRAWINGS.
SO SEALED OPEN SEE NOTE 25 AF -AUXILIARY FEEDWATER 9. CS AND SS VALVES 2" AND SMALLER WILL BE GLOBE RATED AT 600 LBS THREE WAY VALVE BR -BORON RECYCLE SOCKET WELD END SCH 80 UNLESS NOTED OTHERWISE. TEMPORARY CONE TYPE INSTRUMENT AIR SUPPLY CA -COMPRESSED AIR-SERVICE AIR 2 LIP LOCKED IN POSITION SEE NOTE 23 STRAINER CENTRIFUGAL FIXED PRESSURE CB -CONTROL FLUID HOLD-UP SYSTEM
- 10. FOR VENTILATION SYMBOLS AND NOTES SEE DWG MI-0313. 2 BLACKED IN VALVES ARE NORMALLY PUMP CC -COMPONENT COOLING WATER 11. PIPE BENDS SHALL BE IN ACCORDANCE WITH G & H SPECIFICATIONS CLOSED. VALVE POSITION SHOWN IS CD -CHEMICAL FEED DRAIN 2323-MS-43A, 43B, 44A OR 44B AS APPLICABLE.
AS IT IS DURING POWER OPERATION. NC NORMALLY CLOSED OPEN FUNNEL DRAIN CF -CHEMICAL FEED VALVES THAT ARE NOT BLACKENED IN ELECTRICAL SIGNALS 12. PIPING FABRICATOR TO PROVIDE COMPANION FLANGES TO AGREE WITH SYSTEM CG -CARBON DIOXIDE GAS/ARGON GAS ARE NORMALLY "NOT CLOSED". THEY CERTIFIED MANUFACTURERS EQUIPMENT DRAWINGS EXCEPT WHERE NO NORMALLY OPEN CH -CHILLED WATER MAY BE OPEN OR THROTTLE. VALVE SMALL CANNED INDICATED ON THE COMPOSITE DRAWINGS. CI -COMPRESSED AIR INSTRUMENT AIR POSITIONS (CLOSED OR NOT CLOSED) MOTOR PUMP ARE DEPICTED ON THESE DRAWINGS CL -CHLORINATION 13. ALL VALVES SHOWN TO HAVE LEAKOFF CONNECTIONS SHALL BE INSTRUMENT CAPILLARY CO -CONDENSATE AND CONTROLLED BY OPERATING TC TEST CONNECTION PERMANENTLY PIPED TO THE APPROPRIATE DRAIN POINT. ALL OTHER VENT STACK TUBING CP -CONDENSATE POLISHING PROCEDURES. VALVES WITH LEAKOFFS WILL HAVE LEAKOFF CONNECTIONS CAPPED. CS -CHEMICAL VOLUME CONTROL AND BORON THERMAL REGENERATION TD TEST DRAIN CT -CONTAINMENT SPRAY 14. ON VENTS AND DRAINS WHERE A DOUBLE BARRIER/ISOLATION IS REQUIRED FAN, BLOWER, OR CHECK VALVE CV -CONDENSER VACUUM AND WATER BOX PRIMING THE SECOND BARRIER/ISOLATION CAN BE " OR " CLASS 2505 COMPRESSOR INSTRUMENT LINE R CW -CIRCULATING WATER TUBING/CONNECTOR WITH SWAGELOK CAPS. THIS EXCLUDES ASME CLASS 1 TV TEST VENT DC -DOMESTIC COLD WATER PIPING. STOP CHECK VALVE LOUVER DD -DEMINERALIZED AND RCS MAKE-UP WATER
- 15. IN SAFETY CLASS 1 PIPING A FLOW RESTRICTION IS REQUIRED, IN (NORMALLY OPEN) DDW -DOMESTIC DEMINERALIZED WATER V VENT ELECTRICAL HEAT TRACING " PIPING, TO ALLOW TRANSITION FROM SAFETY CLASS 1 TO SAFETY DH -DOMESTIC HOT WATER DHR -DOMESTIC WATER-HOT RECIRCULATION CLASS 2. TYPICAL FLOW RESTRICTOR SHOWN.
DO -DIESEL GENERATOR FUEL OIL " SOCKET WELD CONNECTION EQUIV TO 6,000 LB STOP CHECK VALVE VERTICAL CANNED D DRAIN EH -TURBINE CONTROL FLUID AS A HALF COUPLING DRILLED FOR 0.375 ID (NORMALLY CLOSED) FORWARD-REVERSE PITOT PUMP SS CS TRANSITION PIECE EX -EXTRACTION STEAM (STAINLESS TO CARBON STEEL) FD -FLOOR DRAINS DH DRAIN HEADER BY FP -FIRE PROTECTION BUTTERFLY VALVE INSTR FR -FEEDWATER HEATER VENTS, RELIEF AND DRAINS 0.375 FLANGED OR WAFER TYPE (NORMALLY OPEN) CONTR SS CS FW -STEAM GENERATOR FEEDWATER MAX TRANSITION PIECE (TYPICAL FOR FLANGED CONN.) FX -DIVERSE AND FLEXIBLE STRATEGIES (FLEX) PIPE AND EQUIPMENT ACCESSORIES BY GH -WASTE PROCESSING-GAS PIPING FLOW NOZZLE BUTTERFLY VALVE GS -TURBINE GLAND STEAM AND DRAIN FLANGED OR WAFER TYPE CONTR HD -HEATER DRAINS (NORMALLY CLOSED) HG -HYDROGEN GAS 12 RUPTURE DISC SHIELD WALL PENETRATION LO -TURBINE LUBE OIL 3 LT -LEAK TEST 16. ALL ORIFICE PLATES USED WITH FLOW METERING INSTRUMENTATION IN 3 POST INDICATOR VALVE MS -MAIN STEAM REHEAT AND STEAM DUMP THE NSSS SCOPE TO BE SUPPLIED BY WESTINGHOUSE. ALL ASSOCIATED FLOW RESTRICTION ANNUBAR FLOW FLANGE CONNECTION NG -NITROGEN GAS ORIFICE FLANGES TO BE SUPPLIED BY OTHERS. ORIFICE FLANGES FE FT ORIFICE MEASUREMENT (PIPING OR EQUIPMENT) OG -OXYGEN GAS SHALL NOT BE LESS THAN 300 LB RF WITH FLANGE TAPS. TC PS -PROCESS SAMPLING PRIMARY PLANT FIRE PROTECTION 17. FOR ALL INSTRUMENTATION CONNECTIONS WITH A " VALVE INSTALLED, PW -POTABLE WATER POST INDICATOR VALVE " RC -REACTOR COOLANT AND RTD BYPASS THE PIPING SIZE IS ", AND THE PIPING PRESSURE-TEMPERATURE SIGHT FLOW BY PIPING CONTR BY INSTR CONTR TEST CONNECTION LOCATION RH -RESIDUAL HEAT REMOVAL CLASS IS IDENTICAL TO THE CLASS OF PIPE TO WHICH IT IS CONNECTED. INDICATION SA -AUXILIARY STEAM 18. FLOW DIRECTION FOR TEST CONNECTIONS, VENTS AND DRAINS ARE BY SB -STEAM GENERATOR BLOWDOWN AND CLEAN-UP BLOW OFF VALVE INSTR TV ASSUMED AWAY FROM THE PROCESS PIPING FOR VALVE ORIENTATION. FT SD -STORM DRAINS CONTR FOR HERMETICALLY SEALED VALVES SUCH AS ROCKWELL-EDWARDS THERMAL SLEEVE SF -SPENT FUEL POOL COOLING AND CLEAN-UP
" TEST VENT LOCATION HERMAVALVES, THE PREFERRED VALVE FLOW ORIENTATION IS AWAY FROM SI -SAFETY INJECTION BY THE PROCESS PIPING FOR VENT, DRAIN, TEST VENT, AND TEST DRAIN VALVES SN -SANITARY WASTE DRAINS PIPING AND TOWARD THE PROCESS PIPING FOR TEST CONNECTION VALVES.
"Y" PATTERN VALVE CONTR SO -GENERATOR SEAL OIL SS -SECONDARY PLANT SAMPLING HOWEVER, INSTALLATION IN EITHER ORIENTATION IS ACCEPTABLE.
BLIND FLANGE ORIFICE TYPE FLOW IMB OMB MISSILE BARRIER PENETRATION ST -SEWAGE TREATMENT 19. APPROPRIATE DRAIN SUBSYSTEM(S) SHALL BE IDENTIFIED FOR ALL DRAIN MEASUREMENT SW -SERVICE WATER FLOAT CHECK VALVE POINTS BY GENERAL NOTE OR DRAIN POINT LEGEND OR BOTH. TO -TURBINE OIL PURIFICATION FE INSTRUMENTATION AND CONTROL TW -TURBINE PLANT COOLING WATER 20. FOR ADDITIONAL INSTRUMENTATION AND CONTROL SYMBOLS SEE THE CAPPED STUB SYMBOLS W BY OTHERS M1-2200 SERIES DRAWINGS. VA -HEATING AND VENTILATION SYSTEM (NOTE 20) SPLIT OF RESPONSIBILITY VD -VENTS AND DRAINS 21. FOR INSTRUMENTATION SAFETY CLASS CHANGES REFER TO VH -VENT HEADER AIR RELEASE VALVE SPECIFICATION CPES-I-1018. WD -POWDERED RESIN DISPOSAL BOUNDARY OF RADIOACTIVE WASTE WM -WASTE MANAGEMENT SYSTEM 22. VALVES WHICH ARE LOCKED CLOSED FOR CONTAINMENT ISOLATION REDUCER FI EITHER MANAGEMENT SYSTEMS WP -WASTE PROCESSING LIQUID ARE DESCRIBED IN DBD-ME-013 AND SHALL BE CONTROLLED IN LOCAL MOUNTED INSTRUMENT WITH REPRESENTS RWMS WR -WATER TREATMENT DRAINS ACCORDANCE WITH TECHNICAL SPECIFICATION 3.6.3. SINGLE SERVICE AND FUNCTION VACUUM BREAKER A FLOW WS -TURBINE WATER SPRAY INDICATOR 23. VALVES WHICH ARE LOCKED FOR OTHER THAN CONTAINMENT WT -WATER TREATMENT EXPANSION JOINT AREA BOUNDARIES ISOLATION ARE DESCRIBED IN THEIR RESPECTIVE SYSTEM DESIGN 3 .2 - 1 XG -PLANT GAS BOARD REAR MOUNTED BASIS DOCUMENT AND SHALL BE CONTROLLED IN ACCORDANCE INSTRUMENT WITH PRECAUTIONS AND LIMITATIONS THEREIN. 4 LEGEND 24. VALVE IS LOCKED CLOSED DURING UNIT 2 CONSTRUCTION/ UNIT 1 4 VARIABLE CAPILLARY PRESSURE QUICK DISCONNECT COUPLING WATER METER REDUCING ELEMENT OPERATION TO SERVE AS UNIT 1/ UNIT 2 CROSS TIE ISOLATION. BOARD FRONT MOUNTED REFERENCE BLOCK SYSTEMS CONTROL OF VALVES AND LOCKS SHALL BE BY UNIT 1 OPERATORS. INSTRUMENT NORMALLY ONLY LINES WITHIN SYSTEMS ARE NUMBERED, RCS -REACTOR COOLANT SYSTEM 25. VALVE IS SEALED OPEN. ALL AIR AND POWER CONNECTIONS ARE FOOT VALVE WITH FIRE HYDRANT REMOVED AND THE VALVE IS SECURED IN THE OPEN POSITION. HOSE CONNECTION HOWEVER IT IS ACCEPTABLE TO PROVIDE THE LINE/ CVCS -CHEMICAL AND VOLUME CONTROL SYSTEM STRAINER SIS -SAFETY INJECTION SYSTEM F S AR F IGURE LOCATION NUMBER FOR A SYSTEM CHANGE. NOTES: (CONTINUED BELOW) RHRS -RESIDUAL HEAT REMOVAL SYSTEM SYSTEM BRS -BORON RECYCLE SYSTEM DIAPHRAGM SEAL REFERENCE BTRS -BORON THERMAL REGENERATION SYSTEM LOOP SEAL TRAP VESSEL MANWAY SFPCS -SPENT FUEL POOL COOLING SYSTEM DIVERTER VALVE WPS(L) -WASTE PROCESSING SYSTEM (LIQUID) DASHED LINE IF -WASTE PROCESSING SYSTEM (GAS) DIRECTION WPS(G) SPARGER OUT OF SYSTEM SECONDARY C-CONDUCTIVITY OF FLOW CCS -COMPONENT COOLING WATER SYSTEM (INSIDE VESSEL) OR UNIT TWO SAMPLING SYSTEM FLEXIBLE CONNECTION T-TEMPERATURE SS -PROCESS SAMPLING SYSTEM M1-0222-0 (PRIMARY PLANT) SAFETY AND RELIEF VALVE P-PRESSURE LOC: A-6 F-FLOW CSS -CONTAINMENT SPRAY SYSTEM FIRST LETTER IN BALLOON L-LEVEL DWS -DEMINERALIZED WATER SYSTEM INDICATES PROCESS VARIABLE. R-RADIOACTIVITY RMWS -REACTOR MAKE-UP WATER SYSTEM
REFERENCES:
FD FLOOR DRAIN SPRAY NOZZLES DRAWING DRAWING SEE REF 1 FOR COMPLETE A-ANALYSIS RCPS -REACTOR CONTROL AND PROTECTION SYSTEM COORDINATES NUMBER EQUIPMENT LIST GLOBE VALVE OR BALL VALVE TAG NUMBERING SYSTEM. X-TRIP H-HAND LINE LIST EQUIPMENT M-MODIFIER EQUIPMENT MOTOR LIST BREAKDOWN ORIFICE D-DENSITY PRT -PRESSURIZER RELIEF TANK VALVE LIST T HIS DRAWING CREAT ED ELECT RONICALLY HERMETICALLY SEALED VALVE FROM AUXILIARY DASHED LINE IF OR BALL VALVE FEEDWATER OUT OF SYSTEM OR UNIT TWO RWST -REFUELING WATER STORAGE TANK SPECIALTY LIST SYSTEM RMWST -REACTOR MAKE-UP WATER STORAGE TANK A-ALARM PIPING SPECIFICATION SHEETS M1-0206-0 -GAS DECAY TANK TEMPORARY STRAINER V-VALVE DAMPER OR LOUVER GDT BALANCING VALVE LOC: F-5 INSTRUMENTATION AND CONTROL DIAGRAM E-ELEMENT FDT -FLOOR DRAIN TANK S-SWITCH RCDT -REACTOR COOLANT DRAIN TANK VERTICAL U-TUBE SUCCEEDING LETTERS IN THE FOLLOWING REFERENCES APPLY TO NSSS SCOPE FLOW DIAGRAM ONLY W-WELL RHT -RECYCLE HOLD-UP TANK STEAM GENERATOR BALLOON INDICATE FUNCTION VALVE OPERATOR TYPES T-TRANSMITTER SDT -SHUTDOWN TANK 5 SPECTACLE FLANGE SEE REF 1 STANDARDS FOR G-GLASS SRST -SPENT RESIN STORAGE TANK A. W WASTE PROCESSING PANEL, DWG 271C594 5 COMPLETE TAG NUMBERING Q-POWER SUPPLY TO BE INSTALLED WITH UNIT 1 FURNISHED BY VENDOR WHT -WASTE HOLD-UP TANK B. W ANNUNCIATOR LIST, DWG NUMBER SYSTEM. I-INDICATING AIR DIAPHRAGM R-RECORD OR PRINT C. W MASTER COMPUTER INPUT/OUTPUT LIST WELD CAP C-CONTROL GENERAL D. W RADIATION MONITORING SYSTEM, DWG 206C860 Y-TRANSDUCER M W OR E. W PROCESS CONTROL BLOCK DIAGRAMS, DWG NUMBER STRAIGHT TUBE -WESTINGHOUSE ELECTRIC MOTOR W HEAT EXCHANGER F. W ELEMENTARY WIRING DIAGRAMS, DWG NUMBER CONTAINMENT A-E -ARCHITECT ENGINEER (GIBBS & HILL) ISOLATION CAP ATM -ATMOSPHERE G. W CONTROL AND ELECTRICAL STANDARDS SECTION 1.1 S TYPICAL INSTRUMENT CONNECTIONS IMB -INSIDE MISSILE BARRIER APPLICATION OF SYMBOLS FOR INSTRUMENT DIAGRAMS. SOLENOID OMB -OUTSIDE MISSILE BARRIER SECTION 3.0-INSTRUMENT INSTALLATION DETAILS STRONGBACK IRC -INSIDE REACTOR CONTAINMENT H. W VALVE REFERENCE GUIDE, E-SPEC G-677473 REV U-TUBE 2" " " ORC -OUTSIDE REACTOR CONTAINMENT HEAT EXCHANGER H2 -HYDROGEN SUPPLY I. W MATERIAL SPECIFICATION PIPE AND FITTINGS, E-SPEC G-678854 REV THREADED OR SOCKET PISTON 1" N2 -NITROGEN SUPPLY WELDED CAP J. W SYSTEMS STANDARD DESIGN CRITERIA TYPICAL REPRESENTATION OF UNIT 2 TYPICAL REPRESENTATION OF G LT LG LG EQUIPMENT VENDOR PACKAGE NOTES: (CONTINUED) MANUAL GEAR OPERATED EDUCTOR OR EJECTOR COIL TYPE 26. THREADED PIPE CAPS MAY BE ADDED TO OR REMOVED UNDER 2" 1" " " HEAT EXCHANGER ADMINISTRATIVE CONTROLS FROM THE NON-SAFETY RELATED PIPING EXTENSION STEM BY PIPING BY INSTR DOWNSTREAM OF ALL VENT, DRAIN AND TEST CONNECTION VALVES EXCEPT AS REQUIRED OPERATOR CLASS 1 TO CLASS 2 CONTR (TYP) CONTR (TYP) BY NOTE 27. WHERE APPLICABLE, TUBING AND FLEX HOSE MAY BE DISCONNECTED FLOW RESTRICTOR FROM THE PIPE NIPPLE AND LEFT SUPPORTED IN PLACE TO ACCOMMODATE (SPECIAL BRANCH THE INSTALLATION OF A THREADED PIPE CAP, OR TUBE CAP APPLIED PER NOTE 14. CONNECTION) VENT CONDENSER QUICK OPENING 2" 1" 27. LOCAL VENT, DRAIN AND TEST CONNECTION VALVES WITHIN THE CONTAINMENT PENETRATION BOUNDARY (SEE NOTE 14) ARE REQUIRED TO BE CAPPED WHERE SHOWN ON SYSTEM FLOW DIAGRAMS USING A "CONTAINMENT ISOLATION CAP" SYMBOL. THESE CAPS ARE ADMINISTRATIVELY CONTROLLED IN ACCORDANCE WITH SELF CONTAINED PRESSURE REGULATOR IMMERSION HEATER LC LS OPERATING PROCEDURES. LUMINANT 6 (STEAM OR ELECTRICAL) 6 EXTERNAL MONITORING DEVICE
- 28. MINIMUM REQUIREMENTS FOR PROCESS TEMPERATURE AND/OR FREEZE PROTECTION CPNPP 2" 1" ARE TO BE MAINTAINED FOR PIPING TO BE HEAT TRACED AS SHOWN ON THE THROTTLING APPLICABLE FLOW DIAGRAMS. FOR PHYSICAL DETAILS OF HEAT TRACING, GLEN ROSE, TEXAS BY PIPING BY INSTR REFER TO E1/E2-1500 SERIES DRAWINGS.
CONTR (TYP) CONTR (TYP) DISC-LESS CHECK VALVE, 29. FLOOR DRAIN COVERS AND FLOOR DRAIN STRAINERS LOCATED IN THE PROCESS ACTUATED AIR INTERNALS REMOVED FLOOR DRAIN CUPS ARE BELOW THE LEVEL OF DETAIL SHOWN ON DIAPHRAGM OPERATOR WITH LEVEL VALVE POSITIONER DESIGN DRAWINGS AND MAY BE REPLACED WITH EITHER A FLOOR MECHANICAL DRAIN TOOL OR SOCK FILTERS OR BOTH AS DEPICTED IN DCN 11914. ENGINEERING REVIEW IS REQUIRED TO REPLACE THE SOLID DRAIN SYMBOLS & NOTES INSTRUMENT ACTUATED AIR COVERS WITH A FLOOR DRAIN TOOL OR TO ADD A SOCK FILTER IN DIAPHRAGM OPERATOR WITH THE MSIV OR FWIV CUBICLES DURING MODES 1 THROUGH 4. VALVE POSITIONER DWG. NO. SH. NO. REV. M1-0200 - CP-28 me969100.dgn A M1-0200 B C D E F G FINAL PRINT H
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RESTRAINT SUPPORT STRUCTURE CONTAINMENT BUILDING STRUCTURE PROCESS PIPE RESTRAINT BASE PLATE CONTAINMENT ANCHOR ISOLATION BOLTS VALVE Amendment 73 August 5, 1988 COMANCHE PEAK SES BREAK FINAL SAFETY ANALYSIS REPORT EXCLUSION UNITS 1 AND 2 PROCESS FORGING THREADED PIPE FLANGE (BOL TEO J AR TYPICAL MOMENT RESTRAINT AND BREAK EXCLUSION AREA BOUNDARY TO STRUCTURE) DS15BB067 FIGURE 3.6 5
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COMANCHE PEAK S. E. S. FII\IAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JULY 31, 1980 PIPING STRESS-STRAIN CHARACTERISTICS FIGURE 3
- 6B-7
I I I z~ 0 I 1- I u < I lJ.I a:: I I I DISPLACEMENT RESTRAINT STIFFNESS F EFFECTIVE IMPACT MASS Tl ME SLOWDOWN THRUST-TIME HISTORY COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 JULY 31, 1980 RESTRAINT IMPACT FIGURE 3. 6B-8
~ DENOTES BREAK LOCATION PLAN VIEW STEAM GENERATOR REACTOR PRESSURE VESSEL ELEVATION NOTE: 1. Postulated main reactor coolant loop break locations 1 through 8 and branch nozzle breaks 9 through 11 are considered for containment design, ECCS and enviornmental qualification. These breaks are not postulated for dynamic effects.
(Sections 3.68.2.1.1 and 3.63.2.1.2)
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to the largest RCL postulated breaks after application of LBB to selected lines. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 76 MAY I, 1989 Location of Postulated Breaks in Main Reactor Coolant Loop FIGURE 3. 68-9
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r 1 i~I LEGEND t T AMENDMENT 80 I NOVEMBER 30, 1990 I I COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT I UNIT 1 I SAFETY JNJEC110N sYSTEll I INSIDE CONTAINMENT J. SlRESS NOD£ BREAK POINT AND RESTRAINT LOCA110N FIGURE 3.88-48-2 !'ROB. 1-13A
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LEGEND AMENDMENT 76 MAY 1, 1989 COMANCHE PE FINAL SAFETY ANAK S. E. S. AL YSIS REPORT UNIT 1 SAFETY INJECTION S INSIDE CONTAINM 'I'S1Et.4 S1RESS NODE BREM<a:4T AND R£S"'JWNT LOCATJON POINT FIGURE 3.68-50-1 PROB. t-158
0 AK S E. S. COMANCHE :~ALYsis REPORT Sl-!-026-2501/i'-f FINAL SAFE~NIT 1 AMENDMENT 76 MAY 1, 1989
27 l/2'1.i:L - - - , LOQP 3 CD
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FIGURE 3.68-55 PROB. 1-170 &: 1-
LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSJS REPORT UNIT 1 SAF1::TY INJECiiON S'1STEl.t OUlSIDE CONTAINMENT STRESS NODE BREAK POINT AMENDMENT 76 AND RESlRAINT I.OCA110N MAY 1, 1989 FlGURE 3.68--56 PROB. 1-51A
L.-------f LEGEND 0 C) COMANCHE PEAK S. E. S. FINAL SAFETY ANALYS!S REPORT UNIT 1 SAFETY lNJECllON SYSTEM INSIDE CONTAINMENT Sl'RESS NODE BREAK POINT AMENDMENT 76 AND RESTRAINT LOOAnON MAY 1, 1989 f1GURE 3.68-57-1 PROB. 1-145
LEGEND 0 C) COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 SAFETY INJECllON S'I'$1EI.C INSIDE CONTAINMENT S1RESS NODE BREAK POINT AMENDMENT 76 AND Re>IRAINT lOCA110N MAY 1, 1989 FIGURE 3.11&-57-2 PROS. 1-145
LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANAL YSJS REPORT UNIT 1 AUX. STEAM SYS1EM S1R£SS NODE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCA110N MA'Y 1, 1989 ACURE 3.88-58-1 PROB. 1-1358
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LEGEND !. lH/S li'ES'Tli'AINT IS INACJJn:: COMANCHE PEAK S. E. S. FINAL SAFETY ANAL YS!S REPORT UNIT 1 AUX. STEAM SYSTEM Sl'RESS NODE BREAK POINT AMENDMENT 78 AND RESl'RAINT LOCAilON JANUARY 15, 1990 FIGURE 3.68-58-3 PROB. 1-135F
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FINAL SAFETY ANALYSIS REPORT UNIT 1 AUX. STEAM SYS'TEM S1RESS NODE BRE.AI< POINT AMENDMENT 78 AND RES'JRAINT LOCATJON JANUARY 15, 1990 FIGURE 3.68-59-1 PROB. 1-135A
LEGEND
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FINAL SAFETY ANALYSIS REPORT UNIT 1 AUX. S1EAM SYS1EM AMENDMENT 76 SiRESS NOO£ BREAK POINT AND RES1RAINT LOCA110N MAY 1, 1989 AGURE 3.613-59-2 PROS. 135C
AMENDMENT 76 MAY 1, 1989 LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 AUXIUARY S1EAM S'tSTEM AUX. BUILDING S1RESS NODE BREAK POINT AND RES1RAINT LOCAliON FIGURE 3.68-80 PROB. 1-147C
LEGEND 0 C) COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 AUXIUARY S1tAM SYSTEM AUX. BUilDING AMENDMENT 76 SlRESS NODE BREAK POINT AND RESTRAINT LOCA110N MAY 1, 1989 FIGURE 3.88-61-1 PROB. 1-1-4-70
LEGEND 0 c::> COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 AUXIUARY STEAM SYSTEM AUX. BUILDING STRESS NODE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCA110N MAY 1, 1989 flGURE 3.68-61-2 PROS. 1-147£
LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 AUXIUARY STEAM S'I'SlEM AUX. BUILDING STRESS NODE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCA'nON MAY 1, 1989 FIGURE 3.68-62 PROB. 1-1478
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- OlE
- 1. 7JIIS lif:SmAINT IS !NACO!£ LEGEND AMENOMENTBO ~
NOVEMBER 30, 1990 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 RHR SYSTEM S1RESS NODE BREAK POINT AND RES1'RAINT LOCA110H FICURE 3.69-64-1 PROB. 1-13A
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NOlE
- 1. JHIS li'£S7li'AINT IS INAC77JE.
LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 REACTOR COOLANT SYSTEM INSJD£ CONTAINMENT STRE~ NODE BREAK POINT AMENDMENT 78 AND RESTRAINT LOCATION JANUARY 15, 1990 FIGURE 3..68-65 PROB. 1-25
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LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 REACTOR COOLANT SYSTEM INSIDE CONTAINMENT AMENDMENT 76 S1R£SS NOOE BREAK POINT AND RESlRAlNT LOCAnoN MAY 1, 1989 AGURE 3.6&-66-2
I )> 3 LEGEND CD
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~ AND RESTRAINT LOCATION lBK-Ht::Ft::PH-01 FIGURE 3.68-67-1 PROB. 1-53
0£1)4/L C (L(JQP C) (L(JQP e) LEGEND AMENDMENT 76 MAY 1, 1989 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT NOlES UNIT 1 1 fl1H t.~m:w fF 8f£ofK.) QV REACTOR COOlANT S'tS1EU INSIDE CONTAINMENT DETAIL A L()(JPS-" 4 .. C $II DETAIL E 1'7(;; .l" flll-67-J STRESS NODE BREAK POINT AND RES'IRAINT LOCA110N (L()(JP .-t) FIGURE 3..89-67-2 PROB. 1-53
LOOP A LOOP B LOOP C LEGEND DETAIL £ 0 C) BHEAK LOCA!ltWS R:N LaPS A. 4 i t: HU: .1:61:1-67-.2 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 REACTOR COOLANT S'I'ST'EJd INSIDE CONTAINMENT AMENDMENT 76 SlRESS NODE BREAK POINT AND RESTRAINT LOCAllON MAY 1, 1989 FIGURE 3.68-67-3 PROB. 1-53
LEGEND AMENDMENT 80 NOVEMBER 30, 1990 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 REACTOR COOLANT S'T'STEM INSIDE CONTAINMENT S"IRESS NODE BREAK POlNT AND RESTRAINT LOCATION FlGURE 3.66-68-1 PROB. 1--430
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AMENDMENT 80 NOVEMBER 30, 1990 LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 REACTOR COOLANT SYSTElof INSlOE CONTAINMENT STRESS NOOE BREAK POINT AND RESTRAINT LOCA110N AGURE 3.68-68-2 PROB. 1--430
LEGEND 0 S'IRESS ll<llE POINT c::> ==:w-...Jr!OR LJ 2-J#P-f-D.H-2501H-5 u-BM~
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COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 2-C$-1-fli5-2501H-2 REACTOR COOLANT SYSTEM INSIDE CONTAINUENT AMENDMENT 76 S1JitESS NODE BREAK POINT AND RES'IRAINT LOCA'llON MAY 1, 1989 FlGURE 3.88-69 PROB. 1-# a 1-.otOR
LEGEND
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f tf I COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYS'1'EU INSIDE CONTAINMENT AMENDMENT 76 STRESS NODE BREAK POINT AND RESlRAINT LOCA110N MAY 1, 1989 FIGURE 3.6&-70 PROB. 1-.W
..1-li'C-t-052-.25()!/i'-1 LEGEND S'l!IESS NODE POINT COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 CVCS SYSlEM INSIDE CONTAINMENT S1RESS NODE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCATION MAY 1, 1989 FIGURE 3.68-71 PROB. 1-41
J-.CS-t-lltf()-IIOfH-2 DETAIL An LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYS1£N
-cs-t-ot.2-60fli'-2 INSIDE CONTAINMENT AMENDMENT 76 SlRESS NODE BREAK POINT AND RESTRAINT LOCA110N MAY 1, 1989 FIGURE 3.88-72 PROB, 1-42A
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MODERATE ENERC Y PIPING COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves S'IS'IEM INSIDE CONTAINMENT AMENDMENT 76 STRESS NODE BREAK POINT ANO R£SiRAINT LOCAllON MAY 1, 1989 fiGURE 3.89-73-1 PROB. 1-428
!WOOERATE ENERC Y PIPING COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1
/ eves SYSTEN
./ AMENDMENT 76 INSIDE CONTAINMENT SlRESS NODE BR£AK POINT AND RESlRAJNT LOCA110N MAY 1, 1989 AGURE 3.68-73--2 PROB. 1-428
AMENDMENT 80 NOVEMBER 30, 1990 COMANCHE PEAK FINAL SAFETY AN AL YSlS S. E.REPORT S. UNIT 1 0 STRESS NODE POINT eves S"l'S1'E:W c::>
~DE CONTAINMENT AND ~NBTREAK POINT LOCAllON flGURE 3.118-74 PROB. 1-438/C .t 1-<4-30
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AMENDMENT 76 MAY 1, 1989 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT LEGEND UNIT 1 0 eves SYS1tM INSIDE CONTAINMENT SlRESS NODE BREAK POINT c::> AND RES1RAINT LOCATION FIGURE 3.68-75 PROB. 1-43Y/Z lc 1-438/C
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CONTAINMENT BUILDING OIHFICE A(P S(A~ BYPASS l)fl,ft(E T8X~CSOI!SS.03
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(£) (IRCII"f(I'<£Nt!AL &REA~ 0 STRESS HOD£ 9Qt"T COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 CVCS SYSTEM STRESS--~------1 NODE: BREAK POINT AND AMENDMENT 26 AUGUST 25, 1981 FIGURE
CONTAINMENT BUILDING
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Nang BREAK POINT AND SU-PER AMENDMENT 26 AUGUST 25, 1981 FIGURE
LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves S'YS1EM INSIDE CONTAINMENT AMENDMENT 76 SlRESS NODE BREAK POINT AND RESlRAINT LOCA110N MAY 1, 1989 AGURE 3.68-78 PROS. 1-39
LEGEND 0 $'lll£liS IIOOE POINT
<:::) ~~/OR l.J U-IIAR fiESli!AINT
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FINAL SAFETY ANALYSIS REPORT UNIT 1 CVCS SYSTEM INSIDE CONTAINIIENT smESS NODE BREAK POINT AMENDMENT 76 AND RES'TRAJNT LOCA110N MAY 1, 1989 FlGURE 3.88-79 PROB. 1-450
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FINAL SAFETY ANALYSIS REPORT UNIT ~ CVCS SYSID.t INSIDE CONTAINMENT STRES" ~:vOE BREAK POINT AND RESTRAINT LOCAllON AMENDMENT 78 JANUARY 15, 1990 AGURE 3.68-80 PROS. 1-450
LEGEND S'lR£SS NODE POINT COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 CVCS SYSTEM INSIDE CONTAINMENT Sl"RESS NODE BREAK POINT AMENDMENT 76 AND RES1RA!NT LOCAllON MAY 1, 1989 FIGURE 3.89-61 PROB. 1-45£:
LEGEND BUMPER RES'IIWNT HARD IIES'IRMIT COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 CVCS SYSTEM OUTSIDE CONTAINMENT SlRESS NODE BREAK POINT AND RESlRAINT LOCAllON FIGURE 3.68-82-1 PROB. 1-46A
LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 CVCS SYSl'EM OU1SIOE CONTAINMENT AMENDMENT 76 SiRESS NODE BREAK POINT AND RESiRAJNT LOCATION MAY 1, 1989 FlGURE 3.68-82-2 PROB. 1--468
LEGEND COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves S'fSTEM OUTSIDE CONTAINMENT AMENDMENT 76 S1RESS NODE BREAK POINT AND RESlRAJNT LOCATION MAY 1, 1989 f1GURE 3.68-82-3 PROB. 1-N068
LEGEND 0 c::J COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYS1EM AUX. BUILDING STRESS NODE BREAK POINT AMENDMENT 76 AND RESTRAINT LOCA110N MAY 1, 1989 FlGURE 3.68-83 PROS. 1-51A
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*""'* 'NT LOCAliON FlGURE J..IIB-64 PROB. 1-51B
LEGEND S'lRE'SS NODE POINT COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYSTEM AMENDMENT 76 AUX. BUil.DING STRESS NODE BREAK POINT MAY 1, 1989 AND RESTRAINT LOCAllON FlGURE 3.68-85 PROB. 1-51C
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LEGEND 0 S1RESII NODE PlliiiT COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYS1EM SAFEGUARDS BUILDING AMENDMENT 76 S1RESS NODE BREAK POINT AND RESTRAINT LOCAllON MAY 1, 1989 AGURE 3.68-88-1 PROB. 1-52Y
LEGEND 0 C) COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNIT 1 eves SYST!il.4 SAFEGUARDS BUILDING AMENDMENT 76 STRESS NODE BREAK POINT AND RESTRAINT LOeA1lON MAY 1, 1989 flGURE 3.68-88-2 PROS. 1-52Z
NOTfi.S:
- 1. Break locations 1 to 13 per Table N 3.6B-2.
- 2. Based on GDC-4, leak-before-break (Section 5.4.14) the loop whip Rrii.C'Tt:>flt COOI..I\NT P'UM""
restraints and non-T&ll- RC"'C',..C-01 crushable insulati are not required. Slt"-M
~£N'-"A.TOit Tall- R'CI'nCa 01
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(C~o*e.ovelll!) li!eA..CTOit T&X-IIit.C ...CA!"
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- 2. Based on GDC-4, leak-before-break (Section 5.4.14) the loop whip restraints are not required.
~E,....CTOR - - - " " '
COOLA.'-lT P'U~~ T&lC..- RCP'C PC-Ot Foil! coo..aT. e.aec FIQ. 3.40.8-~* R'C- 2501 ~-1 e,t ];.D ........ E ( c:'1!'0!lo.OVI:") LE:<ioEUD CD* '5EE NOTE COMANCHE PEAK S E S fiiW. SN£TY NIW..YSIS AEf'QU UNITS 1.-.ct 2 AMENDMENT 76 REACTOR COOlANT LOOP I l MAY 1, 1989 STRESS NODE ' BRE~ POINT f~ l.6B-90 (LOOP 12t
~:
- 1. Break locations 1 to 13 per Table 3.6B-2.
- 2. Based on GDC-4, leak-before-break (Section 5.4.14) the loop whip restraints are not required.
N 10-AC-1-0**- ZliOiilt*l FOR CONT !o&.£ Fl** !!>."'&* 54-
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C:.*RC*I*O<IGo.t!)OIR*I Fott c.o""T.
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COMANCHE PEAK S E S FNAl SN£TY ANN.YSIS ~POOl CD
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~
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/ break (Section 5.4.14) the loo whip restraints are not required 14 *IIPC*I*I~I)* f')OI R *I FOR COWT &£f. Fie;.. ~-4o8*6S 13 I
y _........-2'-trC-I*O'?t*Z'501R-I F"OIIl' coo.aT &E. e. J:'l~. ~ "8* .. CD- S&l: NOU 1 COMANCHE PEAK S E S FtW.. SAFETY ANALYSIS REPOOT UNITS 1 and 2 AMENDMENT 76 llf:I\CTOR C(X)LANT L(X)P 14 MAY 1, 1989 STRESS NODE &. BI:EAJ< POINT AND RESTRAINT !QC!TJONS __ flilft l.f>B-'12 ll.OOP 141
CPSES/FSAR Figure 3.66-93-1 This figure has been deleted. Amendment 87 December 18, 1992
CPSES/FSAR Figure 3.68-93-2 This figure has been deleted. Amendment 87 December 18, 1992
CPSES/FSAR Figure 3.68-94 This figure has been deleted. Amendment 87 December 18, 1992
CPSES/FSAR Figure 3.68-95 This figure has been deleted. Amendment 87 December 18, 1992
PLANE AT END OF JET CORE ASYMPTOTIC PLA,NE REGION 3 REG I0 N 2 ----..-f--t~ REGION 1 Da JET CORE BREAK PLANE Lc --11-+--~~_, La ---~-....-.J L Amendment 71 May 27, 1988 COMANCHE PEAK S. S. FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 CIRCUMFERENTIAL PIPE BREAK WITH FULL SEPARATION JET CONE FIGURE 3.68-96A
n z 0 0 w 0:::: PLANE AT END ASYMPTOTIC PLANE OF JET CORE REGION 2 REGION Lc La Amendment 71 May 27, 1988 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 LONGITUDINAL PIPE BREAK JET CONE FIGURE 3.68-968
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FINAL SAFETY ANALYSIS REPORT UNITS 1 & 2 JET CORE REGION GEOMETRY FOR A CIRCUMFERENTIAL PIPE BREAK WITH FULL SEPERATION FIGURE 3.6B-96C
100 - - .. __. - ................. - .. - - .. - ... - - .... - - .. - - - .. I*
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I I l I COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 EFFECT OF IRREVERSIBLE LOSSES OF ASYMPTOTIC AREA RATIO AMENDMENT 76 MAY 1, 1989 FIGURE 3. 68- 96E
CPSES/FSAR Figure 3.6B-97 thru 3.6B-99 (NOT USED)
CPSES/FSAR Figure 3.6B-97 thru 3.6B-99 (NOT USED)
CPSES/FSAR Figure 3.6B-97 thru 3.6B-99 (NOT USED)
AMENDMENT 86 AUGUST 31, 1992 LEGEND 0 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM: LOOP 1 INSIDE CONT A!NMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.66-100 PROB 2-1 Fl G100000.BLI
AMENDMENT 86 AUGUST 31, 1992 LEGEND CJ ClllC~JIFEJI!O}~TJAt. lONGPUlHW... &f!EAA
.I'IMli\'F lr COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM:LOOP 2 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-101 PROB 2-2 F; G1010,)0.Bl
AMENDMENT 86 AUGUST 31, 1992 LEGEND C~J<<;';:NftAI.M(U(lR lOHCITI..()!*L &REAle COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM:LOOP 3 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.66-102 PROB 2-3 Fl GIO?OOO.RI I
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t AMENDMENT 86 AUGUST 31, 1992 LEGE~m (JRCI}!"F[f!ENT!A.. f#<<)l{ll'l lCN::olTtJOIIOrol. BRf..:U.. COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM: LOOP 4 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-103 PR08 2-4
AMENDMENT 86 AUGUST 31, 1992 LEGEND COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM: LOOP OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATIONS FIGURE 3.68-104 PROB 2-100
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,, ----'""' LEGEND COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM: LOOP 2 OUTSIDE CONTAINMENT STRESS NODE BREAK POINT ANO RESTRAINT LOCATION Fl GURE 3.GB-105 PROB 2-100
AMENDMENT 86 AUGUST 31, 1992 LEGEND 0 STRESS NODE POINT CtAC!JMFERENT [Al ANOIOO LONGITUOtNAL BREAK lJ U-SAR RESTRAINT BUMPER RESTRAINT SPEClAL 6UMPER RESTRAINT COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM:LOOP 3 OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-106 PROB 2-lOO
AMENDMENT 86 AUGUST 31, 1992 LEGEND 0 STRESS NOO[ POlNT CiRCUMFERENTIAL ANO!OR LONGITUDINAl BREAK U-BAR RESTRAINT BUMPER RESTAAtNT SPECIAL BUMPER RESTRAINT COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM:LOOP 4 OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCA T!ON Fl GURE 3.68-107 PROB 2-100
AMENDMENT 86 AUGUST 31, 1992 LEGEND t.llltt.tfi'Rii:ffi!AL IIINIJf"" L~ITvtllJIIAL!)fl(AIC COMANCHE PEAK S E S Fl NAL SAFETY ANAL Y$1 S REPORT UNIT 2 FEEDWATER SYSTEM:LOOP INS!OE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-108 PROB 2-5 !G1 VlRVlVli/LRI l
NOTES
- 1. THE FOLLOWlNG LlST OF SHOCK SUPPRESSORS AND BEEN ACTIVATED AS RlGtU Kt:S fRAlNTS SHOCK SUPPRESSORS FW-2-018-448-C52K AMENDMENT 86 AUGUST 31, 1992 LEGEND ClRCIJMFf.Rfkf!A;. AW(Vl;IA U:J<<;HUOIJ<Ai.SREIIK COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEDWATER SYSTEM:LOOP 2 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-109 PROB 2-G
NOTE SUPPRESSORS AND RIGID RES>RAINTS WHIP RESTRAINTS. RE<'£fi6-j(:E SIJPPI'<ESSOR AND RIGID RESTRAINT LOCATIONS AMENDMENT 86 AUGUST 31, 1992 L.EGEND CJRCI.M'EI'e<Tl<\l AHDICP LONGt!Wl!UIL ~'~REM COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEOWATER SYSTEM:LOOP 3 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.69-110 PROS 2-7 FIG110000.Bc.i
AMENDMENT 86 AUGUST 31, 1992 LEGEND CIRCU4"RENl!iiL ANil/00 lONGtnnii'W. 6fi'(AA COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEDWATER SYSTEM:LOOP 4 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCA T!ON FIGURE 3.68-111 PROB 2-8
FW~2-tH6~'i04-S57W F"W~2-016-"l03A- S57W FW-2*015-904-S57'1o' Fw- 2-015-90JA~ss7-w AMENDMENT 86 AUGUST 31, 1992 LEGEND COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEDWATER SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.66-112 PROB 2-104 & 2-'lA. 'lC
Fw~2~014~q04~557W FW- 2-tll 4 -'i03A-S57W FW-Z-013-"!04-557W FW* 2*k)l3-~0 JA*S57W AMENDMENT 86 AUGUST 31, 1992 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEOWATER SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCA T!ON Fl GURE 3.68-113 PROB 2-104 & 2-98. 9D
HEAH R £'"lA CP.?*f-WHlf-l-'-01 i > ( J j COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2
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FEEOWATER SYSTEM OUTSIDE CONTAINMENT AMENDMENT 87 STRESS NODE BREAK POINT DECEMBER 18, 1992 AND RESTRAINT LOCATION Fl GURE 3.68-114 PROB 2-104
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FIGURE 3.68-115 PROB 2-104 1.1.1
AMENDMENT 86 AUGUST 31, 1992 LEGEND Ctll(U<F(JlENt:AI..I'KJ/011 LO~NAl.BAEAI( COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEOWATER SYSTEM: F.W. BY-PASS OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-116 PROB 2-104 FIG116000.fLi
AMENDMENT 86 AUGUST 31, 1992 LEGEND Cli'!Ci..H'UIEN*W..~t~ L'JHGlfUJlNAL BRB¥ COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEDWATER SYSTEM:F.W.BY-PASS OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-117 PROB 2-104 FI G117000.BI_I
t067C-C AMENDMENT 86 AUGUST 31, 1992 LEGEND CI~ERElHIAI.. AMJ<OO U'KilRIO~ tii!EH: COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 FEEOWATER SYSTEM:F.W.BY-PASS OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-118 PROB 2-104 Fl G118000.8:_!
AMENDMENT 86 AUGUST 31, 1992 LEGEND ctRC(J~NfiALAND/O'l L<:J<GJTWIN<oLBRfAX COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM: M.S. BLOWOOWN OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCTION FIGURE 3.68-119 PROB 2-96A F I(; lFiOOO.RI I
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j: I I COMANCHE PEAK S E FINAL SAFETY ANAL YSI REPORT UNIT 2 MAIN STEAt-1 SYSTEM: M.S. BLOWOOWN OUTSIDE CONTAINMENT STRESS NODE BREAK POHH AMENDMENT 87 AND RESTRAINT LOCATION DECEMBER 18, 1992 ~-*-~--~~~~ FIGURE 3.68-120 PROB 2-966 1 rr,:
AMENDMENT 86 AUGUST 31, 1992 LEGEND COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM: M.S. SLOWDOWN OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCA HON Fl GURE 3.68-121 PROB 2-96C FIG'210CJO.BL I
AMENDMENT 86 AUGUST 31, 1992 LEGEND COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 MAIN STEAM SYSTEM: M.S. BLOWDOWN OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-122 PROB 2-960 Fl GI??OOO.Bl
CPSES/FSAR Figure 3.6B-123 {NOT USED)
- VALVE INTERNALS ARE REMOVED COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT 2 AUXILIARY F.W. SYSTEM: LOOP I OUTSIDE CONTAINMENT STRESS NODE BREAK POINT FIGURE 3.68-124 PROB 2-IOC ve0002fr.dgn
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FINAL SAFETY ANALYSIS REPORT
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COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT 2 AUXILIARY F.W. SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-126 PROB 2-12E ve0002fp.dgn
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X AMENDMENT 86 AUGUST 31, 1992 LEGEND t!RC.\IMFEAEWTIAL AI<OIOR Lt:N:.I!lll.\i'ol9REAI: COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 AUXILIARY F.W. SYSTEM: LOOP 4 OUTSIDE CONTAINMENT I STRESS NODE BREAK POINT
-'- AND RESTRSAINT LOCATION FIGURE 3.66-127 PROB 2-IOB Fl G127000.BLI
AMENDMENT 86 AUGUST 31, 1992 C!~ri:RNTI"'L~/QI< l(li<¥:;!TIJON.91!5:1}K COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 AUXILIARY F .W. SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RES TRA!NT LOCA liON FIGURE 3.68-128 PROB 2-12A Fi 128000.RI I
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COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT 2 AUXILIARY F.W. SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-129 PROB 2-128 SHT I OF 2 ve0002fq.dgn
AMENDMENT 86 AUGUST 31, 1992 LEGD;D COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 AUXILIARY F.W. SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-130 PROB 2-128 SHT 2 OF 2 CiGi:)OOOO.Rl I
CPSES/FSAR Figure 3.6B-131 (NOT USED)
AMENDMENT 86 AUGUST 31, 1992 LEGEND (.(~CUHFRENT!AI.. I\WOJOR l~ll*JDI~SJICAI< COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEOWATER SYSTEM:LOOP INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-132 PROB 2-152 Fl Gn?OOCLRI I
AMENDMENT 86 AUGUST 31, 1992 LEGEND COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEOWATER SYSTEM:LOOP 2 INSIDE CONTAINMENT STRESS NODE BREAk POINT AND RESTRAINT LOCATION FIGURE 3.68-133 PROB 2-153 Fl!~l'J'\()0(J.RI I
2-Fw-2-'f04-1303e2 AMENDMENT 86 AUGUST 31, 1992 LEGEND tl'ltl!>W(R!;:NHAL AH01M LI)!<GITUOt"ALBI<£111: COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 FEEDWATER SYSTEM:LOOP 3 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION Fl GURE 3.68-134 PROB 2-154 F Gl3s000.BLI
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AMENDMENT 86 AUGUST 31, 1992 ctRCtJ>o!f(RI:<.lt:A!. 4>1P>Qi'! L():.IGHIJDlNALet<'EAit lJ COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 FEEOWATER SYSTEM:LOOP 4 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION Fl GURE 3.6B-l35 PROB 2-155
AMENDMENT 86 AUGUST 31, 1992 LEGEND 0 CIPC~RENTtAt. ~/t;R t(N{;ITlOIW.J.. SREQ~; COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 STM.GEN.BLOWDOWN SYS.LOOP 1 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.66-136 PROB 2-75 FIGI35()00.Bi i
AMENDMENT 86 AUGUST 31, 1992 tJRi: .....(R(hfi"L MIUJOR U:NG:TtJO:>.ktL f>I'IEM COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 STM.GEN.BLOWOOWN SYS.LOOP 2 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-137 PROS 2-76A
AMENDMENT 86 AUGUST 31, 1992 LEuENO Cl"CU'4~E~!ll>c_""':lt~ U)fl(;ITIJOlKAL f!R!;AI( COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 STM GEN BLOWOOWN SYS LOOP 2 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-138 PROB 2-0766 F! GURCOl).R:
I I I AMENDMENT 86 AUGUST 31, 1992 LEGE~m 0 S'RESS NODE POiNT ClRCUMFERtWIAL AN<)/OR LONG I T<JOINAL BREAK COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 STM.GEN.BLOWOOWN SYSTEM LOOP 3 INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-139 PROB 2-077 FIGI:'iCJOOD.RI I
AMENDMENT 86 AUGUST 31, 1992 CtRCIJMFERt:>>TI>>t.. AMJ/00 l().IGPLJO~BRE<IK COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 STM.GEN.BLOWOOWN SYSTEM LOOP 4 INSIDE CONTAINMENT STRESS NODE BREAK POINT ANO RESTRAINT LOCATION FIGURE 3.68-140 PROB 2-078 Fl
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J: 3-MS-2*07 3*!303*2 3-MS 075-!303-2 3-MS-2-076-1303-2 NOTE: BREAKS ARE CONSERVATIVELY POSTULATED AT EVERY FITTING FOR PROBLEM 2-7'lH. IF NECESSARY. SEISMIC ANAL YS!S RESULTS CAN BE USED TO ELIMINATE INTERMEDIATE BREAKS. COMANCHE PEAK S E S LEGEND Fl NAL SAFETY ANALYSIS REPORT UNIT 2 (!R(li"-FERENT!AL M(]lcw;' LO~!TU)lNAL BR£Ak STEAM GENERATOR SLOWDOWN SYSTEM BUMPER RESTRAINT Amendment 88 OUTSIDE CONTAINMENT April 16, 1993 STRESS NODE BREAK POINT AND RESTRAINT LOCATION Fl GURE 3.68-141 PROB 2-79E AND 2-79H
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BREAKS ARE CONSERVATIVELY POSTULATED AT COMANCHE PEAK S E S EVERY FITTING FOR PROBLEM 2-7%. IF NECESSARY.SEISMIC ANALYSIS RESULTS CAN Fl NAL SAFETY ANALYSIS REPORT BE USED TO ELIMINATE INTERMEDIATE BREAKS. UNIT 2 STEAM GEN.BLOWOOWN SYSTEM Amendment 88 OUTSIDE CONTAINMENT April 16, 1993 STRESS NODE BREAK POINT AND RESTRAINT LOCATION Fl GURE 3.68-142 PROB 79F AND 2-79G
AMENDMENT 86 AUGUST 31, 1992 LEGEND CWCLMFE'lOIT!i>L Mf)ll)!'l
\t'fiGlfl.J)IN!\1. kfl[AK COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 STEAM GEN.BLOWDOWN SYSTEM AUX. BUILDING STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-143 PROB 2-148 SH 1 OF 2 F! (, 14 \:lOC.bl I
AMENDMENT 86 AUGUST 31, 1992 (!R(~FEIJE>H!"l,ot./01()'1: Ll>>:JITUCtHAt.l\R£4¥ COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 STEAM GEN.BLOWOOWN SYSTEM AUX. BUILDING STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-144 PROB 2-148 SH 2 OF 2 FIG144000.f~l I
CPSES/FSAR Figure 3.6B-145 (NOT USED)
CPSES/FSAR Figure 3.6B-146 (NOT USED)
p I AMENDMENT 86 AUGUST 31, 1992 LEGEND tlRCl>!'WE>>t:OH(AL "NC,z(JP lONGJrlJO!NAL BPrru:. COMANCHE PEAK S E S Fl~jAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INS!DE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-147 PROB 2-138
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AMENDMENT 86 AUGUST 31, 1992 LEGEND t!I!C\J~E!'VIT!AI.. AI<IO;(W LCNCHUDI>.i
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AMENDMENT 86 AUGUST 31, 1992 LEGEND ClRCtH'fltt<ITIAt Mll/00 LO<<>ITIJ)It4o\L SRENtt COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY !NJECT!ON SYSTEM INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-149 PROB 2-14
AMENDMENT 86 AUGUST 31, 1992 LEGEND Gfl(;lli'II'E~~t;AL "'"0/01<
U:..G!"t.IOlMALMEAX COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-150 PROB 2-158 FIG150~J7:VLRI 1
AMENDMENT 86 AUGUST 31, 1992 LEGniD tlf!C.l.IWEF!ENT!~~OR LO'ItlfU:llNAI.. SREAK COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-151 PROB 2-15Y Fl G1'1 I~JOO,BL I
AMENDMENT 86 AUGUST 31, 1992 LEGEND CfAC!HlJ't(l4fiAL l>oi'<);()A LON&IIliJI"'Gl 5f!EO:.O:
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-152 PR08 2-158
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COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NODE 3REAK POINT AND RESTRAINT LOCATION FIGURE 3.68-153 PROB 2-15Z
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COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.6B-154 PROB. 2-16A F ICil ')4VJliJCJ.RI I
AMENDMENT 86 AUGUST 31, 1992 COMANCHE PEAK S E S SAFETY ANALYSIS REPORT UNIT 2
AMENDMENT 86 AUGUST 31, 1992 LEGEND CIAC!.JHFtliENTIAL"'N0/00 lONGJYOO:HAt.. SREAA COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT A
UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NOOE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-156 PROS. 2-168 C155000JlL:
C1PC\>!Yf.fl£11HAI. 1\W/OR t.OWC!fU:ltNillt_ Ml:Ak lJ AMENDMENT 86 AUGUST 31, 1992 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68*157 PROB. 2*17C
LEGEND AMEti>MENT 86 AUGUST 31, 1992 COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM INSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION FIGURE 3.68-158 PROB. 2-170
AMENDMENT 86 AUGUST 31, 1992 LEGEND C!R(1.1o'f'(R(NTII\t "'NIJ/OR Lf.NJt1JOI*'L6!1EAr COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 2 SAFETY INJECTION SYSTEM OUTSIDE CONTAINMENT STRESS NODE BREAK POINT AND RESTRAINT LOCATION Fl GURE 3.68-159 PROB. 2-51A FIG1"i9000.RI
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- r:::::::::::::::r::::::::::::::r::::::::::::::r:::::::::::::r::::::::::::r:::::::.. ***;::*.:::::::::::r:::::::::::::r:::::::::::::
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- I................:I................:1................:l................;I.............................. C!
