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Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23129A4882023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 4215, Rev. 3, Reactor Building Structural Shielding Blocks (HPCI Hatch) ML23129A2642023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section I, Figures ML23129A4682023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 4259, Sheet 1A, Containment Vessel Penetration Schedule ML23129A4982023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 919D690BC, Reactor Vessel, Sheet 5 ML23129A4992023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Functional Control Diagram Control Rod Drive Hydraulic System, Sheet 1 ML23129A4952023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E222BB, Sheet 3, Reactor Protection System ML23129A4962023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E222BB, Sheet 1, Reactor Protection System ML23129A4932023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E727BB, Rev. 2, Sheet 3, Functional Control Diagram Recirculation Flow Control System ML23129A4942023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing ILE70-3, Sheet 107c, Installation Details - Temperature Detectors for Nuclear Boiler Systems Leak Detection ML23129A4912023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E402BB, Rev. 6, Sheet 1, Functional Control Diagram Core Spray System ML23129A4922023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E223BB, Neutron Monitoring System, Sheet 1 ML23129A4892023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E589BB, High Pressure Coolant Injection System Functional Control Diagram, Sheet 3 ML23129A4872023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E100, Neutron Monitoring, Sheet 2 ML23129A4702023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E517BC, Functional Control Diagram Reactor Core Isolation Cooling System, Sheet 2 ML23129A4842023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Sheet 5, Functional Control Diagram Control Rod Drive Hydraulic System ML23129A4862023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 4259, Rev. 10, Sheet 1, Containment Vessel Penetration Location ML23129A4822023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Functional Control Diagram, Control Rod Drive Hydraulic System, Sheet 2 ML23129A4832023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 919D690BC, Revision N01, Recirclulation Outlet Nozzle, Sheet 3 ML23129A4792023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 3005, Sheet 4, Auxiliary One Line Diagram Motor Control Centers M, N, P, U, V, & W ML23129A4802023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Functional Control Diagram Control Rod Drive Hydraulic System, Sheet 6 ML23129A4772023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Control Rod Drive Hydraulic System Sheet 7 ML23129A4782023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing CNS-NBI-10, Revision N06, Reactor Water Level Indication Correlation ML23129A4752023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E517BC, Reactor Core Isolation Cooling System Functional Control Diagram, Sheet 3 ML23129A4762023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E148BB, Sheet 1, Process Diagram Reactor Water Clean-Up System ML23129A4722023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E727BB, Recirculation Flow Control System, Sheet 1 ML23129A4742023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing CNSMS43, Rev. 5, Leakage Paths from Outboard Msiv'S ML23129A4712023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E719BC, Sheet 1, Process Diagram Reactor Core Isolation Coolant System ML23129A4672023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 6000302, P & I Diagram Augmented Offgas System, Sheet 1 NLS2023022, 1 to Updated Safety Analysis Report, Drawing ILE70-3, Sheet 107f, Installation Details - Temperature Detectors for Nuclear Boiler Systems Leak Detection2023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing ILE70-3, Sheet 107f, Installation Details - Temperature Detectors for Nuclear Boiler Systems Leak Detection ML23129A4902023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E140BB, Revision N05, Sheet 2, Fcd Residual Heat Removal System ML23129A5002023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 719E479BB, Process Radiation Monitoring System, Sheet 1 ML23129A5012023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 3058, DC One Line Diagram ML23129A4812023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E140BB, Rev. 10, Sheet 1, Functional Control Diagram Residual Heat Removal System ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23129A4692023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 791E257, General Electric, Sheet 4 ML23129A4852023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E805BA, Revision N01, Neutron Monitoring System Functional Control Diagram, Sheet 7 ML23129A4732023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 731E611, Revision N04, Primary Steam Piping Nuclear Boiler Purchased Part, Sheet 1 2023-04-20
[Table view] Category:Drawing
MONTHYEARML23129A4862023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 4259, Rev. 10, Sheet 1, Containment Vessel Penetration Location ML23129A4662023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E197BB, Rev. 7, Sheet 6b, Reactor Recirculation Controller Configuration ML23129A2642023-04-20020 April 2023 1 to Updated Safety Analysis Report, Section I, Figures ML23129A4982023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 919D690BC, Reactor Vessel, Sheet 5 ML23129A4962023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E222BB, Sheet 1, Reactor Protection System ML23129A4952023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E222BB, Sheet 3, Reactor Protection System ML23129A4932023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E727BB, Rev. 2, Sheet 3, Functional Control Diagram Recirculation Flow Control System ML23129A4922023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E223BB, Neutron Monitoring System, Sheet 1 ML23129A4912023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E402BB, Rev. 6, Sheet 1, Functional Control Diagram Core Spray System ML23129A4882023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 4215, Rev. 3, Reactor Building Structural Shielding Blocks (HPCI Hatch) ML23129A4872023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E100, Neutron Monitoring, Sheet 2 ML23129A4682023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 4259, Sheet 1A, Containment Vessel Penetration Schedule ML23129A4842023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Sheet 5, Functional Control Diagram Control Rod Drive Hydraulic System ML23129A4832023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 919D690BC, Revision N01, Recirclulation Outlet Nozzle, Sheet 3 ML23129A4822023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Functional Control Diagram, Control Rod Drive Hydraulic System, Sheet 2 ML23129A4782023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing CNS-NBI-10, Revision N06, Reactor Water Level Indication Correlation ML23129A4792023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 3005, Sheet 4, Auxiliary One Line Diagram Motor Control Centers M, N, P, U, V, & W ML23129A4762023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E148BB, Sheet 1, Process Diagram Reactor Water Clean-Up System ML23129A4772023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Control Rod Drive Hydraulic System Sheet 7 ML23129A4742023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing CNSMS43, Rev. 5, Leakage Paths from Outboard Msiv'S ML23129A4752023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E517BC, Reactor Core Isolation Cooling System Functional Control Diagram, Sheet 3 ML23129A4712023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E719BC, Sheet 1, Process Diagram Reactor Core Isolation Coolant System ML23129A4732023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 731E611, Revision N04, Primary Steam Piping Nuclear Boiler Purchased Part, Sheet 1 ML23129A4692023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 791E257, General Electric, Sheet 4 ML23129A5012023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 3058, DC One Line Diagram ML23129A4812023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E140BB, Rev. 10, Sheet 1, Functional Control Diagram Residual Heat Removal System ML23129A5002023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 719E479BB, Process Radiation Monitoring System, Sheet 1 ML23129A4942023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing ILE70-3, Sheet 107c, Installation Details - Temperature Detectors for Nuclear Boiler Systems Leak Detection ML23129A4802023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Functional Control Diagram Control Rod Drive Hydraulic System, Sheet 6 ML23129A4702023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E517BC, Functional Control Diagram Reactor Core Isolation Cooling System, Sheet 2 ML23129A4902023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E140BB, Revision N05, Sheet 2, Fcd Residual Heat Removal System ML23129A4672023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 6000302, P & I Diagram Augmented Offgas System, Sheet 1 ML23129A4892023