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- :::::t:::::::::::l:=::::::t ::::::::::j: =::::::j::::=~:* :::::::1:: ::::~.:::::::::f::: -*** .
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- z I ,Q I .0 0 .*
- =::f:::::::=f::::=j::=_==f=:=.:::t::::::::1::::::$:::::t::::: ~E::.::
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- =t*-::::l:=:=t=*=t=:_ _:t.:==+/-::.=~~-::*-=:*l::=***::t:::* -
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- l 0
- : : : :!: : : : d: : :=: : l:=: b: : : : :1: : :J_: : :d: : :~: : l: : =: : . !. --*-**-* ~
- =:::j= ::::1: :::::-.::::j:=~.:::::~:::::::J:=:::f:=:=::::f.::::=:::j:: :::::: :1=: -* .
- ~:~:1: : =~1: :~-~t~-~ ~= ~ :~1: : : ~ : .~-;: :~ -~ : : :
- : : : =:=:l: : : = : l: : :=l=-;:=d:=:=~:.: l: : : : : : L: : : d: : : : : =J: : : : : :; :.
- e.n o.CJ o.ot t.ot f.l FREQUENCY IN CYCLES/SECOND COMANCHE PEAK S.E.S.
- ICI X
- .-.0
- i .
- O:, _~-~-*.* ** o*o~* * * * * * * * *
- T* * *u*u*
- o .....
- ~
- i 6w i i
- r:
- 9 11 COMANCHE PEAK S. E.S.
- EL so~** 1'0..
- ~-~
- z Q
- <; hJ!:--1 z m n
- , ....,t1<!H I
- 0 (/) / .
- 0
- y I.
- e. CENTROID OF BASE A
- 1'
- 1. 000 r f co 50.0
- AT
- z~
- Z' 0
- r
- 1. 000 COMANCHE PEAK S.E.S.
- 1. 000 10.00 FREQUENCI (HZl COMANCHE PEAK S.E.S.
- 1' 0
- 1' L) 0 0 zC::
- 1. 000 10.00 FREQUENCI (HZl COMANCHE PEAK FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 AUXILIARY BLDG.
- 1. 000 50.0 lD 0
- t' ::::t' a
- 1. 000 f y 7?
- 1' C) 0 0 0
- 1. 000 50.0 CX) 1.0 0 HAX. RT DIRECT.
- 4. 251.1 0 b ~ 2.851 14.93 At: 'VEitT. A:l.: H-S
- r 0
- r 0
- 1. 000 10.00 FREQUENCY CHZl COMANCHE PEAK S.E.S.
- 1' 0
- Wru 0
- 1. 555 9.480 8.330 AX; E-W
- 3' I
- TS
- 1\~,m 2 1\rviENDMENT 78
- 7B- Sl
- 1 L
- z ci I
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- )
- )
- )
- )
- EL. eo3'-o" AUXILIARY BUILDING FUEL BUILDING SECT I ON 8-B COMANCHE PEAK S.E.S 10 :s o 10 20 30 40 :so &o 10 eo 90 100 110 120 130 140 150 FINAL SAFETY ANALYSIS REPORT U;,l I I I I I I I I I I I I I I I UNITS 1 and 2 SCALE IN FEET STRUCTURAL PLANT ARRANGEMENT FIGURE 3
- 8-3
- 8 - 4
- N~ ,... J.\ 1 **
- TRANSFER t CANAL Ll NER EX PANS! ON JOINT t ....
- .*0 * ~
- c E F H
- lltGRADlAL @ 51'2."+/- UP TO EL.65G'-O" A~D (SEE FtGURE 3.8-11 SHEAR BARS ~ 11' +/- AOOVE EL.85<0 1-0 11 1
- CONTINUATION OF VERTICAL WALL BARS
- SPR!Iv't; LINF EL./000~*6
- CON5TR. ,JT.
- >I
- r--- !1----.
- r 0
- z !
- 8-lS
- o. 2.525 -5.- f I f4 R..EV. 7.
- :I L --Y,:------+
- R.C. PUMP TIE ROD SUP'T S.G. LOWER LATERIAL SUP'T f"l<~l!RE: 3. 8 18
- 3 831 1950 1
- 3. VALVES 1BS-0202 AND 1BS-0203, ON EMERGENCY (3) (3) AIRLOCK CP1-MEMEPE-01, ARE INTERLOCKED WITH THE 1-PI- 1BS-0010 1BS-0038 DOOR OPERATING MECHANISM, AND SERVE TO EQUALIZE ALO20 1BS- DIFFERENTIAL PRESSURE ACROSS LOCKED DOORS.
- 5. FOR GENERAL SYMBOLS AND NOTES SEE DRAWING M1-0200.
- 1. VALVES 2BS-0016 , 2BS-0017 , 2BS-0029 , 2BS-0039 , 2BS-0040 ,
- 2. SHOWN WITH BOTH DOORS CLOSED AND LOCKED. BOTH TC LOCK PRESSURE EQUALIZING VALVES CLOSED AND WITHOUT 2BS-0031 -2505-5 ELECTRICAL POWER TO HYDRAULIC SYSTEM.
- TD VALVES 2BS-0198/0199/0200/0201 SHALL BE 2-PI- (1) (1)
- 7. NUCLEAR SAFETY-RELATED.
- 1. CB&I DRAWING 74-2428-0119 REV 3 PERSONNEL LOCK E-86 E-85 HYDRAULIC SCHEMATIC.
- 2. DCA 94072 REV 7.
- TD
- TD
- TD
- F S AR F IGURE 3 . 8 - 2 2 2BS-0201 2BS-0200 IRC ORC 2BS-0198 2BS-0199 4 2BS-0056 NO NO TYPICAL EPA DETAIL 4 LC (7) NO NO 2BS-0215 2BS-0214 2BS-0213 2BS-0212 2-PI-AL012 2BS-0015 R 2-PI- 2-PS- LC (7)
- 1. SHOWN WITH BOTH DOORS CLOSED AND LOCKED. BOTH LOCK PRESSURE EQUALIZING VALVES CLOSED.
- 2. VALVES 2BS-0202 AND 2BS-0203 ARE INTERLOCKED WITH THE DOOR OPERATING MECHANISM AND SERVE TO EQUALIZE DIFFERENTIAL PRESSURE ACROSS LOCKED DOORS.
- 3. VALVES 2BS-0063, 2BS-0202/203/204/205/206/207 ARE ASME VALVES, THE BALANCE ARE NON-ASME.
- 4. INSTRUMENTS PURCHASED COMMERCIAL GRADE AND HAVE BEEN DEDICATED TO MEET THE DESIGN CRITERIA TO BE SAFETY-RELATED.
- 5. NUCLEAR SAFETY-RELATED.
- f. ~ 'I ---~~-~---~-~------1 UNIT 2 REINFORCED (MA50NRY) sEcT B -B (FIGURE 3.8-24}
- E w
- .::E w
- =I J
- z:
- X:
- X:
- EUTIIOII SHIELD rUEl IADIAL SU"RT l(f COMANCHE PEAK S. E.S.
- e I
- 5000*!//f/ Jv- ----- ! 15U.~
- u. I """ 1--- "---+---r--.1
- 25ft.
- i / v
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- 5 6 7 LEGEND 1 ...
- z:
- t 400
- PRESSURIZER TO Lo 2- Lo TO LG COMANCHE PEAK S.E.S.
- J
- E
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- II 591 I@** l*!l
- 6) u
- I
- b. -SUPPORTS COMANCHE PEAK S. E.S.
- 1. MEMBERS 1 & 6-6" SCH 160 PIPE
- 2. MEMBERS 2 & 3-8" SCH 160 PIPE
- 3. MEMBERS 4 & 5-TS 1 0" X 1 0" X 1/2" x-+1 ~ ~
- 4. MEMBER 71S A FICTITIOUS MEMBER FROM THE CENTERLINE WELD AT JOINT 5s TO THE OUTER SURFACE OF THE SUPPORTED PIPE
- 5. LEGEND:
- 6. 3" ~ ~ ~~
- ,) 7 -8
- ,)
- r:: :::,)
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- ,) (/')
- z:
- z: 800 0
- 9 14 23 23 4 4 4 944 BP Rods 15 12.5 w/o B 0 2 3 NUMBER INDICATES NUMBER OF BURNABLE POISON RODS
- r- - - - r- -
- i:
- '.0 p = o.::
- 0 3::
- z 0.5 0.0 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM COMANCHE PEAK S.E.S.
- o. 77~ I. 255 0.800 '* 2~9
- 3. ~' -0.5.
- 1. 170 I. 256
- so )>0 Tl ro G'i c::0 o..a
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- REACTOR 5 0 e REACTOR 3 FQ 0
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- BOL.EOL FIGUAE 4.3-34 Amendment 96 August 2, 1999
- BOL, EOL FIGURE 4.3-3S
- r. ,
- r. ,
- E
- 30 0:::
- <}_
- All Rods But One (Typical:
- l 0"'
- l - 2 ' _jfl' .....................
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- r: 590 589.2
- 8 560
- r: 590 589.2 ffi~ T HOT
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- 8
- SEE IEF G ON IRUIIG 1111-0200.
- t. catN:CTUlll LOCATED 1N ID110U HALF OF REACTOI COIi.MT PIPIIG ON e*ANCLETOVERTICAL, L
- 21. THE STRAP ON RTD'S IDENTIFIED ON THE FCILLOIIIG HILE ARE USEO 10 IIINTilR1HERIIIM.CYCLIIGAtGSTRA11FICA110NIM11£1RRESPECTIYE PIPIIGLEGS. ASMOTEOON THE TAII.E 0 THE RTD'SARE YDl.lflEDONEITHER THE 1(11 OR THE BOTTOM CF THEPIPE.
- o. VALVES AtG UIIE IUIERS lllYE EDI AIIEO.
- 6 "'" LUMINANT CPNPP 6 t GLEN ROSE, TEXAS
- 7. 600 LB ANSI FLANGES.
- 19. LOCATE ABOVE THE PRESSURIZER RELIEF TANK. PIPING MUST BE SLOPED 1-8708A -151R-5 CONTINUOUSLY DOWNWARD FROM THE REGULATOR TO THE PRT TO AVOID RHR SUCTION WATER SEALS.
- 23. 0.83 INCH I.D. FLOW RESTRICTORS IN PRESSURIZER STEAM SPACE LEVEL INSTRUMENT NOZZLES PROVIDE THE CLASS-1 TO CLASS-2 TRANSITION.
- 24. BY INSTRUMENTATION.
- S S RHR SUCTION 1-TE-3618A-1 1-TE-3618A-6 1-TE-3618A-11 1-TE-3650E-1 3-RC-1-146-2501R-1 3-RH-1-006-601R-2 (TRAIN B)
- T 1-TE-3618A-4 1-TE-3618A-9 1-TE-3618A-14 2 5 TO ATM 5 1 1-TE-3618A-5 1-TE-3618A-10 NOTE 11 SEE NOTE 11 CP1-RCSTDR-01
- 30. THE FOLLOWING LANYARD POTENTIOMETERS (REF DCN 00238) ARE FC 6-RC-1-108-2501R-1 NOTE 2 6-RC-1-147-2501R-1 1-RC-1-941-151R-5 DRAIN SYSTEM ABANDONED IN PLACE:
- 21. LOCATE N-16 MONITOR AS CLOSE AS POSSIBLE TO BIOLOGICAL SHIELD.
- a. VALVE AND LINE NUMBERS HAVE BEEN ADDED.
- r. _
- z::
- E 0::::
- z::
- z:::
- E 0::: 180°
- z:::
- )
- ii
- w *
- u. u.
- c 300
- z:
- 1. THIS DIAGRAM IS A SIMPLIFICATION OF THE SYSTE~ INTENDED TO FACILITATE THE UNDER- FINAL SAFETY ANALYSIS REPORT STANDING OF THE PROCESS. FOR DETAILS OF UNITS 1 and 2 THE PIPING, VALVES, INSTRUMENTATION, ETC.
- _:)
- s 10 1::) 20 2::) 30 40 TIME AFTER REACTOR SHUTDOWN (l-OURS) 212 F AT T=7 :S HOURS 200 F AT T=l3 0 HOURS COMANCHE PEAK S. E.S.
- )
- LOWER LATERAL SUPPORT PIPE COLUMNS
- ONLY 2 SNUBBERS REQUIRED.
- 4- 14
- tol I
*--- ---------------*~---------
FIGURE 3. 8-14
L II ' I I ; MISSLE SHIELD UNIT20NLY E PEAK S.E.S. FIN;~~:~~~ ANALYSIS REPORT UNITS 1 and 2 6C:At..f ,.ff.T CONTAINMENT INTERNAL STRUCTUR~-----*--
-RGURE 3
*~ ----- --- ... -*-*~ -~-----
-~--*--
~
I I I
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AMENDMENT 8 NOVEMBER 30, 1979 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 SERVICE WATER INTAKE (I, ..... ~- STRUCTURE
FIGURE 3. 8-16
,________________ ,___~-- 0 ... __ ~
;.+--:....
;\ :.:_~~~~r~~~J***:. ~-:.,.
*6
. e REACTOR * (> * *
.. (;,
I I r*t.N I . I I . *- I
/
J .P . I I
/r-----1 l I .
~
~ VENTE REACTOR
_, >(......REACTOR SUPPORTS ---~ SU PORT SEE FIG. 5. 4 -10 PLAN-~REACTOR SUPPORTS Jl l
'-...R.C PUMP AN 0 STEAM GEN:t:-RA TOR PtPf COldM NS
.:.EE =-!GURES 5_4-11 t. 5.4-12 IJ...._...;._.;..._.......,._ _ --+_* AN crl OR
..-'r l30LTS l
'j I t I I
'i I ...
t L . ._:.~ ._,._**~*~----+---- i --------~-
SECTION 2-2 COMANCHE PEAK S. E.S_ FINAL SAFETY ANALYSIS REPORT SECTION 1-1 UNITS 1 and 2 a REACTOR SUPPORTS R.C.PUMP & S.G. VERT.SUP'T RC PUMP STEAM GEN. - VERTICAL SUPPORTS - ---~-~-----*----- ......._ ......______________ -----..- - - - - - - - - - *~""'" Fi(]URF 3.8-17 ___ .. _ _ __L__;,.;,;.;,;..;.;.;~..;....;-----...
Tl E ROD ANCHOR_/ BOLTS REBARS
-~PLAN PLAN TYPICAL R.C.PUMP TIE ROD SUPPORT STEAM GEN- LOWER LATERAL SUPPORT
( S E E FIG. 5 .4-12 ) ( S E E F I G. 5, 4 -II ) COMANCHE PEAK S E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2
._~~--**-~--~-*
CPSES/FSAR 931 FIGURE 3.8*19a HAS BEEN DELETED Amendment 93 February 1, 1995
---------------** ~---*-*--,
H H, ~<'t:~lltt:..L Pt:<t.c_;S LJ~,r:
- I,!OYH E.NC!S TO HYORALJC..iC.
POwER uN:T H 0 .kTfA(~ ~;. AN
~ r_o~:Nt.:.T ':JN :... _... AL: Ht 'S!VE (Ty &::
J:-OR M'(U ;:.-owe...- ecrrH E~>.~DS) PA.C.K I
"I \ I!
ol \ 1 ELEv. I
, a;:wo ToP FLooR
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1 THE LOCK~ ELEV OUT'S LOCK IN<;:; MECHANI9-1S ARE OESIGNED TO SEAL A<?AJ~ST SOP'SIG IN THE C<W"TAIN'>AENT 133< LOCI( l VESSEL OR l'i THE LOCK _AND COf'lTA1~"-1EN; SIMUL T ANEOlJSL Y I A$Mt (.ODE OVER Lt,,t_.Q TEr,., r P~E:'S5UP.E 51 5 PS ;r..;) 15 0 ;::-LANGE FACE ND£ DESKNATION VT V!5UAL E.XAMINAliOI\1 PT ovft PENETRANT TEST UT UL TRASON!C TESI RT RADIOCRAPHIC TEST MT "-1AC--NETIC PART1CLE T(:ST COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENOt~ENT 5 GENERAL ARRANGEMENT ~
~ ..1\RCH 30, 1979 PERSONNEL AIR LOCK J i---- --FIG_U_R_E_3-.-8---2-0------- -----li~
GAS~Ei f8 PRESSURE TE5T HOLE TO BE LOCATED AFTER AS5EMBL'1 OF ~SKET LOCK STRUCTUAL. A5~EMBL'( NOTE: GA5KE.T CONF14URAiiON PAT
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 5 PERSONNEL AIR LOCK MARCH 30. 1979 GASKET TESTING ARRG'T. SEC. FIGURE 3.8-21
CPE A B C D E F G H REV DWN CHKDAPVD REMARKS JRMC DJL THIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE IRC ORC CP-12 03-10 03-10 FDA-2012-000230-02-00 PER SK-0001-12-000230-02-00. 2014 2014 LINER 1BS-0047,1BS-0048,1BS-0049, 1BS-0050,1BS-0051,1BS-0052, 1BS-0054 AND 1BS-0055 1 1BS-0030 1BS-0025 E-82 1 (1) (1) ROTARY TC TC ROTARY NOTES: ACTUATOR E-85 E-83
-2505-5 ACTUATOR
-151-5 1. VALVES 1BS-0016 AND 1BS-0017 ARE LOCKED CLOSED IN (INTERIOR 1BS-0031 1-PI- 1BS-0026 (EXTERIOR MODES 1-4 EXCEPT DURING INGRESS AND EGRESS AS ALO21 E-84 5 DOOR) E-86 1BS-0061 2 1BS-0062 DOOR)
ALLOWED BY TECH SPECS. LC LC 2. THE FOLLOWING VALVES ASSOCIATED WITH PERSONNEL
-2505-2 AIRLOCK CP1-MEMEPA-01 ARE ASME VALVES:
2 (2) 1BS-(2) 0028 1BS-0004,1BS-0005,1BS-0006, 1BS-0014,1BS-0016,1BS-0017,1BS-0018,1BS-0025,
-151-2 TC 1BS-0007,1BS-0008,1BS-0009, 1BS-0030,1BS-0036,1BS-0037,1BS-0038,1BS-0039 (8)
" 1BS-0011 AND 1BS-0012 1BS-0040,1BS-0043,1BS-0198,1BS-0199,1BS-0200 1BS-0053 (8) 1BS-0201 AND 1BS-0061. THE BALANCE ARE NON-ASME.
1" 1"
0033 1BS-0032 1BS-0027 " DOOR TEST (2) 4. VALVES 1BS-0063, AND 1BS-0202 THRU 1BS-0207 ON TUBING EMERGENCY AIRLOCK CP1-MEMEPE-01, ARE ASME VALVES. 1BS-0037
1BS-0013 (2) 6. INSTRUMENTS PURCHASED COMMERCIAL GRADE AND HAVE BEEN 25 25 DEDICATED TO MEET THE DESIGN CRITERIA TO BE 1BS-0034 (4) (4) SAFETY-RELATED. 1BS-0044 1BS-LC 1BS- 7. NUCLEAR SAFETY-RELATED. (7) 1BS-0060 0065 1BS-NOTE 6 0059 0064 2 1-PI- R 2
REFERENCES:
AL014 1BS-0201 1. DM 90-343 R LC (6) 2. C B & I DRAWING 74-2427-0119 REV 5 1-PS- 1BS-0200 1-PI-PERSONNEL LOCK HYDRAULIC SCHEMATIC 1BS-0041 LC NOTE 6 ALO24 LC (6) AL013 3. C B & I DRAWING 74-2427-0200 REV CP-1 NOTE 6 (5) GENERAL ARRANGEMENT 3, 2-6" DIAMETER LC R LC (2) (5) ESCAPE LOCK 25 1BS-0042 (2) 1BS-0029 4. C B & I DRAWING 74-2427-138 1BS- 1BS- 0043 1BS- 1BS-0036 1BS-0035 1BS-0039 1BS-0040 (7) 5. C B & I DRAWING 74-2427-261 0067 0066 1BS-0019 1BS-1BS-0057 LINER 1BS- 1BS-0017 2 0016 1BS-0018 LC 0014 5 LC LC 1BS- NOTE 1 NOTE 1 0058 IRC ORC LOCKED 1BS-0056 LC (7) 3 1BS-0069 3 LC 1-PI-NOTE 7 1BS-0068 1-P1- LC AL012 1-PS-1BS- 1BS-0015 1BS-0021 AL011 ALO23 0198 1BS-0199 2 (7) R LC LC 5 NOTE 6 NOTE 6 R LOCKING RING (6) (6) CP1-BSAPPA-01 LOCKED CYLINDERS HYDRAULIC (INTERIOR DOOR) PUMP 1BS-0001 (6 GPM) CONTAINMENT PERSONNEL 1BS-0002 1BS-0003 AIRLOCK 1-PI-ALO22 CP1-MEMEPA-01 CP1-BSTNPA-01 1BS-0020 NOTE 2 HYDRAULIC LOCKING RING (6) (6) TANK CYLINDERS (20 GAL) (EXTERIOR DOOR) IRC ORC F S AR F IGURE 3 . 8 - 2 2 4 2 4 LINER 1-PI-AL025 NOTE 6 1-PI- 1BS-0206 AL028 NOTE 6 1-PI- R 1BS-0204 NOTE 6 AL026 R 1BS-0207 E-87 R E-89 1" TC 1-PI- -151-5 2 5 NOTE 7 AL027 1" 1BS-0205 TC R 1BS-0063 T HIS DRAWING CREAT ED ELECT RONICALLY LC PERSONNEL AIRLOCK VALVES
-151-2 ELECTRIC PENETRATION ASSEMBLIES KEY TYPE (FUNCTION)
EPA FUNCTION N2 PURGE VLV N2 PRESS IND 1 AUTOMATIC EQUALIZING VALVE EMERGENCY E-82 POWER 1BS-0022 1-PI-AL017 2 DIRECTIONAL CONTROL VALVE (DCV) 5 AIRLOCK E-83 COMN 1BS-0023 1-PI-AL018 3 PRESSURE REDUCING VALVE (PRV) 5 CP1-MEMEPE-01 E-84 POWER 1BS-0024 1-PI-AL019 4 CAM OPERATED VALVE (CDV)
" NOTE 4 " " E-85 COMN 1BS-0045 1-PI-AL015 5 FLOW CONTROL VALVE (FCV)
TC E-86 POWER 1BS-0046 1-PI-AL016 6 QUICK DISCONNECT TC E-87 POWER 1BS-0208 1-PI-AL029 7 MANUAL EQUALIZING VALVE E-88 COMN 1BS-0209 1-PI-AL030 8 DUAL RELIEF VALVE E-89 POWER 1BS-0210 1-PI-AL031 G G E-90 COMN 1BS-0211 1-PI-AL032 REF CKD 8 / 2 1/ 9 7 CP - 6 1BS-0202 1BS-0203 NOTE 3 NOTE 3 HANDWHEEL (TYP) PI AIRLOCK WALL E-90 2 E-88 CLASS (NUCLEAR SAFETY-RELATED) EMERGENCY AIR SAFETY CLASS 1 SEISMIC CATEGORY SAFETY CLASS 2 CLASS 1E SAFETY CLASS 3 ASSOCIATED CIRCUITS LINER TYPICAL EPA DETAIL LUMINANT 6 6 CPNPP IRC ORC GLEN ROSE, TEXAS FLOW DIAGRAM AIRLOCKS DWG. NO. SH. NO. REV. M1-0245 - CP-12 me104270.dgn A M1-0245 B C D E F G FINAL PRINT H
CPE A B C D E F G H REV DWN CHKDAPVD REMARKS JRMC DJL THIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE CP-12 03-10 03-10 2014 2014 FDA-2012-000230-02-00 PER SK-0002-12-000230-02-00. 1 1 NOTES
2BS-0044 , 2BS-0015 , 2BS-0056 , 2BS-0057 AND 2BS-0058 ARE LOCKED CLOSED IN MODES 1-4 EXCEPT DURING INGRESS AND EGRESS AS ALLOWED BY TECH SPECS. 2BS-0026
5 5 (2) 3. VALVES 2BS-0014/15/16/17/18 , 2BS-0025 , 2BS-0029/30 , 2 2 5 2BS-0036 , 2BS-0039/40 , 2BS-0043/44 , 2BS-0056 AND 2BS-0061 2BS-0030-HO 2BS-0025-HO 2 2BS-0062 2-PI-(2) TC AL021 ARE ASME VALVES. THE BALANCE ARE NON-ASME. 2BS-0030 2BS-0025 LC
-2505-2 4.
AL020 POSITIONED HORIZONTALLY. IRC ORC -151-5 " 5 (3) 5. TUBING IS PROVIDED AS A DRAIN TO THE HYDRAULIC TANK. 2 TC 2BS-0061 6. INSTRUMENTS PURCHASED COMMERCIAL GRADE AND HAVE BEEN (3) 2 LINER LC E-82 E-83 E-84 DEDICATED TO MEET THE DESIGN CRITERIA TO BE 2BS-0027 SAFETY-RELATED.
-151-2
2BS-0032 1" 1" R 2 REFERENCE DRAWINGS 2
NOTE 5 AIRLOCK VALVES 2BS-0004 ROTARY 2BS-0005 KEY TYPE (FUNCTION) 2BS-0006 NOTE 5 ACTUATOR 2BS-0007 1 AUTOMATIC EQUALIZING VALVE (EXTERIOR 2BS-0008 2 DIRECTIONAL CONTROL VALVE (DCV) 2BS-0047 2BS-0009 ROTARY 2BS-0048 DOOR) 2BS-0011 3 PRESSURE REDUCING VALVE (PRV) 2BS-0049 2BS-0012 5 FLOW CONTROL VALVE (FCV) ACTUATOR 2BS-0050 6 QUICK DISCONNECT (INTERIOR 2BS-0051 2BS-0052 7 MANUAL EQUALIZING VALVE DOOR) 2BS-0054 8 DUAL RELIEF VALVE 2BS-0055 (8) 2BS-0010 PERSONNEL " DOOR TEST AIRLOCK TUBING CP2-MEMEPA-01 (8) 2BS-0053 NOTE 3 ELECTRIC PENETRATION ASSEMBLIES (2) 2BS-0013 EPA FUNCTION N2 PURGE VLV N2 PRESS IND 3 E-82 POWER 2-BS-0022 2-PI-AL017 3 E-83 COMN 2-BS-0023 2-PI-AL018 (2) 2BS-0034 NOTE 6 2-PI- E-84 POWER 2-BS-0024 2-PI-AL019 2BS-0044 R AL013 E-85 COMN 2-BS-0045 2-PI-AL015 LC (7) NOTE 6 R E-86 POWER 2-BS-0046 2-PI-AL016 2-PS- 2BS-0029 AL024 LC (7) 2-PI-AL014 (6) (6) (6) (6) R (2) (5) 2BS-0036 NOTE 6 2BS-0043 PI 5 5 2BS-0016 2BS-0017 2 2 2BS-0039 2BS-0040 2BS-0019 LC LC LC LC AIRLOCK WALL 2 LINER 2 2 5 2BS-0018 2BS-0014 5 TD
NOTE 7 AL011 AL023 2BS-0021 NOTE 6 NOTE 6 R (2) (5) CP2-BSAPPA-01 HYDRAULIC LOCKED PUMP 1 2BS-0035 (5 GPM) CP2-BSTNPA-01 T HIS DRAWING CREAT ED ELECT RONICALLY 2BS-0020 HYDRAULIC 2BS-0058 TANK LOCKING RING LC (20 GAL) CYLINDERS (EXTERIOR DOOR) (6) (6) 5 2BS-0057 5 CP2-BSAPPA-02 LC HYDRAULIC LOCKED PUMP 2 (5 GPM) (6) (6) DRAWING M2-0245 REV CP-1 CP2-BSTNPA-02 HAS BEEN SPLIT INTO THE FOLLOWING SHEETS: HYDRAULIC TANK LOCKING RING M2-0245 (20 GAL) CYLINDERS M2-0245-A (INTERIOR DOOR) REF CKD 8 / 2 1/ 9 7 CP - 7 CLASS (NUCLEAR SAFETY-RELATED) SAFETY CLASS 1 SEISMIC CATEGORY SAFETY CLASS 2 CLASS 1E SAFETY CLASS 3 ASSOCIATED CIRCUITS LUMINANT 6 6 CPNPP GLEN ROSE, TEXAS FLOW DIAGRAM PERSONNEL AIR LOCK DWG. NO. SH. NO. REV. M2-0245 - CP-12 me104280.dgn A M2-0245 B C D E F G FINAL PRINT H
CPE A B C D E F G H REV DWN CHKDAPVD REMARKS JRMC DJL THIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE CP-6 03-10 03-10 2014 2014 FDA-2012-000230-02-00 PER SK-0003-12-000230-02-00. 1 1 NOTES
IRC ORC R REFERENCE DRAWINGS 2 LINER 1. CB&I DRAWING 74-2428-0200 REV CP-1 GENERAL ARRANGEMENT ESCAPE LOCK. ELECTRIC PENETRATION ASSEMBLIES 2 2BS-0204 2BS-0206 2 2-PI- 2-PI- EPA FUNCTION N2 PURGE VLV N2 PRESS IND AL028 AL025 R E-87 POWER 2-BS-0208 2-PI-AL029 2BS-0207 NOTE 4 2-PI- NOTE 4 E-88 COMN 2-BS-0209 2-PI-AL030 E-87 R AL026 E-89 POWER 2-BS-0210 2-PI-AL031 2-PI- R NOTE 4 E-90 COMN 2-BS-0211 2-PI-AL032 AL027 E-89 2BS-0205 NOTE 5 1" TC R PI
-151-5 2 5 1"
TC AIRLOCK WALL 2BS-0063 LC 2
-151-2 EMERGENCY AIRLOCK CP2-MEMEPE-01 TYPICAL EPA DETAIL
" " NOTE 3 TC " "
3 TC 3 G 2BS-0203 HANDWHEEL NOTE 2 (TYP) G 2BS-0202 NOTE 2 E-90 E-88 EMERGENCY AIR LINER F S AR F IGURE 3 . 8 - 2 3 IRC ORC 4 4 T HIS DRAWING CREAT ED ELECT RONICALLY 5 5 DRAWING M2-0245 REV CP-1 HAS BEEN SPLIT INTO THE FOLLOWING SHEETS: REF CKD 8 / 2 2 / 9 7 CP - 4 M2-0245 M2-0245-A CLASS (NUCLEAR SAFETY-RELATED) SAFETY CLASS 1 SEISMIC CATEGORY SAFETY CLASS 2 CLASS 1E SAFETY CLASS 3 ASSOCIATED CIRCUITS LUMINANT 6 6 CPNPP GLEN ROSE, TEXAS FLOW DIAGRAM EMERGENCY AIR LOCK DWG. NO. SH. NO. REV. M2-0245 A CP-6 me460000.dgn A M2-0245-A B C D E F G FINAL PRINT H
~ Rf::_A~I()_~ _§_ ..... CONTAINMENT ..... ') I I MIS-ORIENTED f': .._"" REACTOR VE S6EL 1 ~ SUPPORT
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8 CORRECT ORIE.rJTATION OF REACTOR VESSEL SUPPORT (T'YP.) Amendment 91 April 15, 1994 COMANCHE PEAK S E.S P L Ai"J FINAL SAFETY ANALYSIS REPORT REACTOR VESSEL PORTS UNITS 1 and 2 TUSI - UNITwz LOCATION OF MIS-OR!ENT~O SUPPORTS FIGURE 3.8-24
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1 LLJNG OF THESE BOLTS SHALL PRECEDE EL.
~--****~ TH E DRILLING OF INDICATED REBARS 1
2" vcurATOPENING IN LINER1 REMOVE ONE LINER TO VERIFY IMPACT ON CONG. er C(.C. CHIP TO LOCATE EL.81G ru-
"1 /
HE XlRE IN!=. DRILL HOL.E.S AND GROUT IN REBAR5. Ll NER MAY BE REPLACED OR OMITTED. PATCH Ll NER AS REQD. ALL AS DIRECTED BY THE LEVE:LJNG Fl ELD ENGINEER. STUD (.TYP) EL.BIG ~8'+/-1" l EL.81 zk" 4> ANCHOR 80LT(A5TM A-540, EL. 81:2/-o GR.B-23) .3'-IOLONG. .. - -- - -- ---~~~-- r---- (DRILL 15 GROUT IN 4"4> HOLE. GROUT MATERIAL AS APPROVED 7 El.81 BY ENGINEER IN THE FIELD)
~ ~~~~
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2 ~ EL819'-4~ 1 r* Amendment 91 April 15, 1994 EL. 812~0*
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.., COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT II UNITS 1 and 2 SECT. B-6 {fiGURE 3.8-24) --- 1--~---
CONCRETE RPV SUPPORTS (REIN F.)
Leg Leg & Throat Throat Appendix 3.8A- Figure 3-1
Irrelevant Indications A - A B - B Transient Sound weld Condition showing complete at end of weld. fusion Appendix 3.8A- Figure 3-2
Overlap with visible fusion Overlap Appendix 3.8A- Figure 3-3
Undercut I Undercut f Same Plane A B c Appendix 3.8A- Figure 3-4
CPE NOTE (1): BASED ON GDC 4, LEAK-BEFORE-BREAK APPLICATION (SECTION 5.4.14) THE LOOP RESTRAINTS ARE NOT REQUIRED AND MAY BE ELIMINATED. NOTE: STEAM GENERATOR FOR UNIT 1, THE REPLACEMENT STEAM GENERATOR ACTUALLY HAS 8 MASSES DISTRIBUTED ALONG THE VERTICAL CENTERLINE, AND THE SNUBBERS HAVE BEEN ELIMINATED FROM THE UPPER SUPPORT. STEAM GENERATOR UPPER SUPPORT REACTOR PRESSURE VESSEL REACTOR COOLANT PUMP CROSSOVER VERTICAL REACTOR COOLANT RUN RESTRAINT (1) PUMP SUPPORT ZG LUMPED MASS STEAM GENERATOR LOWER SUPPORT RCL GLOBAL COORDINATE SYSTEM Amendment 102 CROSSOVER LEG RESTRAINT (1) COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND2 CROSSOVER LEG RESTRAINT (1) REACTOR COOLANT LOOP SUPPORTS SYSTEM, DYNAMIC STRUCTURAL MODEL FIGURE 3.9N-l fsOOOOOy.dgn
10,450-9 VESSEL HEAD CORE BARREL FLANGE PRIMARY NOZZLE ----- 12 8 UPPER CORE PLATE 9 COMANCHE PEAK S. E.S, FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2
~-----*--*----*-*--- -----11 Reactor Pressure Vessel Lumped Mass Model FIGURE 3. 9N-2
8555-28 X ACTUAL l PIPE WALL THICKNESS T COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Through-Wall Thermal Gradients FIGURE 3. 9N-3
1o1 ( I) -I HYDRAULIC INSTITUTE
-7*:... . ,
_.J al ...;( ]1: C) -I -I ...;( TYPICAL PUMP >< NEMA i,..._._..._ MANUFACTURER LIMIT
0
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> WESTINGHOUSE & NEMA ~ < NOTE: PUMP BEARING VIBRATION LIMITS w
c.. AS MEASURED AT THE BEARING HOUSING 0 2 1-
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10-1 J02 2 4 6 8 I 03 2 4 6 8 I 04 2 6 a ro 5 FREQUENCY OF VIBRATION (CPM) COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 West u\.ghouse -Pump Bear1 ng Vibration Limits Compared to Industry Standards f--~Ftt1tJRE--*3. 9N --*~----- .
19039-1 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Control Volume for Momentum Equation AMENDMENT 21 MAY 21, 1981 FIGURE 3.9N-4a.
EYEBOLT PLUG RECEPTACLE ELCTRICAL LEAD TUBE DRIVE ROD ASSEMBLY PRESSURE HOUSING ********~******** ***** I LIFT ELECTROMAGNET ASSEMBLY MOVABLE GRIPPER ELECTROMAGNET ASSEMBLY MOVABLE GRIPPER STATIONARY GRIPPER ELECTROMAGNET ASSEMBLY STATIONARY GRIPPER DRIVE ROD ASSEMBLY LATCH ASSEMBLY PRESSURE HOUSING CONNECTION COIL STACK TO RCCA COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNIT 1 FULL LENGTH CONTROL ROD DRIVE MECHANISM Amendment 102 FIGURE 3.9N-5A
ll026-302 CABLE COKNECTIOM OPERATING COIL STACK ASSEMBLY COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNIT 2.. Full Length Conrtol Rod Drive Mechanism FIGURE ~ . QN-!\ 5
COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNIT 1 Full Length Control Rod Drive Mechanism Schematic Amendment 102 FIGURE 3.9N-6A
IJ026-303 COMANCHE PEAK S.E.S.. FINAL SAFETY ANALYSIS REPORT UNILZ Full length Control Rod Drive Mechanism Schematic FIGURE 3. 9N-6 B
BEFORE LOAD TRANSFER AFTER LOAD TRANSFER f*1G AT 70° AT 70° A B CD A B G) B LIFT COIL OFF 15.640 15.625 0.015 LIFT COIL OFF B 15.625 15.578 0.047 LIFT COIL ON 16.265 16.250 0.015 Ll FT COIL ON 16.258 16. 203 0.047 A AT 650° A A B CD A B LIFT COIL OFF 15.725 15.679 0.046 LIFT COIL OFF 15.679 15.641 0.038 L1FT COIL ON 16.375 16.387 0.068 LIFT COIL ON 16.387 16.291 0.016 SG COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Nominal Latch Clearance It---~--:----::-~~**** at Minimum and Maximum 1------T=-=e=m::pe rat ure FIGURE 3.9N-7
0.080 (/) 0.070 w
0.060 w LlrT COIL OFF} MG CLEARANCE AFTER 0 LIFT COIL ON LOAD TRANSFER c a::: 0.050 (!:) LU a::: 0 O.OitO 0 z: (/) 0.030 / / w
I-
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....J 0.020 ~--- lJj <.:> / - - \ : I Fl COIL ON } SG CLEARANCE BEFORE z: -< LOAD TRANSFER a::: 0.010 L I FT CO I L 0 FF w ....J 0.000 0 roo 200 300 !tOO 500 600 700 TEMPERATURE (°F) COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Control Rod Drive Mechanism Latch Clearance Thermal Effect
~-----------------~-----------
FIGURE 3. 9N-8
FUH AS59elY GUIDE ,.. CME Stl""l)ltf COLIHI toe**** wer E*EttY USORBU USENILY OrF-!ET IM!TRI,)IUTlTIOI COLUioO' SECOIII!UY COR( SU"lt JUTT rtP£ COLIMI
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{CJ\ICI FOR>~) UHU TIE PUTE
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Lower Core Support Assembly (Core Barrel Assembly) FIGURE 3.9N-9
UPPER SUPPORT ASSH1BLY SUPPORT COLuMN UPPER CORE PLATES COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Upper Core Support Structure FIGURE 3. 9N-1 0
6164--2 HEAD AND VESSEL ALIGNMENT PIN LOCATION SUPPORT COLUMNS GUIDE TUBE ASSEMBLY LOCATIONS COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Plan View of Upper Core Support Structure FIGURE 3. 9N-11
CPSES/FSAR FLANGE 2 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Reactor Internals Model for MARCH 31, 1980 DARI Variables Figure 3.9N-12
CPSES/FSAR 22
I 23 r 13 NOTE: NODE 2 IS THE REACTOR VESSEL SUPPORT 7 NODE WHICH IS COUPLED TO NODE I IN DARI-2 s*----e 9~---------~~---------~ 9 9 t 18 TWO-WAY SPRING-DAMPER ELEMENT NUMBERED n
...,.. ONE-WAY SPRING-SNUBBER NODE m WITH MASS REPRESENTING I INTERNAL COMPONENT PRELOADED ONE-WAY SPRING NODE m WITHOUT MASS ONE-WAY SPRING-SNUBBER ELEMENT WITHOUT STIFFNESS WITH INITIAL GAP SLIDING ELEMENT n COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Reactor Internals Mathematical MARCH 31, 1980 Model for WOST AS Variables Figure 3.9N-13
a::: "" 0 LL II, l I I I I l COMANCHE PEAK S. E.S FINAL SAFETY ANALYSIS REPORT Ut..JITS 1 and 2 TYPICAL FORCE-TIME PLOY FOR ONE LEG OF PIPING FK;unE 3 . 9 B-l
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.............._~------------------*------
NORMALIZED REFERENCE CURVE FIGURE 3. 9I3 2
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L I I l i l I I 0.5 i i 10 ~~ I I I I I I I I I I I I CUR' ~ES OF POS ITIVE r FC ~RCE DU RATION VER ~us WAT ER SEA. Vt )LUME F DR VARI )US VAL'.'E J ~REA 6 Amendment 74 October 14, 1988 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POSITIVE FORCE DURATION FIGURE 3
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y NOTE: CIRCLED NUMBERS ARE ELEMENT NUMBERS. AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MATHEMATICAL t*lODEL FOR RESPONSE SPECTRA SEISMIC VERIFICATION FIGURE 38 .' 1-1
y z X 3 18 NOTE: CIRCLED NUMBERS ARE AMENDMENT 61 ELEMENT NUMBERS. DECEMBER 19, 1986 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MATHH1ATICAL MODEL FOR RESPONSI SPECTRA SEISMIC VERIFICATION FIGURE 3B.l-2
y DATA NODES 53-6705: Do=18" t .375" W 173. LB/FT NODES 6705-178: Do= 24" t = .375" W = 280. LB/FT CONC. WGTS: NODE 64-471.LB 5001 -840.LB (5 FT.) SCALE: KEY X -ANCHOR
~
COMANCHE PEAK S. E. S. -RESTRAINT FINAL SAFETY ANALYSIS REPORT -SNUBBER UNITS 1 and 2 MATHEMATICAL MODEL FOR MISSING -MASS POINT MASS VERIFICATION FIGURE 38.1-3 AMENDMENT 61 DECEMBER 19, 1986
y X z
-KEY (j) MASS POINT X ANCHOR PIPE PROPERTIES O.D. = 10.75 INCHES 0
t = 0.594 INCHES W = 95.5 LBS.IFT AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MATHEMATICAL MODEL FOR MISSING MASS VERIFICATION FIGURE 38.1-4
5 6 7 4.5' 6.0' 2 6.0' OPERATING CONDITIONS PIPE THICKNESS PRESSURE TEMPERATURE 10" 0.593" 0 PSI 350°F 1 AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MATHEMATICAL MODEL FOR THERMAL ANALYSIS FIGURE 38.1-5
~~--------------~PJ___; ____________~~ Po !...,...___.--L-~*1 CLOSED OPEN END END CASE (A) FOR COMPARISON WITH ANALYTICAL RESULTS INITIAL CONDITIONS =
p /p 0 = 4.72, a 0 /a 1 = 0.80 1 DIMENSIONS = A 8 /A 1 = 0.6, l = PIPE LENGTH SPECIFIC HEAT RATIO = Y = Cp/Cv = 1.4 p = PRESSURE, a = SOUND VELOCITY, A = FlOW AREA AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 SUDDEN DISCHARGE OF A GAS FROM A PIPELINE THROUGH A NOZZLE (CASE A) FIGURE 38.8-1
GAS
~~~~3_1_N~~~p~*~~-'~*-=~7-9_o_F~~~~~~~~~~ Po = 0.229 PI I*
CLOSED END SFT *' OPEN END CASE {B) FOR COMPARISON WITH EXPERIMENTAL DATA AND HAND CALCULATION PRESSURE = p 0 = 14.7 psia, p = 14.7/0.229 = 64.2 psia 1 AREA= A 1 = : (0.25) 2 = 0.0491 ft 2 , A* = 0.2SA1 = 0.0123 ft 2 GAS CONSTANT = R = 53.35 ft - lbf /lb 0 R TEMPERATURE= T0 = 79°F = 539°R, T1 = T0 Po 3 P 3 DENSITY =Po= - = 0.0736 lb/ft , p1 = _J.. = 0.3215 lb/ft RT 0 RT 1 AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 SUDDEN DISCHARGE OF A GAS FROM A PIPELINE THROUGH A NOZZLE (r.A'.F R) FIGURE 38.8-2
5.00 . - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - c. 0 4.00 c. Q z Q 3.00 ~ 0 u .... 2.00 w Clll:
~ ~ w ac: 1.00 Cl.. 1.00 2.00 3.00 -4.00 5.00 6.00 7.00 8.00 LEGEND (CASE A)
- - - STEHAM
- - - - ANALYTICAL SOLUTION (REF 4&5)
AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 COMPARISON OF PRESSURE RESPONS! AT THE CLOSED END FIGURE 3B.8-3
4.oor------------------------------------------------------------------- - Q. 0 Q. 3.20 0 zw zw 0.. 2.40 0 t-
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a: 0.. LEGEND (CASE A) COMANCHE PEAK S.E.S. STEHAM FINAL SAFETY ANALYSIS REPORT
- - - ANAL YTJCAL SOLUTION (REF 4&5}
UNITS 1 and 2 COMPARISON OF PRESSURE RESPONSE AT THE OPEN END AMENDMENT 61 FIGURE 38.8-4 DECEMBER 19, 1986
1.2or--------------------------- D..
- 1.00 D..
0 zw 0 w 0.80 0 u 0.40 0.201~--~~--~-:--~~~-~~---L---...t..----J 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 LEGEND: TIME (a 1 t/L) (CASE B) COMANCHE PEAK S. E.S. STEHAM FINAL SAFETY ANALYSIS REPORT ANALYTICAL SOLUTION (REF 4&5) UNITS 1 and 2 COMPARISON OF PRESSURE RESPONSES BY STEHA~ & EXFERIMENT AMENDMENT 61 FIGURE 38.8-5 DECEMBER 19, 1986
626.64' 0 1,500'*18"0, f:0.02 22oo'*Jo"o t*0.04 20oo'*3e"ot*0024
~--~~--~~~~~--~~~~~~~~~>dVALVE o = 17.96 cr. -..... 17.'\ o = 30ch _...,.. Ho* 6 oo.o' a= 3,140ft/sec ~ a~ 3,300ft/aec:
AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 HYDRAULIC NETWORK FOR VERIFICATION PROGRAM FIGURE 38. 9-1
~.
2 1 2 0 :\ 0 5
.. 5 6 7 8 6 2 3
0 PIPE NUMBER AMENDMENT 61 DECEMBER 19, 1986 PIPE JUNCTION 5 COMANCHE PEAK S. E. S. e NODE NUMBER FINAL SAFETY ANALYSIS REPORT --f><l VALV£ UNITS 1 and 2 HYDRAULIC NETWORK FOR WATHAM VERIFICATION FIGURE 38.9-2
1200 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , 1000 800 Q <( w
600 400 200 0'---------------------~------~~--~~~~--~~~~~~~ 2 3 .. 5 6 7 8 9 10 11 12 13 14 15 16 17 18 lEGEND TIME (SECONDS)
- * - * -WATHAM
- - - - STREETER (REF 1)
- - - - - - WHAM(REF2)
AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 HEAD-VERSUS-TIME PLOT FOR JUNCTION J FIGURE 38.9-3
1400 r-------------------------------------------------l 1000
'H E 800 II Wool
~ Q Wool 600
\
~I 200 ~
TIME (SECONDS) LEGEND
- * - - * - WATHAN\
- - - - - - STREETER (REF 1)
- - - - - - W H A M (REF 2)
AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 HEAD-VERSUS-TIME PLOT AT VALVE FIGURE 38.9-4
GAS i
-LG PRESSURIZER VESSEL 1
DISTANCES FROM PRESSURIZER VESSEL: Lo =SAFETY /RELIEF VALVE LG =DOWNSTREAM AREA CHANGE LF: PIPE EXIT IXt: TRAILING EDGE OF SLUG 1 ...,..._FORCING FUNCTION DIRECTION,+ AMENDMENT 61 0 EPRI TEST 908 SEGMENT NO. DECEMBER 19, 1986 WATSLUG MODEL PIPE NUMBER l
3- LG TO LF FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 WATSLUG MODEL OF EPRI SAMPLE PROBLn1 FIGURE 38.10-1
QJ 5.5* 105 110 11!5 120 30 LEGEND 0:: NODE NUMBER 25 35 6.: MASS POINT 40 SUPPORT 1 022.7' 0= EPRI TEST SEGMENT NO. 45 55 0 ~ NUPIPE-SW MODEL PIPE SECTION NO. 50 240 2.!5'
@ ~
WE 30/31 23!5 2.30 SUPPORT 2 0 45.4' SUPPORT 4 SUPPORT 3 WE 34/35 WE 32/33 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 NUPIPE-SW MODEL OF EPRI AMENDMENT 61 SAf~PLE PROBLEM DECEMBER 19, 1986 FIGURE
~-------11 3B .10-2
50,000 , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 0.0 Lr A~ _,:J N l 1 I I
,..,..--'-"'-----...---------------1 II I
I I I I l i!* -IJ)
'-.~ I I
II .Q w -50,000 i-0 l a::: 0 lL I I J z w -100,000 1- I
~
(9 I w I (/) I
-150,000 1-
'I 200,000 I I I I I I I 0.0 0.1 0.2 03 04 TIME {SEC)
COMANCHE PEAK S. E.S. LEGEND FINAL SAFETY ANALYSIS REPORT WATSLUG
------ RELAP 5/MOD 1 UNITS 1 and 2 COMPARISON OF SEGMENT 2 AMENDMENT 61 DECEMBER 19, 1986 FORCING FUNCTION FIGURE 38.10-3
180,000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , 130,000 1.0 .0 w 80,000 0 0:: 0 Lt... rt) ....z w 30,000
~
(!) w C/) 0.0
-20,000
-70,000 ' - - - - - _ _ j ' - - - - - _ . . J L - -_ _ ___jL.__ _ __ _ j L - - - - - - - - l L - - - - - - - l L - - - - - - - - - - '
0.0 0.1 0.2 0.3 0.4 TIME (SEC) LEGEND COMANCHE PEAK S. E.S. WATSLUG FINAL SAFETY ANALYSIS REPORT
------- RELAP5/MOD 1 UNITS 1 and 2 COMPARISON OF SEGMENT 3 FORCING FUNCTION AMENDMENT 61 DECEMBER 19, 1986 FIGCJRE 3B .10-4
160,000~--------------------, EPRl PEAK 80,000
-C l) ..c 0
2 Q r-(.)
<[
LL.J -eo,ooo 0:: r-0:: 0 0. 0.
(/) N
-160,000 r-2 LL.J
(!) LL.J (/)
-240,000 EPRI PEAK
-320,000 02 40o,oooL----..l.-------:.1.:.~----::o.-=3------;:o. 4 0 1 TIME (SEC)
LEGEND COMANCHE PEAK S. E.S. NUPIPE- SW FINAL SAFETY ANALYSIS REPORT
---- EPRI TEST RESULTS UNITS 1 and 2 COMPARISON OF SEGMENT 2 SUPPORT REACTION AMENDMENT 61 FIGURE 3B.l0-5 DECEMBER 19, 1986
80,000,...----------------------, 40,000 Cl'l .0 z Q 1-(.) <{ LLJ 0 0::: 1-0::: 0 c.. c..
-40,000 1-z LLJ
~ C) LLJ (f)
-eopoo
-r2o,oooL-----..Jo.-J----o~.2::------='o.'="3------::o.4 TIME (SEC)
LEGEND AMENDMENT 61 DECEMBER 19, 1986 NUPIPE -SW
---- EPRI TEST RESULTS COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 COMPARISON OF SEGMENT 3 SUPPORT REACTION FIGURE 38.10-6
5.60 DAMPING VALUE = 0.005 OBE 4.80 4.00 ABSOLUTE SUMMATION OF Z3.20 CURVES 1 AND 2 0 ICIC: w ~2.40 u u CURVE 1 1.60 FREQUENCY Hz AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E. S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 PSPECTRA-ABSOLUTE SUMMATION OF ARS CURVES FIGURE 38.12-1
uo DAMPING VALUE = 0.005 SSE 1.20
- INPUT AMPLIFIED RESPONSE SPECTRUM
---*OUTPUT REQUIRED RESPONSE SPECTRUM 1.00 I I
Cll I I z I 0 0.80 j: < I w I I w 0.60 v I v I < I I ..... 0.-40 I I I J 0.20 I 0.00 . . ._ ....._ _. . ._ _. ._ _ _ _ _ _..__ _. _ _....._ _ _ _ _ _...__.... 0.00 0.10 0.20 0.30 0.40 o.so 0.60 0.70 0.80 0.90 1.00 PERIOD SEC AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 PSPECTRA-REQUIRED RESPONSE SPECTRUM GENERATION FIGURE 38.12-2
33 7!l" 13,0' 0 20.76 J ,.
~I'
! 10$ 11M
*~'
1M 10'> !10
.~-L .f!J I t~ !*~ill r
j 94- 1()! SlO ~"~@ , ls2 ~ l.l 96 l .
;ql ~* *~
~ 1@ @ @ I
~
J2 fl OS ** ., 48 [,._ 80 TO 7)_
"-~
@ r@r: @
I I " iS 66 l1 70 11 I I (':;j 51
@ )i 60
@ I@
i, r
,,~l'!i ,.
@+@
** so ll ~J ;* i ;;
1.. H: ** TE _@ ,J~ @
., 4~ u
@l
*1 I! :@'
f 3J 34 l~.L~ l' 3! l .H tO H I
@ @ @Y @ @ @
Q 25 26 2', ll,a a 30 l 3~ ll
....~ : !
ll 10 -JOINTS
@ @ 17 @ @ @
@-MEMBERS H l! 19 tl 10 21 !: I 23 I< j:
@ L@j 0
'0
(!) .@:' I 11
*l 12@ f t1 I
" 1$
- -(0 L---.1 TF
(;) (2) 0~~0-I:>'
""I 1 1 J IT-- ' ~
* ~.
AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. ES. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2
,..--------* ~*------~--1 FINITE ELEMENT MODEL OF THE FOUNDATION MAT FOR A PORTION OF
....____,.._T.LIJHE....__OFE -GAS BlllllU.~---
FiGURE 38 .13-1
YG MYY~~-------------- VYY¢9 Mxx Vxx vxx
-+----t~....... J 0 0 * *MxY MXY Mxx
-----*XP VYYC8)
-----=-----t....,. MYY MYx NOTES:
Mxx, Mvv, Mxv, THE MOMENT RESULTANTS,ARE OUTPUT AT THE AVAILABLE LOCATIONS ON THE ELEMENTS. Vxx. VYY ARE ALSO OUTPUT FOR THE TRANSVERSE SHEAR RESULTANTS 0 POSITIVE DIRECTION COMING OUT OF PAPER @POSITIVE DIRECTION GOING INTO THE PAPER XP, YP- PLANER COORDINATE SYSTEM XG.YG- GLOBAL COORDINATE SYSTEM XP IS PARALLEL TO XG AMENDMENT 61 YP IS PARALLEL TO YG DECEMBER 19, 19~6 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POSITIVE SIGN CONVENTION FOR RESULTS OF PLATE BENDING ELEMENT FIGURE 38.13-2
1 @ 53 @ 41 G) ss § 2 @13@16819@22@32@35@38~94 56 @ J @ 23 @ 43 0 57 @ 9
... 4 @ 24 @ 44 1~v 0 @
58 s@ 14 @17 @20Q iJ 2s @m@ 36@ J9 ~2 45
... ~
0 @ @ 6 @ 26 @ 46
...9 7 @! 27 @ 47 0 @ @
8 @ 28 @ 48 l~ ty 9 @ 1s @1s@ 21@ 29
@w§ 31@ 40 ~s 49 L
let>< y 0 @ @ 10 @ 30 @ so I X 9 N @ @ 11 @ 31 @ 51 X ROT 0. 0 v Y ROT 0. 0 Z ROT 0. 0 II @ @ @ I 12 @ 54 @ 52 L' I i AMENDMENT 61 7 - J OINT$ I Il DECEMBER 19, 1986 0-M EMBERS '
"' *v @-HANGERS
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MODEL - SUSPENDED CEILING FIGURE 38.13-3
r 10.5"
*j: 37.5"
.I
/~-,
5s} SEE WELD DETA:~ y y NOTES:
2 INDICATES JOINT AMENDMENT 61 DECEMBER 19, 1986
@ INDICATES MEMBER s INDICATES STRUCTURAL ATTACHMENT POINT COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 STRUDL INPUT ASME ANCHOR FIGURE 38.14-1
616~-7 0 0 00 e ee 11.973 FUEL ASS'Y
~<P~960 o+
0 e o8 AND CONTROL ROD Q 0 PITCH 0
,.~a~ 0 0 0 e e80 2*976 0 0 0 G G GUIDE 0 0 00 0 oo 00 THIMBLE 8.~66 0.04 TYP TYP.
INSTRUMENTATION SHEATH FUEL ASSEMBLY WITHOUT ROD CLUSTER CONTROL FUEL RODS 2~ REQ'D COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Typical Fuel Assembly Cross AMENDMENT 92 Section 17X 17 AUGUST 31, 1994 FIGURE 4.2*1
REF--------------------"---------------------.1 GRID ASSEMBLY TOP VIEW 0.875 DIA. REF BOTTOM VIEW COMANCI£ PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Typical 17X17 Fuel Assembly Outline AMENDMENT 92 AUGUST 31, 1994 FIGURE 4.2-2
7579-59 I \ 1,v-END PLUG I I
!\
i\ I I ~ I I ~ I
..... "~ SPRING I
"~
~'--
~~
( TYP) ~~ r:::
~~ ~
~
1\ ,....-
-" v 1\- -~
U0 PELLETS 2 1\ I FUEL-CLAD GAP lij ij,Q" (T YP)
~~ .,... \
" i\
~,-
ZIRCA LOY CLAD
~
~
I ~ I \r-- J l SPECIFIC DIMENSIONS DEPEND ON DESIGN VARIABLES SUCH AS PRE-PRESSURIZATION. POWER HISTORY. AND DISCHARGE BURHUP COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Typical AMENDMENT 92 Fuel Rod Schematic AUGUST 31, 1994 FIGURE 4.2-3
CPSES/FSAR Figures 4.2-4A,B thru 4.2-7A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.2-4A,B thru 4.2-7A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.2-4A,B thru 4.2-7A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.2-4A,B thru 4.2-7A,B have been deleted I 92 Amendment 92 August 31, 1992
CROM IJ!liVE ROO Flll. U:NGnl QJIO£ TUBE FUEL ASSEI4:L Y ASSEMBlY RCC ASSEMill Y ASSEI4:LY COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Full length RCC and Drive Rod Assembly With Interfacing Components FIGURE 4.2-8
160.15 150.40 r 1.1140 MAX.
\ 4~~~~~~~~-~~--~--~-~~~-~;~-~--=-~-~--~~---~-~~-=m3 -k f qp;
"'"" ,.\ -- 0.315 DIA MAX I. .,2 00 ABSORBER lEH(lT" l
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Typical AMENDMENT 92 Rod Cluster Control AUGUST 31, 1994 Assembly Outline FIGURE 4.2-9
r----0.381 DIA. NOM. ~~~==~str:==~====:3~l~T~~~~~~~~~~i'~;s~~~~~~~~4~2=_~oo::*:~~i~~B-E--RM-AT_E_R_IA-l~r~~0~.~~*:*~:~.'~---~ 1 . . . - - - - - - - - - - - - - - - - - - - - - - 151.9 *- AMENDMENT 84 FEBRUARY 28, 1992 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Full Length Absorber Rod All Ag-ln-Cd Design FIGURE 4.2 *10
CPSES/FSAR Figure 4.2-11 Has Been Deleted AMENm1ENT 84 FEBRUARY 28, 1992
I 1 2 ~ POISOII LEIIGIM
--= ***----- - --- ...
f--*- - H --- . ---- l i
,.. ,.. t;
+ -
i
- r ---- - 1)i)i}i} '(:.LL.L-::z
- ./-0
+-- _..
~~
r-- J =:
~
~ SPRINGS
.. - ---- .. - -- _../
AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Typical Burnable Poison Assembly FIGURE 4. 2-12
r~* 2.970 TYP. ~-~ 1- 2.415 TYP. j 1*-1485 TVP. l 88.00 SECONDARY SOURCE ANTIMONY BLRYLUUM 8.104 6.320 SQ ALUMINUM OXIDE ABSORBER _ _ _ _ _ _ ___, II 1 '50~--- 32.50 ~-........; I PRIMARY SOURCE i CALIFORNIUM
~--~--~ 4.385 ------+--~--~~- 7.942 ~J X- 151.565 143.107
-8,458 Y X + END PLUG LENGTH
~ 9.583 PHI MARY BURNABLE StCONDAAY THIMBLE SOUAC<. ABSORBtH SOURCt PlUG COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNIT2 AMENDMENT 84 Composite Core Component FEBRUARY 28, 1992 Rods and Assembly Outline FIGURE 4.2-128
CPSES/FSAR Figures 4.2-13A,B and 4.2-14 have been deleted 1 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.2-13A,B and 4.2-14 have been deleted 1 92 Amendment 92 August 31, 1992
"'150.4
*-=z, 1- 88.0 SECONDARY SOURCE ANTIMONY BERYLLIUM
.I NOTE: ALL DIMENSIONS ARE IN INCHES t
0.381 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT Typical Secondary Source Assembly THIMBLE AMENDMENT 92 SECONDARY SOURCE PLUG AUGUST 31, 1994 FIGURE 4.2-15
-q 13
- c:() I::>
-E:(J 1::::>
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT Typical AMENDMENT 92 Thimble Plug Assembly AUGUST 31 1994 I FIGURE 4.2-16
CPSES/FSAR Figure 4.3-1 has been deleted.
9 0 8 -
1- !i: :::E 0'1 0'1 6 -12 w(/') (/') w Cl.. Cl.. 0 0 1- 1-0 0 5 -16 (/') (/') 0::: ....I w w
(!) 4- / -20 1..1...
7I Pu239 0 1..1... 0 z: 0 z: 3 1-0 Cl.. 1- :::E <..) :::,) I
0 z: 0 0::: 2 -28 0
<..)
Cl..
-32 0 -36 16 20 21j. 4-0 BURNUP, (GWD/MTU)
COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Production and Consumption AMENDMENT 92 ~f Higher Isotopes AUGUST 31, 1994 'Tvni ",., 1 ) FIGURE 4.3-2
1600 NOTE: HOT FULL POWER RODS OUT ~ Q.. 1~0
0
.................. WITHOUT BURNABLE POISON
~ 01::: 1- ~, ffi
BURNUP DIFFERENCE z:: 1300 MWD/MTU 0 01:::
~ ...J ct IJOO WITH BURNABLE POISONS 01:::
(.) 0 0 2000 IJOOO 6000 8000 10000 1~00 lliOOO CORE AVERAGE BURNUP (MWD/MTU) COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Boron Concentration va Pint Cycle AMENDMENT 92 Bumup Wtth and Wllbout Burnable Absorber Rode (fypical) AUGUST 31, 1994 FIGURE 4.3-3
181181 181 181181 o181 D 181o 181 ~ ~ r8J r8J 181 0 181 0 I8J 181 I8J D r8J r8J 0 181 D I8J 0 181 181 r8J r8J ~ 181 0 181 D 181 181rgr 181 181181 0181 D 1810 24 BP'S 12 BP'S ~CORE CENTER 181 181 181 181o 1810 0 0181 181 D 181 D D 0 0 181 0 0 1811810 D D 0 181 0 181 0 18100 0 D 0 0 181 0 0 0 0 D oo 1810 0 o181 9 BP' S 8 BP'S CORE CENTER CORE CENTER
~ 1:
D 181 D 181 0 f810 0 Do 181000181 0 0 181 0 0 00000 0 I8J 0 0 D 0 0 0 0 0 0 0 0 0 D 0 o o o 0 Do 0 oo 4 SP'S 3 BP'S COMANCHE PEAK S.E.S. AMENDMENT 92 FINAL SAFETY ANALYSIS REPORT AUGUST 31, 1994 UNITS 1 and 2 Burnable Abaotber Arrangement Wlthia an Aucmbly (Typical) FIGURE 4.3-4
180. R P N M L K J H G F E D C B A 4 4 4 1 3b4 9 lP lP* 9 2 23 23 4 8 4 24 3 3 24 12 4S 8 8 12 24 4 9 12 8 8 8 12 9 5 4 4 8 8 8 8 4 4 6 24 8 8 12 8 8 24 7 go* 8 4 8 8 12 12 8 8 4 24 8 8 12 8 8 24 9 4 4 8 8 8 8 4 4 10 9 12 8 8 8 12 9 11 24 12 8 8 4S 12 24 12 3 24 4 8 4 24 3 13 9 lP lP
*s* INDICATES SECONDARY SOURCE ROD *p* INDICATES PRIMARY SOURCE ROD COMANCHE PEAK S.E.S. *-.* INDICATES DEPLETED PRIMARY SOURCE ROD FI'JAL SAFETY ANALYSIS REPORT Typical Burnable Absorber AMENDMENT 92 Loading Pattern AUGUST 31, 1994 FKJURE 4.3-5
G F E D c B A 0.93 -
~~-~ EJDDDDDD I
9 6 0
~~-~ EJBDDDDD 2
1 Dc:JEJDDDD 3 BGBBDD J.,w 2 ~~-~ 3~~-:~2 EJGEJEJEJD lj. :=:0.+~6~EJBBEJEJ 0.~2 ~Q ou 15 EJ.Bl!. CALCULATED F :H = 1.40 t KEY: I VALUE REPRESENTS ASSa.tBLY t RELATIVE POWER COMANCHE PEAK S. E.S. AMENDMENT 92 FINAL SAFETY ANALYSIS REPORT AUGUST 31, 1994 UNITS 1 and 2 Nonnalized Power Density Distribution Near BOL, Unrodded Core, HFP, No Xenon (Typical) FIGURE 4.3-6
G F E 0 c B A I 1.00 - -- -- -- - GDDDDDD I 9 I.:IZ IO~I.~S BEJDDDDD ~~~~*: BBEJDDDD 5 12 "'" - - 41.:0~7 GEJ6 G 0 0 13:=:1:t:.:~=3~GGEJGEJD _GBGG6 1.36 86 I4---0+.l_ IS o.'ao ~~~ CALCULATED F:H =
~~~ K~:VALUE REPRESENTS ASSEMBLY =::::ti===-======-=====:...=====:.J 1
t RELATIVE POWER AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Nonnalizcd Power Density Di.lt. Near BOL, Unroddcd Core, HFP, Equilibrium Xenon (Typical) FIGURE 4.3-7
t IH G F E D c B A rt. 8 0 . 88 r- * -
I VALUE REPRESENTS ASSEMBLY RELAT IVE POWER AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Power Density Distribution Ncar BOL, Group D 35~, HFP, Equilibrium Xenon (Typical) FIGURE 4.3-1
G F E 0 c B A
- -- -r-- --
< BDDDDDD I
I 9 17 0
;: :t: : : : I.~S GEJDD D D D I l.:l BBEJDDDD 2 ~~.~=~::::::GBBEJDD I
3
~~*:=,s::::::BBBBEJD
~ . . ._*-+-~----~BEJBEJ 6 0 5 0.~ I 666 CALCULATED F:H = I.:JJ
=:::t*===-=====~====:.:::====:1 KEY:
I VALUE REPRESENTS ASSEMBLY t RELATIVE POWER AMENDMENT 92 AUGUST 31. 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Nonnali2cd Power Density Distribution Near MOL Unrodded Core, HFP, Equilibrium Xenon (Typical) FIGURE 4.3*9
G F E D c B A I i 8 - o.97 -- - r- . -t EJDDDDDD I 9 0
. - -+- - tO.~? GEJDDDDD 10
~1.: EJGc:JDDDD 12 L. . .-1°*~ - - - ~ GGB EJ D D II 12 9 13
" '"- -l~*:~ q 666 EJ 6 D 1 ~ ::=o.::t::s~6EJEJ EJ EJ IS 0.~6 EJ*85 ~EJ.6S L__j CALCULATED KEY:
F:H 1.29
=
==1,==::..!::=:==:...::=====-==:=::...J I
VALUE REPRESENTS ASSEMBLY RELATIVE POWER AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Powet" Denlity Distribution Near EOL. Unrodded Core. HFP, Equilibrium Xenon (Typical) FIGURE 4.3-10
F E 0 C B A 1-t I VALUE REPRESENTS ASSEMBLY RB.ATIVE POWER COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Power Density Distribution Near EOL, Group D@ 35%, HFP, Amendment 95 Equilibrium Xenon (Typical) February 2, 1998 FIGURE 4.3-11
1.02 1.02 1.03 1.02 1.05 1.08 1.02 1.06 I. 12 1.03 1.08 I. Jl+ I. 17 I. 16 1.03 I. 10 [X I. 17 I. 18 [X 1.03 1.08 I. 14 I. Ill I. 16 I. 18 I. 17 1.03 1.08 I. Ill I. Ill I. 16 I. 19 I. 17 I. 17 1.03 I. 10 [X I. 16 I. 18 1.03 1.09 I. 14 I. 14 I. 16
>< I. 19 I. 19 I. 17 I. 20 [X I. 17 I. 20 I. 18 1.03 1.09 I. 15 I. 15 I. 16 I. 19 I, 17 I. 17 I. 20 I. 18 I. 18 1.04 I. I I 1.04 1.09
[X lo I. 18 I. 18 J5 I. 18 I. 17
>< I. 19 I. 19 I. 17 I. 19 [X I. 17 I. 19 1.20 I. 20 I. 17 I. 17 I. 20 I. 18 1.04 1.08 I. 14 [X I. 18 I. 18 I. 16 I. 16 I. 18 I. 16 I. 16 I. 19 I. 19 [><
1.04 1.06 I. 10 I. 14 I. 16 [X I. 16 I. 16 [X I. 16 1. 16
~ I. 17 I. 15 I. I I 1.04 1.05 1.07 1.08 I. 10 I. 12 I. 10 I. 10 I. 12 I, 10 I. II I. 12 I. II 1.09 1.08 1.07 1.04 1.04 1.04 1.04 1.05 1.05 1.05 1.05 1.05 1.05 1.05 I. 06 1.06 1.06 1.06 I. 06 1.061 AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Rodwilc Power Distribution in a Typical Assembly Ncar &I, HFP, EQ, Xenon, Un.rodded Core FIGURE 4.3-12
0.98 0.98 0.99 0.98 1.00 I. 03 0.99 1.02 1.07 X 1.00 I. 03 1.09 I. I I 1.09 1.0 I I. 06 [X I. II 1.11 [X 1.00 1.014 1.08 1.07 I. 08 I. 10 1.08 1.00 I. 014 1.08 1.07 1.08 I. 10 1.08 1.'08 1.0 I 1.06 X 1.09 I. 10 1.00 1.01+ 1.08 1.07 1.08 [X I. 10 I. 10 [X I. 10 1.08 1.08 1.10 1.08 1.00 I. 014 1.08 1.07 I. 08 I. I 0 1.08 1.08 I. tO 1.08 1.08 1.0 I 1.06 [X 1.11 1.11 [X I. 10 I. 10 [X 1.10 I. 10 [X 1.00 I. 03 1.09 I. II 1.09 I. II 1.08 1.08 I. 10 1.08 I. 08 I. II 1.09 0.99 I. 02 1.07 X I. II I. II 1.07 1.07 1.09 1.07 1.07 I. II I. II X 0.98 1.00 1.03 I. 07 1.09 0.98 0.99 1.00 1.02 1.03 X 1.08 I. 08 [X I. 08 1.08 [X 1.09 1.07 1.03 1.06 I. 014 I. Ott 1.06 1.04 1.014 1.06 I. 03 1.02 1.00 0.98 0.98 0.98 0.98 0.99 1.00 1.0 I 1.00 1.00 1.0 I 1.00 1.00 1.01 1.00 0.99 0.98 0.98 0.981 AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Rodwisc Power Diatribution in a Typical Anernbly Ncar EOL, HFP, Equih'brium Xenon, Unrodded Core FIGURE 4.3-13
2.0
'. 5 a::
1.1.1 3: c a.. 8 1.0 N ...J < p ::: 1.0 ii D = 0. I ~ AO :::-8.8 I 0.5 0.0 0 100 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Axial Power Amendment 95 Shapa Occurrin1 at SOL February 2. 1998 FIGURE '-H'
2.0 ~------------------------------------------------~ POWER= O.S 9 0 55 AO = -2~.03 I. 5 POWER = 0. 5 D = 0.21 AO 8.20 0::: w..J 3: 0 0.. t.O 0 w..J N <1:
0::: 0 0.5 0.0 0.0 0. I 0.2 0.3 O.t+ 0.5 0.6 0.7 0.8 0.9 ! .o PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Typical Axial Power AMENDMENT 92 Shapes Occurring at MOL AUGUST 31, 1994 FIGUAE 4.3-15
D j. 32 AO =-2" p = 0.5
'. 5 D=0 6 AO 6. 59 c:r::
p ::: i. c w D = 0.
0 c.. 0 i .0 w N <( ~ 0
FINAL SAFETY ANALYSIS REPORT AMENDMENT 92 Typical Axial Power AUGUST 31, 1994 Shapes Occurring at EOL FIGURE 4 . 3 -16
Axial Relative Power I. 5 1.0 I I I I I I I I CORE AVERAGE 0.5 ~/ -- -- ADJACENT TO D BANK w' 1
---- REMOVED FROM 0 BANK
- - - - - - PERIPHERAL LOW POWER ASSEMBLY 0.0 CORE CORE CORE HEIGHT TOP BOTIOM AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comp of Assembly Axial Power Diat. with Co~ Average Axial Diat. D. Bank SLightly Inserted FIGURE 4.3-17
CPSES/FSAR Figures 4.3-18 thru 4.3-23A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.3-18 thru 4.3-23A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.3-18 thru 4.3-23A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.3-18 thru 4.3-23A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.3-18 thru 4.3-23A,B have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.3-18 thru 4.3-23A,B have been deleted I 92 Amendment 92 August 31, 1992
0.759 0.792
~.3 I. 217 I. 22~
0.6
I. 229 I. 229 I. 225 I. 218
-0. 3 -0.9~
I. 109 I. 077 I. 107 1.092
-0.2' 1.~
I. 202 I. 223
-2. r 2. 7':
0.523 1.217 I. 22! I. 217 Oo 5~8 I. 203 I. 233 I. 210
~+. 6 . 1.1: 1.0' -0.6' I. 229 I. 229 I. 189 I. 220
-3. 3~ -0.7'1 I. 217 ...,.___ CALCULATED I. 211 ...,.___ MEASURED
-0.5'~
....,.___ DIFFERENCE PEAKING FACTORS 1.5 1.357 2.07 LOCATED AT M-8 SOUTH COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT Comparison Between Calculated AMENDMENT 92 and Measured Relative Fuel AUGUST 31, 1994 Assembly Power Distribution FIGURE 4. 3-24
BOL NO XENON POWER AT 70'/ 1.2 BANK D 25% INSERTED 1.0 CORE AVERAGE a:::: LIJ FROM INCORE MAP 3: 0 AO= 21 0.. LIJ 0.8 1-
<( CALCULATED
.....1 LIJ AO 3r a::
...J 0.6
<(
<(
, O.lt Ql("") z
m ro-s Ql ..... cl>J> 0.2 z~Z (!}(/} c:O -tO
-s:::s ~
ro -1 -m I -h N ):::> ....... Z-o xn 0
~};
U'1
..... QI Q)
Ql-
--'rl
0 10 20 30 ltO 50 60 70 80 90 100 V'l--' c: N
~:A
(/) BOTTOM PERCENT OF CORE HEIGHT TOP
-oro mm roo. "'0*
Q(f)
-1
627~-5~ x REACTOR l 0 REACTOR 4-
\J REACTOR 2
0 3.0 0
'J *
'1 "0< o*
'1 0 0
X \1 X
*ol
0 X X X ~ ~
* ** 8 ~f
0
<o. Q 0
0~
~ **
X 1.5 4-5 0 30 -25 15 -10 -5 0 5 10 15 20 25 30 INCORE AXIAL OFFSET (%) COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Measured Values of Fq for Full PowPr Rod Configurations FIGURE 4. 3-21'
- -1.2 1.1.. 0
Q..
-1.4
.....Q) 1-
'1:>
-1.6 a.
'1:>
1-z: L.IJ -1.8 u 1.1.. 1.1.. L.IJ C) u -2.0 L.IJ 0:::
1-0::: L.IJ Q..
-2.2
_, -2.4 0::: L.IJ 0.. Q.. 0 C)
-2.6 500 600 700 800 900 1000 1100 1200 EFFECTIVE FUEL TEMPERATURE Teff (°F)
AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Typical Doppler Temperature Coefficient at BOL and EOL Cycle 1 FIGURE 4. 3-27
-6
-0::: w 3:
-8 0
c.. lil!!:
0..
<'()
-10 Cl..
<'()
1-z; w <...) l.L l.L w -12 0 <...) 0::: UJ 3: 0 0.. ...J z; 0 -lij 0::: lJ..J ...J 0.. c.. 0 0
-16
-18 0 20 40 60 80 100 POWER (PERCENT OF FULL POWER)
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 92 Typical Doppler..Only Power AUGUST 31, 1994 Coefficient- SOL, EOL FIGURE 4.3-28
0
-500 u
Q..
1-
<.:1' 1.1.,1 u..
1.1.,1 Q 0::: 1.1.,1
0 Q..
=
s a:: 1.1.,1
....J Q..
Q.. 0 Q
-1000
-1500 0 20 110 60 80 roo POWER {PERCENT OF FULL POWER}
COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT Amendment 95 February 2, 1998 Typical Doppler-Only Power Defect- BOL EOL FIGURE 4.3-29
1500 PP14 \ "U:' 0
~
u I 000 PPt-1 0..
~
f-
.0 Cl.. 0 co f-z:
U1
<:..)
u_ u_
-10 i.J..J 0
u i.J..J 0:: f-
-20 <:(
a:: i.J..J 0.. 0 aJ PP~1 f-a:: 0 f-
<:(
a:: -30 i.J..J a 0
~
-40 0 100 LW 300 400 500 600 MODERATOR TEMPERATURE (°F)
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSlS REPORT UNITS 1 and 2 AMENDMENT 92 Moderator Temperature Coefficient AUGUST 31, 1994 - BOL, No Rods (Typical) FIGURE 4.3-30
20 10 0 l.J.._
~
(..) 0.. 0 f-
.0 Q_ -10
f-z: w (..) l.J.._ u.. w -20 0 (..) w c:r: <( 0::: I.J.J 0..
-30 Cfi f-0:::
0 4 0::: I.J.J 0
-40
~
-50 0 100 200 300 4Qo 500 600 MODERATOR TEMPERATU~E (°F)
AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Moderator Temperature Coefficient, EOL FIGURE 4.3-31
5 0 0 1..1..
-5 0
a..
1-(() a_ -10 (() 1-
I.J.J (,..)
-15 1..1..
1..1.. I.J.J 0 (,..) I.J.J 0:: 1-0:: I.J.J
-20 a..
I.J.J 1-0:: 0 1-
<C -25 0::
I.J.J 0 0
-30 0 500 1000 1500 SOLUBLE BORON CONCENTRATIONS (PPM)
AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Moderator Temperature Coefficient u a Function of Boron Concentration
- BOL, No Rods (Typical)
FIGURE 4.3-32
0
-5
0 0..
-10
<0
<I..
;.Q
=
1- -IS I.U u u.. u.. I.U 0 u -20 I.U 0:::
;:::)
1-
<a:::
I.U 0.. CJ 1-
-25 a:::
0 1-a::: I.U Q
~ -ll
-35
-40 0 500 1000 1500 BURNUP (MWO/MTU)
COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1 and2 Amendment 95 HFP Temperature Coefficient February 2, 1998 for the Critical Boron Concentration (Typical) FIGURE 4.3-33
-10 - ec:::
Li..J 3: 0 0..
..... -!2
Li..J u ec::: Li..J 0..
u 0.. - 0..
..0 c... .c r--
Li..J -16 u u... w_ Li..J 0 u ec::: -18 rEOL 1..:.... 3: 0 0.. -l <( f-0 f-
-20
- 2?.
0 20 40 60 80 100 POWER LEVEL (~ OF FULL POWER) COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Toca.l Po-r Coefficient
0 500 1000
=<::
u c... CL I-u w Ll.. w 1500 0 0::: w 3: 0 c... _J <t I-0 I-2000 2500 0 20 4-0 60 80 100 POWER LEVEL {PERCENT FULL POWER) AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Total Power Defect
12288 E!] & @ & ~ r:-,
,s o' L-J <~ ~"
,ry
IS C I L-.J [;] (~) *~ (o) ~ r3 1 r: , I cI 13 o I L-.J L-.J £ 0 \f] 0 k{
~y 0
I
~ \f] (0 \fl s c ~ ~
£ rs 1 0 \fl 0 r:-, £ I DI IS C I L-J L-.J ~ 0 I~ 1(,' i'!.J ~
IS C I L-.J <Y @ ~~ r: , IS D I 1..-.J
~ ~ £ _(ill_
SHUTDOWN BANK SA 8 SHUTDOWN BANI\ sB 8 SHUTDOWN BANK & so 4 &4 SHUTDOWN BANK SE I~ CONTROL BANK A lj. CONTROL BANK B 8 CONTROL BANK c 8 CONTROL BANK D COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Rod Cluster Control Assembly Pattern FIGURE £1.3-36
c.. lj.() I.&J (I)
(,.) c..
i Q 0 0::: <C 20 z: 1.1.1 0::: I.&J 1.1.. 1.1.. Q 10 0 50 100 150 200 250 STEPS WI THDRAWM COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT Amendment 95 February 2, 1998 Accidental Simultaneous Wlthdrawel of 2 Control Banks EOL. HZP Banks C and B Moving in Same Plane (Typical) FIGURE 4.3--37
1.0 0.9 0.8 1-0 0.. (/) NORMALIZED SCRAM TIME <t 0 0.7 u.. 0 0.. ~ 0.6 ~ w <..) 0.5 ~ t:; 0 0 w tL. 0.. 0." ~ C1 UJ 0.3 <..) ~ 1-(/) 0.2 0 0.1 0.0 0.0 0.1 0.2 0.3 0." 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 '*" 1.5 1.6 1.7 TIME AFTER DROP BEGIMS/OROP TIME TO TOP OF OASHPOT COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Trip Curve AMENDMENT 92 AUGUST 31, 1994 FIGURE 4.3-38
~ 0.5 o.o L _______j=:::::::::::====~ 100 50 0 ROD POSITION (PERCENT INSERTED) AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Rod Worth Vs Percent lnaertion
FIGURE 4.3-39
5 --------------------------------------------------------------------------------~ 0 !z UJ
-5
(..) 0:: UJ ~ -10 l;:j (I) CURVE I It -15 0 ...J BURN UP PERIOO STABILITY INDEX ""'>< -20 CURVE (MWO/MTU) (HOURS) (HOURS-I)
""' I 1550 32.4 -0.0141 2 7700 27.2 -0.014
-25
-30 L-----L-----~--...l----~----~----...l----~--~--~~~--~--~--~~--~----~--~----~--~
0 72 TIME COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT Amendment 95 UNITS 1 and 2 February 2, 1998 Axial Offset Vs. Time PWR Core wllh a 12-FI Helghl and 121 Assemblies FIGURE 4.3-40
10 l.~ 8
;:t ...... 6 z:
c( a:: 0 ll c(
\
\
**\
I 2 N STABILITY INDEX= -0.076 (HR.- I)
* !c;r......
z: c( 0 a:: 0 c(
* \, .*Y 0"'
Ul
- ll
*)liP' 0
z: Ul a:: Ul u.. u..
- 6 0
1-
.....1
- 8 RCC E-ll
...... -10 z:
c( a:: 0 c( -12 N43 Hill
-Ill
-16 0 8 12 16 20 2\l 28 32 36 llO qq 148 52 56 60 61l HOURS AFTER WITHDRAWAL Of RCC E-ll COMANCHE PEAK S.E.S FINAl SAFElY ANAl.YSIS REPORT Amendment 95 UNITS 1 and 2 February 2, 1998 XV Xenon Tesl Thermocouple Response Quadrant TKI Olfference \lr.. Time FIGURE43-41
CPSES/FSAR Figures 4.3-42 thru 4.3-45 have been deleted 192 February 2. 1998
CPSES/FSAR Figures 4.3-42 thru 4.3-45 have been deleted 192 February 2. 1998
CPSES/FSAR Figures 4.3-42 thru 4.3-45 have been deleted 192 February 2. 1998
CPSES/FSAR Figures 4.3-42 thru 4.3-45 have been deleted 192 February 2. 1998
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
Key: 1.096
.6.h/.6.h 1.001 GIG 1.029 1.120 1.001 1.001 1.153 1.074 1.185 1.000 1.001 1.000 1.166 1.209 1.162 1.185 1.000 1.000 1.001 1.000 1.223 1.170 1.188 1.065 1.238 1.000 1.001 1.000 1.002 1.000 1.126 1.161 1.093 1.086 0.916 0.967 1.001 1.001 1.002 1.002 1.001 1.001 1.025 1.025 0.990 0.975 0.823 0.466 1.002 1.002 1.002 1.002 1.000 0.997 For Radial Power Distribution 0.717 0.780 0.664 0.563 Near Beginning of Life, Hot Full 0.999 0.999 0.998 0.997 Power, Equilibrium Xenon Calculated F N = 1 .34
.6.H COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Radial Flow and Enthalpy Distribution at 4-Ft Elevation Typical of Cycle 1 Figure 4.4-2 Amendment No. 103
Key: 1.096 0.996 r r r r *- * ..6.h/..6.h GIG 1.026 1.120 1.002 0.994 1.155 1.072 1.188 0.991 0.998 0.988 1.169 1.212 1.165 1.189 0.990 0.986 0.990 0.998 1.228 1.173 1.191 1.065 1.242 0.985 0.989 0.988 0.998 0.981 1.129 1.165 1.095 1.086 0.916 0.963 0.992 0.990 0.995 0.996 1.009 1.006 1.024 1.025 0.989 0.973 0.819 0.468 1.000 1.000 1.003 1.004 1.018 1.018 For Radial Power Distribution 0.715 0.777 0.663 0.562 Near Beginning of Life, Hot Full 1.022 1.019 1.021 1.019 Power, Equilibrium Xenon Calculated F N -- 1.34
..6.H COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Radial Flow and Enthalpy Distribution at 8-Ft Elevation Typical of Cycle 1 Figure 4.4-3 Amendment No. 103
Key: 1.097
.6.h/.6.h 0.995 GIG 1.026 1.121 0.999 0.993 1.157 1.073 1.189 0.991 0.996 0.989 1.170 1.215 1.166 1.190 0.990 0.980 0.991 0.990 1.231 1.175 1.193 1.066 1.243 0.987 0.990 0.989 0.997 0.987 1.130 1.165 1.095 1.087 0.914 0.961 0.993 0.991 0.995 0.996 1.005 1.003 1.023 1.024 0.987 0.971 0.817 0.469 1.000 1.000 1.002 1.003 1.011 1.030 For Radial Power Distribution 0.711 0.774 0.660 0.560 Near Beginning of Life, Hot Full 1.016 1.013 1.019 1.025 Power, Equilibrium Xenon Calculated F N - 1.34
.6,H COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Radial Flow and Enthalpy Distribution at 12-Ft Elevation Typical of Cycle 1 Figure 4.4-4 Amendment No. 103
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992
0 T 0 TO T 0 T 0 T T T 0 0 0 0
@]To T T 0 T T T 0 0 0 0
~ I I TO T 0 T 0 T T T 0 T 0 0 0 u TO TO TO TO T 0 T 0 TO 0 T 0 0 0 0 T T TO TO T T 0 T T ~L 0 0 D D T 0 T 0 0 T D Pi- T D T 0 D To! T TO T TO D T T 0 T - THERMOCOUPLE (50) 0- MOVABLE INCORE DETECTOR (58 LOCATIONS) COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Distribution of Incore AMENDMENT 84 Instrumentation FEBRUARY 28, 1992 FIGURE 4.4-20
630 620 620.1 610
~
t-<
...... 600
~
~
..:c:
~
V!. T HOT
~
~
0
~ 580
~
Ci T AVG
~ 570
~
t-<
~~
p., T COLD 558.3
~
t-< 550 540 530 0 20 40 60 80 100 PERCENT POWER COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT I REACTOR COOLANT SYSTEM Amendment 102 TEMPERATURE PERCENT POWER MAP FIGURE 4.4-2IA fsOOOOIO.d n
620 618.8 610 600
~
t-<
~
..:c:
~ 580 V!.
~
T AVG
~
0
~ 570 Ci
~ 559.6
~ T COLD t-< 560
~~
p.,
~
t-< 550 540 530 0 20 40 60 80 100 PERCENT POWER COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT2 REACTOR COOLANT SYSTEM Amendment 102 TEMPERATURE PERCENT POWER MAP FIGURE 4.4-2IB fsOOOOOz.dgn
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&. VDIT PIPE FIIIIISIEII 11TH REACTOR VESSEL l£AD.
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""" e SI AC~
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I 1-TE*ll!iOA*I 1-TE*llSOA-2 I 1-TE*31SOA*3 1-TE*'650A-.4 I 1*1[*"508-1 1*1[*'8508-2 I l*TE*3MOl-3 l*TE*JeOC*l 1*1E*3MOl-4 1-1E*3MOC*Z I l*TE*JHOD-1 1-TE*JHOD-2 I l*TE*JHOD-3 l*TE*JHOD-4 I 1-TE*l&!IOF*I 1*1E*S!IOF*2 D I l*TE*l&!IOF*l 1-TE*S!IOF*4 L___ -----~ l*TE*lHOG-1 l*TE*ll!OG-2 1-TE*lHOG-l 1-TE*ll!OG-4
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TI-RC*l-tlM*2SOll*2 1-RC-1-IOS*ZSOR-S 10
]2.l*LT*l&IM*U.*2.B-Ul*2.C*IAIGC*2 ME IIGTALLED FOR PERIIDC RCS LEVEL YIIIITORIIG,IIOOT VALVES ARE IOIUALLT Q.DSED.
FOi iN. ll&RVICE UIIE-1.1' SEE APPLICABLE !PO.VALVE IIC-8118l 0:: IS 10 E CAPPED CFF IHENRCSLEYEL YIIIITORIIGSTSTEU <t IS 11)1 IN SERVICE. Vl U. THE FOLLOIIIG TElll'ERATIIIE ELEIIIDITS ME AIWIIOIIEO IN PLACEI LL 1*1E*04DA*I l*TE*ll17A*IO 1-1E*l61l8*n 1*1E*04DA*2 l*TE*l617A*n 1-1E*l61l8*12 1-1E*04DA*l l*TE*ll17A*12 1-TE*llllB*D 1*1E*04Zll*I l*TE*ll17A*D 1-TE*llllB* 1*1E*04Zll*Z l*TE*ll17A*M 1*1E*04Zll*l l*TE*5617A** REFERDICEMOTESI 111S Flot IJIMIRAII HQ EEM REDRUNFAOII IESTINGIICIUSE DRAIING IUIER11llER'5HICFZ,IEYlll1HEICEP710lil5ASFCILLOIISI
br,COllTROL LOOPS HlYE EDI IELETED EXCEPT Fat THE PRIIIMRY NG FINAL ELEIIIDITS. THEIETAILSCF THECONTROLLOCPSIILLESHDlll ONlll!ITIUBITATIONAtGCOllTROL IUGRAM. CLASS I
...,. ..... ma HI I CIU:LEAR SAFETY-RELATEOI
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... ...,. FLOW DIAGRAM REACTOR COOLANT SYSTEM
~ NOTEID
......... CP-36 mel041TO.dgl'I A t.41-0250 B C D E G FINAL IPRINT
CPE A B C D E F G H SAMPLE VESSEL FROM REV DWN CHKDAPVD REMARKS PROCESS SAMPLING SYSTEM
-151R-5 JRMC DJL TC TC IRC ORC CP-34 11-10 11-10 THIS DRAWING REVISED TO INCORPORATE DESIGN CHANGE TV 1-RC-1-136-152R-3 2014 2014 FDA-2008-001958-02-04 PER SK-0039-08-001958-02-00.
NOTE 17 NOTE 17 1/1-1/1- 5
-RC-1-148-2501R-5 8027 5
-151R-5 3 1RC-0004 12-RC-1-115-601R-5 8026 3 LC 5 1RC-0026 1RC-0027 5 2 2 3 1RC-0006 1RC-0005 2 -151R-3 3 5
-151R-5 -151R-2 -151R-3 4-601R-5 FC WPS (G) GDT 6 - RC 10 1- 6 0 1R- 5 1-RC-1-117-151R-2 FC -151R-3 M1-0269-01 6 - RC 0 9 7 - 6 0 1R- 5 6 - RC 0 9 9 - 6 0 1R- 5 1- RC 116 - 15 1R- 5 - RC 12 0 - 15 1R- 3 1-8026 1-8027 1RC-8028 LOC: G-6 151 152 1-RC-1-118-151R-3 1RC-8093 1-GH-X-166-152R-5
- 15 1R- 3 1RC-8036 2-601R-5 PENETRATION 1-RC-1-119-151R-3 1 MV-0008 " 1 6 0 1R- 5 1RC-8153 1RC-8033 1RC-8035 NOTES:
-2501R-5 NITROGEN SUPPLY NOTE 7 FC M1-0243-A 1-8034 1. PRESSURIZER SPRAY LINES FROM REACTOR COOLANT LOOPS TO LOC: C-4 15 1R- 5 1-TE- 1-TE- 1-TE- 1RC-0036 PRESSURIZER ARE RUN USING LONG RADIUS BENDS TO COMPLY WITH NOTE 19 RC NG 0466 0465 0464 SEE NOTE 11 MAXIMUM ALLOWABLE PRESSURE DROP PER WESTINGHOUSE DOCUMENT 1-151R-5 -NG-1-010-151-5 PFD-PD-285-4.
2 5 3 5 NOTE 3 5 1 NOTE 3 5 1 NOTE 3 5 1 NOTE 11 TO CONTAMINATED IMB IMB IMB 2. SPRAY PIPE SLOPED TO PROVIDE WATER SEAL BETWEEN PRESSURIZER AND DRAINS SYSTEM NOTE 9 SPRAY VALVES.
-151R-5 1-8010A 1-8010B 1-8010C 1/1- 3. STRAP ON (SURFACE MOUNTED) RTDS LOCATED AT BOTTOM OF PIPE.
TC TC 5 8047 TV 1/1-NOTE 3 WATER SEAL 2 4. PIPE SLOPED DOWNWARD TO PROVIDE WATER SEAL BETWEEN PRESSURIZER 8045 LC 2 5 3-DD-1-031-151-5 AND MOTOR OPERATED VALVES. ARRANGEMENT 5 2 1RC-0001 1-TE- 1RC-0003 1RC-0002 -RC-1-932-151R-2 -151-5 1-TE- 1-TE- DEMINERALIZED & 6 - RC 9 3 4 - 15 1R- 5 0466A 5. LOCATED APPROXIMATELY MIDWAY BETWEEN LOOP AND PRESSURIZER. 0465A 0464A 3-RC-1-122-151R-5 FC -151R-5 -151R-2 FC 3-RC-1-127-151-5 REACTOR MAKE-V NOTE 3 5 2 SEE NOTE 11 UP WTR SYSTEM 6. SPARGER AND SPRAY HEADER SUPPLIED WITH PRESSURIZER RELIEF TANK. NOT E 2 6 NOTE 3 2 1-8045 1-8047 M1-0242 VENT HOLE PROVIDED IN SPARGER LINE.
-RC-1-102-2501R-2 -RC-1-104-2501R-2 1-8046 RC DD 3-WP-1-022-151R-5 LOC: F-2 2 2 RC WP 3-C72
1RC-8064C 1RC-8048 1RC- 8 15 6 1RC- 8 15 5 3-RC-1-121-151R-2 WPS (L) RCDT MK 8. DELETED 2 1RC-8064A 1RC-8064B 2 -RC-1-107-2501R-5 M1-0264
- 15 1R- 5 5 5 LOC: F-3 9. DRAIN LINES SLOPED DOWN FROM LOOP SEALS TO CONNECT WITH PRT
-151R-5 PENETRATION
-RC-1-106-2501R-2 1RC-8025 HEADER LINE.
-RC-1-103-2501R-5 -RC-1-105-2501R-5 1RC-0020 MIII-0001 RUPTURE DISC 10. INCH I.D. FLOW RESTRICTOR WITH PIPING FOR CLASS-1 AND CLASS-2 1-PT-D 0469 TRANSITION AT PRESSURIZER LIQUID SPACE LEVEL INSTRUMENT AND SAMPLE 2-151R-5 NOZZLES AND OTHER LOCATIONS AS SHOWN SIMILAR TO ARRANGEMENT SHOWN ON MECHANICAL SYMBOLS AND NOTES DRAWING NO. M1-0200, NOTE 15.
- RC 12 6 - 15 1R- 5 - RC 12 5 - 15 1R- 5 2 2 1RC-8049A 11. TYGON HOSE TO BE INSTALLED AT THESE CONNECTIONS TO VENT 2-151R-5 PRESSURIZER DURING DRAINING AND FILLING.
1-LT-NOTE 6 1RC-0024 0470 2-151R-5 NOTE 20 12. LOCATED CLOSE TO PRESSURIZER SPRAY VALVES IN ITS WATER SEAL. 1-TE-0468 13. DIGITAL PRESSURIZER INDICATOR LOCATED ON THIS LINE DOWNSTREAM 1RC-8049B OF SAMPLE HEAT EXCHANGER.
-151R-5 NOTE 3 PRESSURIZER RELIEF TANK 2-151R-5 -151R-5 6 - RC 0 9 8 - 2 5 0 1R- 1 1-TE- D 14. DELETED 1RC-0015 TBX-RCATPR-01 1RC-0025 0463 4-RC-1-128-151R-5 15. INDICATES HERMETICALLY SEALED VALVE.
FC D 6-RC-1-096-2501R-1 6-RC-1-100-2501R-1 RC 1/1-1-8031 -RC-1-124-151R-5 16. SEE REFERENCE "G" ON MECHANICAL SYMBOLS AND NOTES DRAWING NO. 8031 WPS (L) RCDT M1-0200. PUMPS -CS-1-176-151R-5 WP M1-0264 RC CVCS RCP 1 17. ALL QUICK CONNECT COUPLINGS SHALL BE SWAGELOK SS-QC4-S-400 AND RH 4-WP-1-027-151R-5 LOC: C-5 SEAL STANDPIPE SS-QC4-3-400 FURNISHED WITH SAMPLE VESSEL. M1-0253 6x4 5 2 LOOP 1 18. NITROGEN SUPPLY REQUIRED FOR COLD OVERPRESSURE PROTECTION. 6-RC-1-935-151R-5 LOC: A-5
4-RH-1-913-601R-2 (TRAIN A) -CS-1-178-151R-5 M1-0260 D CVCS RCP 2 1RC-0022 20. FLANGES USED IN THE INSTRUMENT CONNECTIONS FOR 1-LT-0470 ARE RATED 1-RC-1-943-151R-5 LOC: F-2 SEAL STANDPIPE AT 150 LBS. M1-0253 CP1-RCSTDR-03 LOOP 2 21. DELETED LOC: D-5 -RC-1-125-151R-5 STEM LEAKOFF 22. TEMPERATURE ELEMENT IS STRAP-ON RTD. T M1-0264 3 LOC: E-3
-CS-1-182-151R-5 -RC-1-123-151R-5
3 RC CS CVCS RCP 4
12 - RC 115 - 6 0 1R- 5 5 2 SEAL STANDPIPE M1-0253 STEM LEAKOFF 3-RC-1-130-151R-5 25. THE STRAP ON RTDS IDENTIFIED ON THE FOLLOWING TABLE ARE USED TO LOOP 4 M1-0264 1-8121 MONITOR THERMAL CYCLING AND STRATIFICATION IN THEIR RESPECTIVE LOC: A-1 LOC: E-3 CVCS SEAL PIPING LEGS. AS NOTED ON THE TABLE, THE RTDS ARE MOUNTED ON EITHER 2-CS-1-428-151R-2 RETURN THE TOP OR BOTTOM OF THE PIPE. M1-0253 -CS-1-180-151R-5 RC CS LOC: A-3 NOTE 3 TOP BOTTOM R PROCESS CVCS RCP 3 NOTE 3 SEAL STANDPIPE -RC-1-126-151R-5 1/1- SAMPLING SYSTEM 6x3 M1-0228 5 2 M1-0253 8000A 1-TE-3650E-3 1-TE-3650E-4 1-TE- LOC: A-2 6-RC-1-933-151R-5 LOOP 3 1-PCV- 1-8117 0495 LOC: D-1 CS RC 1-TE- -PS-1-001-2501R-2 0455A NOTE 27 STRAP ON RTD 1-TE-3650E-5 IS ALSO USED TO MONITOR THERMAL 0495A CVCS LETDOWN 2 2-CS-1-546-601R-2 CYCLING AND STRATIFICATION BUT IS LOCATED IN A VERTICAL RISER, SO 5 1 M1-0253-A 1-TE- BEING LOCATED ON TOP OR BOTTOM OF PIPE IS NOT PERTINENT. PS 0125 LOC: G-1 RCDT RCDT M -RC-1-931-2501R-2 26. TO FACILITATE PIPE SUPPORT DESIGN, PIPE IS UPGRADED TO SCHEDULE 160S. 1RC- 8 0 7 8 RC FC NOTE 18 T 27. TO FACILITATE PIPE SUPPORT DESIGN, PIPE IS UPGRADED TO SCHEDULE 80S. 1-RC-1-901-2501R-2 1-RC-1-942-151R-5 1-PCV-0455A 1-8000A 28. HANDWHEELS FOR VALVES 1RC-8053A , 1RC-8053B AND 1RC-8053C HAVE CP1-RCSTDR-02 3 - RC 111- 2 5 0 1R- 1 RC RH BEEN REMOVED DUE TO INTERFERENCES. A TEMPORARY VALVE 1-HV- 1-HV- 1-TE-1-RC-1-942-151R-5 WRENCH WILL BE USED WHEN NECESSARY. 3-RC-1-112-2501R-5 3609 3610 3606 6x4 5 2 29. THE STRAP-ON RTDS IDENTIFIED IN THE FOLLOWING TABLE HAVE 3-RC-1-111-2501R-1 NOTE
- RC 10 9 - 2 5 0 1R- 2 LO 2 5 6-RC-1-936-151R-5 BEEN ABANDONED IN PLACE. R 3-RC-1-110-2501R-5 22 1-8708B 1RC-8095
FC FC 1-TE-3618A-2 1-TE-3618A-7 1-TE-3618A-12 1-TE-3650E-2 1/1- M1-0260 4 -2501R-2 1-RC-1-902-2501R-5 4 F S AR F IGURE 5 . 1- 1 1-PCV- LOC: F-4 1-TE-3618A-3 1-TE-3618A-8 1-TE-3618A-13 1-TE-3650E-5 8000B 2 1RC-8098 1-RC-1-941-151R-5 0456
-2501R-5 RCDT RCDT M TV 1 1-RC-1-941-151R-5 VENTS AND
CONTAINMENT BLDG 1-PCV-0456 1-8000B M1-0238 OMB IMB IMB OMB NOTE 1 1-ZT-3618B-1 1-ZT-3618B-2 1-ZT-3618B-3 NOTE 4 LOC: C-5 NOTE 3 1RC- 1RC- 4-RC-1-091-2501R-1 NOTE 18 -2505-2 0038 0037 1-TE- 1-TE-1-TE- 1-TE-NOTE 3 V 3650E-4 3650E-3 0496A 1-TE- 3650E-5 2-CS-1-112-2501R-1 1-TE- 1RC- 0454 1RC- 1RC- NOTE 25 NOTE 25 REFERENCES NOTE: 0496 8124 2 -2505-2 0042 0043 NOTE 29 2 CVCS AUX SPRAY 1RC- 2-RC-1-132-2501R-1 THIS FLOW DIAGRAM HAS BEEN REDRAWN FROM WESTINGHOUSE DRAWING NOT E 16 2 V M1-0253-A 1-LT-3615C NOTE 24 8053A R NOTE 10 NO. 1138E92 SH 2 OF 2 REV 6 WITH EXCEPTIONS AS FOLLOWS: LOC: A-6 M1-0250 NOT E 16 1 LOC: C-3 NOTE -2501R-2 2 5 STEM LEAKOFF "SS TUBING R 2 a. VALVE AND LINE NUMBERS HAVE BEEN ADDED. M1-0264 28 NOTE 24 1RC-8053C NOTE 23 D b. CONTROL LOOPS HAVE BEEN DELETED EXCEPT FOR THE PRIMARY 4 - RC 0 8 8 - 2 5 0 1R- 1 LOC: D-3 CP1-RCCNPR-01 NOTE 28 1RC-0023 AND THE FINAL ELEMENTS. THE DETAILS OF THE CONTROL LOOPS
-2501R-2 -RC-1-143-2501R-2 -RC-1-133-2501R-2 WILL BE SHOWN ON INSTRUMENTATION AND CONTROL DIAGRAM.
1RC- 1RC- NOTE 23 CP1-RCCNPR-03 T HIS DRAWING CREAT ED ELECT RONICALLY 0040 0039 -2505-2 IMB STEM LEAKOFF V 2 M1-0264 1-PT- 1-PT- 1RC- 1-PT- 1RC-8052 2 NOT E 16 LOC: E-3 0455F 0455 8053B 0457 NOTE 24 NOTE 28 R NOTE 12 NOTE 10 5 CP1-RCCNPR-02 1-LT- NOTE 29 NOTE 29 1-TE- 5 0462 0452 1-LT- -2501R-2 1-TE- 1-TE-NOTE 1 4-RC-1-075-2501R-1 0459F NOTE 23 3650E-1 3650E-2 RCDT IMB RCS LOOP 4 1-PT- 1-PT- M1-0250 0458 0456 1-PCV-0455C LOC: B-4 2 1 STEM LEAKOFF FC 1RC-8054B 1 M1-0264 1-LT- -2505R-2 LOC: D-3 6-RC-1-161-2501R-1
-RC-1-909-2501R-1 4-RC-1-162-2501R-1 0460 NOTE 10
-RC-1-908-2501R-1 2 1 NOTE 10 1 2 REF CKD CP - 2 1 12 / 19 / 9 6 4 - RC 0 8 7 - 2 5 0 1R- 1 NOTE 10 1RC-8054A -RC-1-144-2501R-2 1-LT- -2505R-2 -2505R-2 1-LT-0459 0461 IMB 1RC-8054C
-RC-1-907-2501R-1 NOTE 10 IMB OMB 1RC-8051 2 HEATER
-RC-1-134-2501R-2 CONTROL 1-TE- 1-TW- NOTE 12
-RC-1-900-2501R-1 NOTE 10 0453 0453 1-TE-1 PRESSURIZER 0451 NOTE 1 4-RC-1-018-2501R-1 CLASS 2 RCDT IRC ORC (NUCLEAR SAFETY-RELATED)
OMB IMB TBX-RCPCPR-01 SAFETY CLASS 1 SEISMIC CATEGORY IMB RCS LOOP 1 SAFETY CLASS 2 CLASS 1E M1-0250 SAFETY CLASS 3 ASSOCIATED CIRCUITS 1-PCV-0455B LOC: E-4
-RC-1-095-2501R-2 NOTE 10 STEM LEAKOFF M1-0264 FC 1 LUMINANT 6 NOTE 1 6-RC-1-163-2501R-1 6 1-TE-0450 LOC: D-3 4-RC-1-164-2501R-1 CPNPP 1RC- 8 0 8 0 NOTE 30 NOTE 13 RC GLEN ROSE, TEXAS NOTE 5 PROCESS PS SAMPLING NOTE 29 14-RC-1-135-2501R-1 RCS LOOP 4 SYSTEM M1-0250 M1-0228 PRESSURIZER SURGE LINE LOC: B-5 FLOW DIAGRAM LOC: A-1 2 1 REACTOR COOLANT SYSTEM
-PS-1-002-2501R-2 DWG. NO. SH. NO. REV.
M1-0251 - CP-34 me776200.dgn A M1-0251 B C D E F G FINAL PRINT H
CPE A B C D E F G H REV DWN CHKDAPVD REMARKS
-WP-2-253-2505R-5 WPS (L) RCDT M2-0264 STEAM GENERATOR CP-19 GAW RG 12-10 12-10 THIS DRAWING REVISED TO INCORPORATE FDA-2018-000097-01-00 PER LOC: A-2 TCX-RCPCSG-02 2018 2018 SK-0003-18-000097-01-00.
RC SI 2-8949B SIS SI AND 2-FT-STEAM GENERATOR RHR PUMPS 0426 M2-0263 TCX-RCPCSG-03 LOC: G-1 2-FT-0425 6 - RC 0 2 9 - 2 5 0 1R- 1 2-FT-2-FT- NOTE 5 OMB 0424 0436 IMB 1 1 2 RC- 8 0 5 9 B 2 RC- 8 0 6 0 B 2 RC- 8 0 6 1B 2-FT-0435 1" PLUG 2-TE- 2-TE- NOTES: NOTES
- 2 5 0 1R- 2 - 2 5 0 1R- 2 - 2 5 0 1R- 2 2-FT- 0423F 0423A NOTE 5 0434 OMB 1. 29" INSIDE DIAMETER. (BY WESTINGHOUSE)
IMB 2 2. 31" INSIDE DIAMETER.(BY WESTINGHOUSE) 2 RC- 8 0 6 1C 2 RC- 8 0 6 0 C 2 RC- 8 0 5 9 C NOTE 8 NOTE 13 1 3. 27.5" INSIDE DIAMETER. (BY WESTINGHOUSE) 2-TE- 2-TE- 4. SPRAY LINE SCOOP. 1" PLUG
- 2 5 0 1R- 2 - 2 5 0 1R- 2 - 2 5 0 1R- 2 0433A 0433F NOTE 11 1 5. ELBOW FLOW METERS INSTALLATION-SEE REF. G ON DRAWING 1" PLUG 2 M1-0200.
2 WP 1/2-1 8032 6. VENT PIPE FURNISHED WITH REACTOR VESSEL HEAD. 5 RC OMB 7. HEAD GASKET MONITORING CONNECTIONS FURNISHED WITH 2 2-8032 SI 2-TE- 2-TE- REACTOR VESSEL. RC IMB 6 - RC 0 4 6 - 2 5 0 1R- 1 1 FO 3650B-2 3650B-1 NOTE 11 NOTE 8 8. RTD INSTALLED IN WELL. 2 OMB IMB NOTE 13 SIS
-RC-2-082-2505R-2 3 1- RC 0 2 4 - WES T - 1 M2-0261 9. CONNECTION LOCATED IN BOTTOM HALF OF REACTOR COOLANT PIPING TELL TALE LOC: G-4 2SI-8900B 2RC-8062B ON 45 ANGLE TO VERTICAL.
- RC 0 3 9 - 2 5 0 1R- 1 NOT E 2 1" PLUG -2501R-5 2RC-8062C -2501R-2 -2501R-2 10. LOOP INDENTIFICATION AS SHOWN.
2-JE- 2-JE- RC SI
-2501R-2 0420D SIS 11. " I.D. FLOW RESTRICTOR PROVIDED. (SEE MECHANICAL SYMBOLS AND SI RC 0430D ACCUMULATOR SI NOTES DRAWING M1-0200, NOTE 15).
2RC-8076 1/2-
- RC 0 8 1- 2 5 0 1R- 2 SIS SI AND NOTE 21 NOTE 21 AND RHR PUMPS 10 - RC 0 3 7 - 2 5 0 1R- 1 2-JE- 2-JE- PCPX2 12. STRAP-ON (SURFACE MOUNTED) RTD LOCATED AT BOTTOM OF PIPE.
RHR PUMPS M2-0263-B 0430C 0420C 2-8948B M2-0263 LOC: G-3 13. 31" IDX29" REDUCING ELBOW. (BY WESTINGHOUSE) 2-8949C NOTE 11 1 5 2 LOC: G-2 2 14. A FLOW RESTRICTING SCOOP WITH A BORE OF 0.234" WILL BE REACTOR RC SUPPLIED BY VENDOR WITH THE LOOP 1 AND LOOP 4 HOT LEGS. WP
" PLUG COOLANT PUMP 1
2-TE-2 2-TE- 2-TE- 2-TE-2-WP-2-033-2501R-5 15. FOR MECHANICAL SYMBOLS AND NOTES SEE DRAWING M1-0200. 2 SI RC 0421B 0420F 0420B 0423B TCX-RCPCPC-02 2-TE- 2-TE- 1 5 16. DELETED SIS 3650C-1 3650C-2 2-RC-2-035-2501R-1 WPS (L) RCDT
" PLUG 17. TYGON HOSE TO BE INSTALLED AT THIS CONNECTION FOR DRAINING M2-0261 12 M2-0264 LOC: G-5 3x1 2RC-8058B LOC: A-5 BOTTOM OF CHANNEL HEAD TO CONTAINMENT SUMP AFTER REACTOR 2SI-8900C IMB COOLANT SYSTEM HAS BEEN DRAINED BELOW STEAM GENERATOR SI RC 2-JE- 2-JE-SIS 0430B 0420B 2RC-8057B NOZZLES.
NOTE 8 ACCUMULATOR SI 2RC-8069A 2RC-8069B IMB 18. DELETED AND RHR PUMPS NOTE 21 NOTE 21 M2-0263-B 2-JE- 2-JE- 19. DELETED 2-8948C 0430A OMB 0420A 3 1- RC 0 4 1- WES T - 1 10 - RC 0 5 5 - 2 5 0 1R- 1
- RC 0 5 7 - 2 5 0 1R- 1 LOC: G-5 20. LOCATE CONNECTION OF UPPER 90 OF PIPE CIRCUMFERENCE.
IMB
- RC 0 8 0 - 2 5 0 1R- 2 - RC 0 8 1- 2 5 0 1R- 2 PRESSURIZER RM 2 RC- 8 12 4 29-RC-2-040-WEST-1 V 22. DELETED EL 905 1/2- NOTE 1 23. USE OF THE NORMAL CHARGING LINE AND ALTERNATE CHARGING PCPX3 NOT E 2 29-RC-2-023-WEST-1 -2505R-5 PRZR 2RC-0038 LINE SHOULD BE ALTERNATED OVER THE PLANT LIFE SUCH THAT 2RC-8150 SPOOL LEVEL NOTE 1 VENTILATION PIECE TREE NEITHER PATH WILL BE EXPOSED TO MORE THAN 60% OF THE DESIGN CONTAINMENT NITROGEN 2RC-0037 SUPPLY CRDM 2RC-8120 2RC-8121 2RC-8145 TRANSIENTS INVOLVING COMPLETE STOPPAGE OF LETDOWN AND/OR M2-0300-A REACTOR 1 LOC: F-2 2RC-8149 2RC-8152 EL 905 VENT CHARGING FLOW. TRANSFER FROM ONE PATH TO THE OTHER SHOULD BE NOTE 7 COOLANT PUMP 2 1 2RC-8151 PERFORMED ONLY AT COLD SHUTDOWN CONDITIONS TO AVOID SUB-2-TE- 2-TE- 2-TE- 2-TE- 2RC-8146 V TCX-RCPCPC-03 V 2 RC- 8 13 8 0433B 0430B 0430F 0431B JECTING THE CHARGING LINES TO UNNECESSARY THERMAL TRANSIENTS.
SPOOL V 2RC-8140 REACTOR VESSLE 2RC-8142 PIECE H NR 24. DELETED VENT EL 860
" PLUG LOOP 3 1x 1x LOOP 2 CRDM 2RC-8122 2RC-8123 25. THESE CONNECTIONS MADE AT BMI (BOTTOM MOUNTED INSTRUMENTATION) 2-LT-3x1 VENT V 2-LT-NOTE 11 27.5-RC-2-042-WEST-1 3615A 2RC- THIMBLE TUBES NUMBERS 46 AND 55 WHICH CORRESPONDS TO CORE NOTE 3 V 2RC-8147 3619A-1 THIMBLE GUIDE 8139 LOCATIONS J-1 AND N-14 RESPECTIVELY.
V TUBES WR 2RC-8141 H L NOTE 29 PRESSURIZER H 3 NOTE 8 LEVEL 2-PT-V 2-LT- 26. THE STRAP-ON RTDS IDENTIFIED ON THE FOLLOWING TABLE ARE 3 3616 2RC- 2-LT- 3619A-2 M2-0251 USED TO MONITOR THERMAL CYCLING AND STRATIFICATION IN THEIR 8129 3615B LOC: A-5 2RC- 2RC- 2RC-8143 RESPECTIVE PIPING LEGS. AS NOTED ON THE TABLE THE RTDS 2RC- 8105 2RC-8132 27.5-RC-2-025-WEST-1 8104 H L ARE MOUNTED ON EITHER THE TOP OR BOTTOM OF THE PIPE. 2 NOTE 3 8128 WP RC 2RC-8148 TOP BOTTOM 2RC-8137
" S S T UBING 2-RC-2-053-2501R-1 3-RC-2-052-2501R-1 V 2 RC- 8 12 6 5 1 2RC- 2RC- 2-TE-3650A-1 2-TE-3650A-2 2RC-8121 2RC-8120 8127 8110 2RC- EWR IMB H WPS (L) RCDT IMB LEAKOFF TO ATMOSPHERE 2RC-M2-0264 8109 8107 D 2-TE-3650B-1 2-TE-3650B-2 M2-0264 R 2-LT-LOC: A-5 2RC-8057C LP 2RC-8058C LOC:C-2 2RC- D 3615C 8104 1" SWAGELOK PLUG 2RC- 2-TE-3650C-1 2-TE-3650C-2 2-LT- 2RC- 2RC-8144 H L 2RC- 0035 2RC- 2-TE-3650D-1 2-TE-3650D-2 2RC- NOTE 27 3619B-1 8106 2RC-8136 CVCS LETDOWN 2-LT- 8106 TC 8108 LO 8107 NOTE 29 M2-0253 3615A HP 2 1 NOTE 25 1-2501R-1 2-TE-3650F-1 2-TE-3650F-2 LOC: A-3 2-TE- 2-LT-2-8085 2RC-0035 3619B-2 2RC-8133 3650F-1 2 CS RC N-5 CODE STAMPING NOTE 11 12 D D D D NOTE 23 NOT REQUIRED REACTOR NOTE 6 2RC-0046 2RC-0045 2RC-8134 2RC-8135 CVCS CW NORMAL -2505-2 ASME VESSEL 2-LT- HP 27. USE " SS TUBING FOR CONNECTION TO CONTROL ROD DRIVE M2-0255 2RC-0034 LO LOC: G-3 3615C NOTE 11 TCX-RCPCRV-01 MECHANISM. CONTROL ROD DRIVE MECHANISM INSERT INCLUDES FLOW 2-8378A " SS TUBING 1-RC-2-902-2501R-1 2-TE- 2RC- 2-HV- 2-HV- 2-TE- RESTRICTOR TO SERVE AS TRANSITION FROM SAFETY CLASS 1 TO 2.
3650F-2 TO ATMOSPHERE 3607 3608 3605 8109 RCS PR SPRAY 28. DELETED M2-0251 2-LT- 2 1 NOTE 25 NOTE 12 LOC: E-5 3615B NOTE 27 29. 2-LT-3619A-1,A-2,B-1,B-2,C-1 AND C-2 ARE INSTALLED FOR PERIODIC HP 2RC-8105 2 S S RCS LEVEL MONITORING. ROOT VALVES ARE NORMALLY CLOSED. 2RC-8108 1-RC-2-903-2501R-2 1-RC-2-904-2501R-5 3 - RC 0 7 6 - 2 5 0 1R- 1 TO ATMOSPHERE 4 - RC 0 7 5 - 2 5 0 1R- 1 1/2- LP 2-PT- FOR ONE INSERVICE LINE-UP SEE APPLICABLE IPO. VALVE 2RC-8083 2RC-8110 4 3616 FC FC 4 F S AR F IGURE 5 . 1- 1 PCPX4 IS TO BE CAPPED OFF WHEN THE RCS LEVEL MONITORING SYSTEM 2 RC CS 2 5 QUICK DISCONNECT 2-TE- IS NOT IN SERVICE. NOTE 23 CVCS CHG ALT 3650G-3 M2-0255 REACTOR NOTE 11 2RC-8123 2RC-8122 LOC: G-3 2-8379A COOLANT PUMP 2-TE- 2-TE-
"PLUG 3-RC-2-019-2501R-1 REFERENCE NOTES:
2-TE- 2-TE- 1/2-TCX-RCPCPC-04 0443B 0440B 0440F 0441B PCPX1 12 2-TE- THIS FLOW DIAGRAM HAS BEEN REDRAWN FROM WESTINGHOUSE DRAWING RCS PR SPRAY 3650G-4 M2-0251 NUMBER 1138E92 SH 1 OF 2 REV 6 WITH EXCEPTIONS AS FOLLOWS: LOC: E-6 4 - RC 0 18 - 2 5 0 1R- 1
27.5-RC-2-060-WEST-1 NOTE 3 REACTOR b. CONTROL LOOPS HAVE BEEN DELETED EXCEPT FOR THE PRIMARY LOOP 4 LOOP 1 " PLUG 6-RC-2-163-2501R-1 COOLANT PUMP NOTE 4 AND THE FINAL ELEMENTS. 3x1 NOTE 8 SI RC 2-TE- 2-TE- 2-TE- 2-TE-TCX-RCPCPC-01 THE DETAILS OF THE CONTROL LOOPS WILL BE SHOWN SIS 2-TE- 0411B 0410F 0410B 0413B 2 1 ON INSTRUMENTATION AND CONTROL DIAGRAM. ACCUMULATOR SI 10-RC-2-078-2501R-1 3617B-14 AND RHR PUMPS 27.5-RC-2-003-WEST-1 M2-0263-B NOTE 11 1 NOTE 3 2-RC-2-072-2501R-1 2-8948D LOC: G-6 "PLUG 2 2-TE- 2-TE- 2-TE- NOTE 1 2RC-8057D 3650D-1 3650D-2 5 1 SI RC 3617B-13 3x1 NOTE 11 NOTE 4 NOTE 8 WPS (L) RCDT 2RC-8058D SIS 2SI-8900D 1 -RC-2-079-2501R-1 29-RC-2-058-WEST-1 "PLUG RC SI T HIS DRAWING CREAT ED ELECT RONICALLY M2-0264 M2-0261 SIS LOC: G-5 2-TE- 2-TE- 2-TE- 12 LOC: A-6 OMB IMB 10-RC-2-021-2501R-1 ACCUMULATOR SI
-RC-2-073-2501R-2 3617B-10 3617B-11 3617B-12 2 RC- 8 0 8 3 AND RHR PUMPS WP RC NOTE 11 2 -RH-2-065-2501R-2 2 M2-0263-B 2-RC-2-015-2501R-1 2-TE- 2-TE- 2-8948A 1 2 RHRS PUMP 2 1 2-TE- LOC: G-2 5 NC M 3617A-10 2RC-8057A 2-WP-2-034-2501R-5 TRAIN B 3650A-2 3650A-1 RC SI IMB OMB 1 5
-2501R-5 M2-0260 2-8702B 2 RC- 8 0 8 2 LOC: G-5 RH RC 2-TE- 1 -RC-2-020-2501R-1 SIS WPS (L) RCDT 5 x -2501R-2 3617A-11 M2-0261 LO M2-0264 5 2-LT- 2-LT- LOC: G-4 2RC-8058A LOC: A-6 2-PT- 2SI-8900A 3619C-2 3619C-1 IMB OMB SIS SI PUMPS 3 1- RC 0 0 2 - WES T - 1 2-8949D 0403 2-JE- 2-JE- 2-TE- 2-TE- RC CS RC WP M2-0263 2RC-8071B 2-TE-NOTE 29 0440A 0410A 3617A-12 3617A-13 3617A-14 LOC: G-3 NOTE 11 CVCS EX 1
STEAM GENERATOR SI RC NOTE 21 NOTE 21 -RH-2-066-2501R-1 LETDOWN 2 2 2-JE- 12 2-PI- 2-JE- M2-0253 TCX-RCPCSG-04 6-RC-2-070-2501R-1 1 0402 0440B 0410B RC RH 2-8154 LOC: A-5 NOTE 11 M NC RHRS PUMP 1 RCS PRESSURE 1-RC-2-016-2501R-1 NOT E 2 2-FT- " PLUG -2505-2 TRAIN A SURGE MAXIMUM 0446 M2-0260 M2-0251 PRESSURE 2-8702A LOC: G-3 LOC: D-6 STEAM GENERATOR 3 1- RC 0 5 9 - WES T - 1 2-FT- "x " GUAGE 14 - RC 13 5 - 2 5 0 1R- 1 12 - RC 0 6 9 - 2 5 0 1R- 1 0445 PROCESS PIPE TO TUBE ADAPTOR 2-PI- 2-PT- TCX-RCPCSG-01 SAMPLING 0404 0437 2-FT- " TUBING NOTE 11 NOTE 5 SYSTEM MAXIMUM 0444 OMB 2-JE- -2501R-2 IMB OMB
- RC 0 7 1- 2 5 0 1R- 2 M2-0228 2RC-8077 2-JE- PRESSURE 0440C 0410C 2-FT-2 RC- 8 0 6 0 D LOC: A-2 2 RC- 8 0 6 1D 2 RC- 8 0 5 9 D IMB GAUGE 2-PT-NOT E 2 0416 REF CKD CP - 12 0 5 / 11/ 9 8 PS RC NOTE 21 NOTE 21 0405 2-JE- 2-JE- 2 2RC-8071A -2505-2 2-FT-0440D 0410D 1
- 2 5 0 1R- 2 - 2 5 0 1R- 2 - 2 5 0 1R- 2 2-TE- 2-TE- 1" PLUG IMB OMB 0415 12 - RC 0 0 7 - 2 5 0 1R- 1 0443A 0443F 12 6-RC-2-008-2501R-1 SIS SI PUMPS 2-FT-2 NOTE 13 NOTE 8 NOTE 11 2-8949A M2-0263 LOC: G-2 OMB NOTE 5 0414 CLASS 1 (NUCLEAR SAFETY-RELATED) 2 RC- 8 0 6 1A IMB 2 RC- 8 0 5 9 A 2 RC- 8 0 6 0 A 1 SAFETY CLASS 1 SEISMIC CATEGORY 2 SAFETY CLASS 2 CLASS 1E RC SI SAFETY CLASS 3 ASSOCIATED CIRCUITS 1 2-TE- 2-TE-
- 2 5 0 1R- 2 - 2 5 0 1R- 2 - 2 5 0 1R- 2 NOTE 11 NOTE 14 NOTE 9 2 " PLUG 0413F 0413A OMB -2501R-2 UNIT 2 UNIT 1 1" PLUG NOTE 13 LUMINANT 6 2 6 IMB 1" PLUG NOTE 8 1
CPNPP 2RC-8062D 2 3 3 2 SFP 29-RC-2-001-WEST-1 GLEN ROSE, TEXAS NOTE 11 1 1 4 4 1 NOTE 9 NOTE 14 " TUBING 2 1" PLUG RC PS P P -2501R-2 OMB RHR RHR 1 FLOW DIAGRAM 2 IMB AUXILIARY PROCESS REACTOR COOLANT SYSTEM BLDG SAMPLING 2RC-8062A SYSTEM RHR RHR -RC-2-013-2501R-2 2RC-8056 M2-0228 NOTE 10 LOC: A-2 DWG. NO. SH. NO. REV.
"x " PIPE TO TUBE ADAPTOR M2-0250 - CP-19 me101980.dgn A M2-0250 B C D E F G FINAL PRINT H
A B c D E G H 1 PRESSURIZER SPRAY LINES FROM REACTOR COOLANT LOOPS TO PRESSURIZER ARE RUN USING LONG RADIUS BENDS TO COMPLY WITH MAXIMUM ALLOWABLE PRESSURE DROP PER WESTINGHOUSE DOCUMENT 3 STRAP ON (SURFACE MOUNTED) RID'S LOCATED AT BOTTOM OF PIPE 4 PIPE SLOPED DOWNWARD TO PROVIDE WATER SEALBETWEENPRESSURIZER 5 LOCATED APPROXIMATELY MIDWAY BETWEEN LOOP AND PRESSURIZER 6 SPARGER AND SPRAY HEADER SUPPLIED WITH PRESSURIZER RELIEF TANK VENTHOLEPROVIDED INSPARGERLINE TRANSITION AT PRESSURIZER LIQUID SPACE LEVEL INSTRUMENT AND SAMPLE NOZZLES AND OTHER LOCATIONS AS SHOWN SIMILAR TO ARRANGEMENT SHOWN ON MECHANICAL SYMBOLS AND NOTES DRAWING NUMBERM1-0200,NOTE 15 27 THE STRAP-ONR ID'S IDENTIFIED ON THE FOLLOWING TABLE ARE USED TO MONITOR THERMAL CYCLING AND STRATIFICATION IN THEIR AND NAC CCHmm THE DETAILS OF THE CONTROL LOOPS LUMINANT CPNPP GLEN ROSE, TEXAS FLOW DIAGRAM REACTOR COOLANT SYS1EM M2-0251 CP-21 G <FINAL PRINT> H
RC-11077 REJ\CTOR IlEAC TOR COOLANT COOlANT
-1 PUhiP Pultf' CCP C.L. ~J:_
RC-1052 PCV-4S~C P6V-4SSB
---]
CCf' C.L. INJ** CCP C.L. INJ. REACTOR REACTOR COOLANT COOlAN1 PUMP f'UIM' NITROGEN 1027 SUPPLY LOOP l LOOP 2 Amendment 67 February 5, 1988 IRC OAC COMAN!)£ PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 ANJ 2 PROCESS FLOW DIAGRAM REACT~ COO..ANT SYSTEM
~ lGUfll[ !l.l-2
'---~~---*--~--- ----~-- ----~--------------~
CPSES/FSAR NOTES TO FIGURE 5.1-2 RCS AT STEADY STATE FULL POWER OPERATION ITEM FLUID PRESSURE TEMP FLow a VOLUME 1 RC 2238.0 618.8 1101250 36.7125 68 2 RC 2233.1 618.8 110,250 36.7125 68 3 RC 2195.9 559.3 99,839 36.7125 68 4 RC 2192.4 559.3 99,839 36.7125 68 5 RC 2285.1 559.6 98,900 36.7125 68 6 RC 2283.2 559.6 98,900 36.7125 68 7-12 See Loop 1 Specifications (1-6) 68 13-18 See Loop 1 Specifications (1-6) 68 19-24 See Loop 1 Specifications (1-6) 68 25 RC 2285.1 559.6 1.0 0.0004 68 26 RC 2285.1 559.6 1.0 0.0004 68 27 RC 2235.0 559.6 2.0 0.0008 68 28 Steam 2235.0 652.7 720 68 29 RC 2235.0 652.7 1080 68 30 RC 2235.0 652.7 2.5 0.0008 68 31 RC 2235.0 652.7 0 0 68 32 Steam 2235.0 652.7 0 0 68 33 RC 2235.0 <652.7 0 0 Minimize 68 34 Nitrogen 3.0 120 0 0 68 35 RC 2235.0 <652.7 0 0 Minimize 68 36 Nitrogen 3.0 120 0 0 68 37 Nitrogen 3.0 120 0 0 68 38 Nitrogen 3.0 120 456 68 39 PRT Water 3.0 120 1350 68 a) Flow measured at 1300f and 2300 psig; charging and letdown not 68 included b) At the conditions specified 68 c) X 106 G8 Amendment 68 February 15, 1988
.--- --**-~- .. _._._ .... -
I I I I I* MISSILE SHIELD I
--:..~-- -.:::=.-:;;;:.:.....:;.:...::.-. **-.:r*-..
UNIT20NLY
, *.,-*.,. I MISSILE SHIELD UNIT20NLY
*~
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,Jt.l!!t-':.
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~
~
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~
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~
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1!4 - ....
~ -"111-11110.
t.::~"'=,.\~
~..,.'5 -f" t-"--:-1
..1.1-llt..~* ....-...,..,!Wlt-.--l ,.;.:...:..:.;~f.Ji SECTION LOOKING NORTH SECTION LOOKING EA§T OOIMAf:OtE PEAK S.E.S.
NUClEAR PLANT UHn'S hnt2 Figure 5.1-3
THIS FIGURE HAS BEEN DELETED. COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Vessel lnservice Inspection Tool Figure 5.2-1
Amendment 102 COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT Amendment 102 UNIT 1
~CS Heatup Limitations I Fi£ure 5.2-2 Sht. 1 Amendment 101 b
Amendment 102 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Amendment 102 UNIT 2 RCS Heatup Limitations Figure 5.2-2. Sht. 2 Amendment 102
THIS FIGURE HAS BEEN DELETED. COMANCHE PEAK S.E.S. Amendment 102 FNAL SAFETY ANALYSIS REPORT UMIT 1 RCS Cooldown Limitations L Figure 5.2*3. Sht. 1 Amendment 102
Amendment 102 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNIT 2 RCS Cooldown Limitations Figure 5.2-3. Sht. 2 Amendment 101 b
15,092-1
...J
...J 90° LlJ
Cl) LlJ 1-
<[ RII07-3 0
LlJ
LlJ 1-z: 180° IOI-121lA CORE 101-171 RII07-I 270° IOI-IIl2A
...J
...J LlJ Rll 08-1
Cl) 0:::: LlJ
~
...J oo 180° IOI-IIl2C IOI-IIl2B AMENDMENT 8 NOVEMBER 30, 1979 COMANCHE PEAK S.E.S.
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 1. Unit No. 1 Reactor Vessel Beltline Region Material Identification FIGURE 5.3-1A
15,092-2 90°
.....1
.....1 L&.l
Cl) L&.l R3807-l c:r: 0 L&.l
....z:
L&.l I OI-J2qA CORE 101-171 270° IOJ-Jq2A R3816-l
.....1
.....1 R3816-3 L&.l
Cl) 0:::
~
L&.l
.....1 oo 180° IOJ-lij2C I OI-l ij2B AMENDMENT 8 NOVEMBER 30, 1979 COMANCHE PEAK S.E.S.
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Unit No. 2 Reactor Vessel Beltline Region Material Identification FIGURE 5.3-1 B
180 r-------------------------------------------~ INTER & LOWER SHELL LONG. & GIRTH SEAM 160 140 120 CCI u.. 100 C!J a: w 80 z w 60 40 TNDT =. 70oF RT NOT = *70°F 20 0
*200 -100 0 100 200 TEMPERATURE (°F)
COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comanche Peak Unit l Beltline Region Weld Metal Charpy V-Notch Impa~t Data Weld Code No. Gl.67 FIGURE 5.3-2A Amendment 91 April 15, 1994
8 N 0 Ito. Ito. 0
~* ~1-
,_ 0 0 z
,_Zl- a::
0 0 N
~
g <?_
.... w a:
1-
<(
Ito. a: j-~ w
~ 0 !E
,_ w 1-1- 0 0 z
~~
0 (81*H) A9ij3N3 COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comanche Peak Unit 2 Beltline Region Weld Meml Charpy V-Notch Impact Data FIGURE 5.71-28 Amendment 91 April 19, 1994
TNDT * .2Qof TNoT* -20oF 100 0 0 100 RTNDT*10°F RTNDT'" -10°F 80 80 a; a;
-J -J to=. 60 to=. 60 I.L. I.L.
(!)
~
a: a: w 40 w 40 z w z w INT. SHELL RATE INT. SHELL RATE 20 R-1107-1 20 R-1107-2 0 ~----~----_.------~~ OL----L----"----"----'
-100 0 100 200 -100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F)
TNDT* *20of 100 RTNOT*10°F 80 a;
-J 60 to=.
I.L. (!) a: w 40 zw INT. SHELL RATE R-1107*3 20 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 o"---J.....--""----'""---'
-100 0 100 200 Comanche Peale Unit l Cho.rpy V*Notch Impact Data for TEMPERATURE (°F) IntennediateShell Plates R-1107-1. Rl107-2 and R-1107-3, Transverse Orientation FIGURE 5.3-3A Amendment 91 April 19, 1994
120 . . . . - - - - - - - - - - - , 120 . - - - - - - - - - - - - - , 0 TNoT* .2QoF TNoT* .2QoF RTNDT ** 20oF RTNDT *10°F 0 100 100 a; _, 80 a; _, 80 r!. r!. Ll. Ll.
> > 60
(,!) 60 (,!) a: a: w w z z w w 40 40 INT. SHELL INT. SHELL R-3807*1 R-3807-2 20 20 0 0 0
-100 0 100 200 -100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F)
TNoT* .2QoF RTNoT* .2QoF 100 2 80 a; r!. 0 Ll. 60 (,!) a: w 2 w 40 INT. SHELL COMANCHE PEAK S.E.S. 20 R-3807*3 FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 0 Comanche Peak Unit 2 Charpy V-Notchlmpact Data for
-100 0 100 200 Intermediate Shell Platea R-3807-1, R3807-2 and R-3807-3 T1"1111Bverse Orientation TEMPERATURE (°F)
FIGURE S.3-3B Amendment 91 April 15, 1994
TNoT* *20oF TNor**30oF 100 100 RTNor*OoF RTNor* 20°F 80
§- 80 m ..J m..J ~ 60 ~ 60 u.. u..
e, > 0 a: a: w w zw 40 zw 40 20 LOWER SHELL 20 LOWER SHELL R-1108*1 R-1108*2 0 o~---'-----'--- ........__.
*100 0 100 200 -100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F)
TNDT * .JOoF 0 100
~
RTNDT *OoF 80
..J *** ~ 60 u..
e, ! a: w 40 2
** COMANCHE PEAK S.E.S.
20 LOWER SHELL FINAL SAFETY ANALYSIS REPORT R-1108*3 UNITS 1 and 2 8 I--*** Comanche Peak Unit 1 0 ~----._----L-----~~ Charpy V-Notch Impact Data for Lower Shell Plates R-1108-1, R-1108-2 and R-1108-3,
-100 0 100 200 Transverse Orientation FIGURE 5.3-4A TEMPERATURE (°F)
Amendment 91 April 19, 1994
120 120 TNDT = -30oF TNDT = -30oF RT NOT= -30oF RTNDT = +/-OoF 100 100 80 80 co
....1 co
....1
60 60 Cl Cl a: a: LIJ LIJ z z LIJ 40 LIJ 40 LOWER SHELL LOWER SHELL 20 R-3816-1 20 R-3816-2 0 0 0
-100 0 100 200 -100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F) 100 80 iii ....1 u.
> 60 Cl a: LIJ zw 40 LOWER SHELL 20 R-3816-3 COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT 0 UNITS 1 and 2
-100 0 100 200 C otnMche Peak Unit 2 _
Charpy V-Notch Impact Data tor Lower TEMPERATURE (°F) Shell Plates R-3816-1. R-3816-2 and R-3816-3 Transve!11e Orientaion FIGURE 5.3-48 Amendment 91 April 15, 1994
FLYWHEEL UPPER RADIAL BEARING THRUST BEARING ---:::r~~'!;fil--- THRUST BEARING OIL LIFT PUMP
+ MOTOR MOTOR SHAFT MOTOR STATOR
~lAIN LEAD CONDUIT BOX 4-------~tOTOR UNIT ASSEMBLY LOWER RADIAL BEARING SEAL HOUSING NO. 3 SEAL LEAK OFF NO. I SEAL NO 2 SEAL LEAK OFF LEAK OFF PUMP SHAFT COOLING WATER INLET > J t - - - - - - COOLING WATER OUTLET
. ,.,.,____,~!+-ffl'-1~---+------ RAO I AL BEAR IN G
~
DISCHARGE NO!ZLE ASSEMBLY
~~~r-------+-------1 HE RMA L BARR I ER AND HEAT EXCHANGER SUCTION NOZZLE -----IMPELLER COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Reactor Coolant Controlled Leakage Pump FIGURE 5 .4-l
4026-183 600 500 TOTAL r-- HEAD t:::l 4-00 LL C> <( w
<( t-o r-- I I 200 I
/
/
/
~ REQUIRED NET 100 .-- PO~ITIVE SL1CTION HEAD 0
0 I0 20 30 4-0 50 60 70 80 90 I 00 I I0 FLOW - THOUSANDS OF GPM COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Reactor Coolant Pump Estimated . .
~~formance CharacterJStlc FIGURE 5. 4-2
6798-2 220 0 BTCT I 200 1--- 0 2TCT 9 6 4TCT I 180 o I I 1-- I 160 1-- I I N
I 4-0 1--
~
I o I 120 I 1-- I 6 I 100 -
~ I/
80 - I I 6 0 I 60 1-- 0 ttl
/
~ f1//
..a. . o.....o 4-0 1-- 0 LOWER BOUND Kid 0
~------
1-- 20 0 I I I I I I I
-200 -ISO -100 -50 0 50 100 150 200 REFERENCE TEMPERATURE (T-NDTr)-°F COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Krd Lower Bound Fracture Tough-ness SA-533, Grade B, Class 1 ___ .LB:~Je rence_Ull.._____. HGURE 5.4-3
GUlLeT NOZZLE WITH SEVE\1 (7) fLOW v:::N'U,RI
\IORMAL Q;:>ERATING WATER LEVEL (APPROX.)
*~~iA;;;j_Wf-4-----FE.W\,~ATER DISTRIBUTING RING
~EEDWA TER INLET NOZZLE AUX. FEEDWAIER NOZLE VIBRATION BARS FQt;R (4) 00 INSPECTION PORT TWO ( 2) TYPICAL TUBf SUPPORT PLATE TEN (10) TYPICAl SAMPL[ 'lAP WlOE RANG[
UPPi:R SLOWDOWN TAP SLOWDOWN TAP SECONDAR'i- SHELL DRAI\1 I AP CHANNEL HEAfl DIV*OER PLATE "RIMARY ""'VJA'v.~ TWO '2) ;vPICAL COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 1 LONGITUDINAL SECTION OF FEEDRING STEAM GENERATOR Amendment 102 FIGURE 5.4-4A
Steam Separators
- - - Level of Auxdiary Feedwater Nozzle Tube Bundle Tube Supports~
Preheater Outlet
~ Feedwater Nozzle
/ 16" Sch. 60 Preheater Section
--....___ Preheater Outlet COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 LONGITUDINAL SECTION OF PREHEAT STEAM GENERATOR Amendment 102 Fl CURE 5.4-48
If , t 90-96 SECTION A-A COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Steam Line Flow Restrictor FIGURE 5.4-5
A B c D E G H 3 D" IDFLOWRESTRICTORPROVIDED RC~<R<C<,,RAC.WUnCCW BE REMOVED A TPLANT STARTUP 7 INLET PIPING AND FITTINGS TO 1RH-8735C AND 1RH-8735D ARE REQUIRED TO BE OPEN IN RESIDUAL HEAT REMOVAL PUMP TBX-RHAPRH-01 MECHANICAL SEAL DRAm CLASS I
/ '
_ _( 1-HV- ~ 1 I \~7.:/ ------------------- D-VD-1-276-151R-5 LUMINANT r:!::..:-.~_:?~~R~ ________________________ .r\._ ____________________ .~A CPNPP
~I RHI GLEN ROSE, TEXAS FLOW DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM Ml-0260 CP-37 me104180dgn A Ml-0260 B c D E G < FINAL PRINT > H
I CPE A B c D E G H
?
--------------------------------------------------- LO-ts-
)AIT 6 9/32" FLOW RESTRICTOR WITH PIPING FOR CLASS 1 TRANSITION 8 INSTRUMENTVALVES AND 2RH-8735D AREREQUIREDTOBE OPEN IN MODES 1, 2AND 3 a VALVES AND LINE NUMBERS HAVE BEEN ADDED b CONTROL LOOPS HAVE BEEN DELETED EXCEPT FOR THE PRIMARY AND THE FINAL ELEMENTS THE DETAILS OF THE CONTROL LOOPS WILL BE SHOWN ON INSTRUMENTATION AND CONTROL DIAGRAM I
I I I ~2-8812A I I I I I I TO FLOOR DRAIN 9:
~I 31 4q gl
~I
~I til I
I I
---------------------------~
(I lruJ I I I I I I I I I
~I
;:'17. I
~~-~~-~
FROMCT HEAT EXCHANGER DRAINS CPNPP GLEN ROSE, TEXAS f-----------' FLOW DIAGRAM RESIDUAL HEAT I REMOVAL SYSTEM M2-0260 CP-21 me961800dgn A M2-0260 B c D E G < FINAL PRINT > H
"'cliJLit(;. JII!AT[F
,------L----------'----
"- *n t;J"<A(,f *AU<
-I ! I I
I _ _ _ _ _ _ __:_______,., - .J I I ~~~ I I j
-~~----~~
l I I i I I I I I '
~
I I 'i'l'i'! I I j I
- I I 1 **
I _.J__*n I I .___.__._.....- r------'-_,..........._ _ _ _ _ _ - I 1 COMANCHE PEAK S.E.S.
~o. .ft"" -' ,..,..., * .,o* ,:;-,) ... <1c',"' *HTt'()(( 'f FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 I< * '>JI. M11>'J~H:,~4 *.II *;,1 pqr(Jl:'>. 1tlf" ()(Htl:.
P t* -.., ,.,. .i', ~'>r'lt.Mtwa *()< t' ~tJfll !) 1l4l
* ,)tt ,, . .;,P.,. '-1f"' 'P ~lU:\', f!(>> ;;,AO.--
.HI IH "*1.,. .1.' fAI,t< NI.Jelllfl(';"*N' Residual Heat Removal System Process Flow Diagram FIGURE :ir.:r:-Sheet l
~'--
AMENDMENT 17 APRIL 7, 1981 NOTE: COMANCHE PEAK S.E.S.
REFER TO THE ENGINEERING FLOW DIAGRAM. Residual Heat Removal System REFER TO PROCESS FLOW DIAGRAM TABLES FOR Process Flow Diagram THE CONDITIONS AT EACH POINT. FIGURE 5.4-7, Sheet 2
NOTES TO FIGURE 5.4-7 (Sheet 1 of 4) MODES OF OPERATION 1 0212.63 Mode A - Initiation of RHR Operation When the reactor coolant temperature and pressure are reduced to 96 RHRS operational conditions. approximately 4 hours after reactor shutdown. the second phase of plant cooldown starts with the RHRS being placed in operation. Before starting the pumps. Component Cooling Water is established through the heat exchanger. Upon initial startup of the RHR pump. the miniflow valves automatically position open to protect the pump and RHR boration requirements are established. Once boration is completed. power is restored and the RHR to Hot Leg Recirculation Isolation Valves are opened. Startup of the RHRS includes a warm-up period during which time reactor coolant flow through the heat exchangers is limited to minimize thermal shock on the RCS. The rate of heat removal from the reactor coolant is controlled manually. not to 96 exceed 100°F per hour. Cooldown rate is based on equipment stress and a maximum Component Cooling water temperature of 122°F through the RHR heat exchanger. A constant flow is regulated automatically by control valves in the heat exchanger bypass line. Mode B - End Conditions of a Normal Cooldown This situation characterizes most of the RHRS operation. As the reactor coolant temperature decreases. the flow through the residual heat exchanger is increased until all of the flow is directed through the heat exchanger to obtain maximum cooling. Note: For the safeguards functions performed by the RHRS refer to Section 6.3. Amendment 96 Au ust 2. 1999
NOTES TO FIGURE 5.4-7 (Sheet 2 of 4) VALVE ALIGNMENT CHART Operational Mode A - B 2 c c 3 c c 10 0 0 11 0 0 12 c c 13 c c 14 c c 15 c c 16 p c 17 p c 18 p p 19 p p 20 c c 21 c c 22 0 0 23 0 0 24 0 0 26 0 0 0 = Open. C Closed. P =Partially Open. February 15, 1988
NOTES TO FIGURE 5.4-7 (Sheet 3 of 4) MODE A - INITIATION OF RHR OPERATION Pressure Temperature Flow Location Fluid (gsig} (OF} (ggm}a (lbLhr) Reactor 24 Coolant 400 350 3800 1.69 X 106 25 II 407 350 3800 1.69 X 106 26 " 542 350 3800 1.69 X 106 93 27 II 541 350 992 0.44 X 106 31 II 539 142 992 0.44 X 10 6 29 II 496 350 2808 1.25 X 106 32 II 496 296 3800 1.69 X 10 6 28 II 480 296 3690 1.64 X 106 19 Loop 4 " 404 296 1992 0.885 X 106 19 Loop 3 II 419 296 1698 0.755 X 106 18 34 II 400 350 3800 1.69 X 106 35 " 407 350 3800 1.69 X 106 36 542 350 3800 1.69 X 106 93 37 II 541 350 992 0.44 X 106 41 II 539 142 992 0.44 X 106 39 II 496 350 2808 1.25 X 106 42 II 496 296 3800 1.69 X 106 38 " 479 296 3910 1.74 X 106 20 Loop 1 II 404 296 1955 0.87 X 106 20 Loop 2 II 404 296 1955 0.87 X 106 a At reference conditions 350°F and 400 psig. Amendment 93 February 1, 1995
NOTES TO FIGURE 5.4-7 (Sheet 4 of 4) MODE B - END CONDITIONS OF A NORMAL COOLDOWN Pressure Temperature Flow Location Fluid (psig) (OF) (gpm)a ( lb/hr) Reactor 24 Coolant 0 140 3800 1.87 X 10 6 25 It 7 140 3800 1.87 X 106 26 " 156 140 3800 1.87 X 106 27 " 149 140 3800 1.87 X 106 31 " 129 120 3800 1.87 X 106 29 It 93 120 0 0 18 32 " 93 120 3800 1.87 X 106 28 " 75 120 3800 1.87 X 106 19 " 2 120 1900 0.935 X 106 18 34 " 0 140 3800 1.87 X 106 35 " 7 140 3800 1.87 X 106 36 II 156 140 3800 1.87 X 106 37 " 149 140 3800 1.87 X 106 93 41 II 129 122 3800 1.87 X 10 6 39 " 93 122 0 0 42 " 93 122 3800 1.87 X 106 38 " 75 122 3800 1.87 X 106 20 2 122 1900 0.935 X 10 6 a At reference conditions 140°F and 0 psig. Amendment 93 February 1, 1995
NORMAL RHR COOL DOWN 400 n lL u UJ 350 a:
1-4: a: 300 UJ 0. UJ 1-2~0
~ <(
__j 0 200 0 u a: 0 1~0 1- IflllffiilliHI!tlfltllHll] l)
<.(
UJ 0::
FINAL SAFETY ANALYSIS REPORT Amendment 93 February 1, 1995 UNITS 1 and 2 Nonna 1 RHR Coo 1down FIGURE 5.4-8
BTP RSB S-1 SINGLE TRAIN RHR COOLOOWN
.. ao . - - - - - - - - - - - - - - - - - - - - ------~--.
1\ lL LJ w cr 350
f-- <( cr w o_ 300 - 2. w f-- f-- z
<( 2'50
_j 0 0 L) cr 0 200 f-- L)
<(
w cr 10 15 20 25 30 35 40 TIME AFTER REACTOR SHUTDOWN (l-OURS) 21:.1 F AT T=H HOURS 200 F AT T=15 25 HOURS COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT Amendment 93 UNITS 1 AND 2 February 1, 1995 SINGLE TRAIN AHA COOLDOWN FIGURE 5.4-9
4026-185 SPRAY NOZZLE SAFETY NOZZLE UPPER HEAD INSTRUMENTATION NOZZLE Ll FT IHG TRUNN ION SHELL LOWER HEAD HEATER SUPPORT PLATE INSTRUMENTATION NOZZLE ELECTRICAL HEATER SUPPORT SKIRT SURGE NOZZLE COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Pressurizer FIGURE 5.4-10
SAFETY HEADS DISCHARGE LINE CONNECTION SPRAY WATER INLET VESSEL SUPPORT DRAIN CONNECTION VESSEL SUPPORT COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Pressurizer Relief Tank FIGURE 5.4-11
8555-29 COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Reactor Vessel Supports FIGURE 5.4-12
CONTAINMENT I 80° goo*----- 270°
-\:ACTOR a CONTAINMENT
<t_ SUPPORT EMBEDMENTS BY OTHERS TYP. FOR EACH SUPPORT 3'-cl' It_ REACTOR COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT AMENDMENT 8 UNITS 1 and 2 NOVEMBER 30, 1979 PLAN- REACTOR SUPPORTS TUSI UNIT:#: I FIGURE 5.4-12A
270°----- I
&CONTA[
t_REACTOR EMBEDMENTS BY OTHERS TYP. FOR EACH SUPPORT 3'-o" 1800
<t_ REACTOR COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT AMENDMENT 8 UNITS 1 and 2 NOVEMBER 30, 1979 PLAN-REACTOR SUPPORTS I
UPPER LATERAL SUPPORT S~UB8ERS
TO BE INSTALLED AT LOCATIONS 2 AND 4 AS SHOWN. DIRECTION OF THERMAL EXPANSION t~OTE: COMANCHE PEAK S E S ST ONLY ON LNIT 2. FINAL SAFETY ANALYSIS REPORT REMOVED FROM UNIT 1. UNITS 1 AND 2 TYPICAL STEAM GENERATOR SUPPORTS Amendment 102
.. FIGURE 5.4-13
TIE RODS CROSS-OVER LEG PIPE COLUMNS COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Reactor Coolant Pump Supports FIGURE 5
3842-5 SEISt~IC SUPPORTS PRESSURIZER SKIRT BEARING PLATE GROUT COMANCHE PEAK S. E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Pressurizer Supports FIGURE 5.4-15
THIS FIGURE HAS BEEN DELETED. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Crossover Leg Amendment 66 Restraint January 15, 1988 FIGURE 5.4-16
THIS FIGURE HAS BEEN DELETED. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Crossover Leg Amendment 66 Vertical Run Restraint January 15, 1988 FIGURE 5.4-17
THIS FIGURE HAS BEEN DELETED. COMANCHE PEAK S.E.S. FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Hot leg Pfpe Amendment 66 Whip Restraint January 15, 1988 FIGURE 5.4-18
0.5 INCH GAP INSULATION --""" (TYPICAL)
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. 4. *
REACTOR COOLANT PIPE COOLING AIR PASSAGE - - J {TYPICAL) AMENDMENT 61 PRIMARY SHIELD CONCRETE - . . . . J DECEMBER 19, 1986 (TYPICAL) COMANCHE PEAK S.E.S. NOTE: Hot and Cold Leg Restraint may be eliminated (See Section 5.4.14.2.5) FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYPICAL LATERAL RESTRAINTS FIGURE 5 . 4-19
Spring Return To Auto From Both Sides OPEN AUTO CLOSE MCB CONTACT CLOSES ABOVE HI FLOW SETPOINT CONTACT CLOSES BELOW LOW FLOW SETPOINT OPEN MOTOR OPERATED MOTOR OPERATED VALVE VALVE (MOV) (MOV) FLOW SW INSTRUMENT MOV TRAIN NO NO A FIS-61 0 FCV -610 B FIS-611 FCV-611 COMANCHE PEAK S.E.S. FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Amendment 91 April '15, 1994 RHR PUMP MINI-FLOW VALVE INTERLOCK FIGURE 5. 4-20}}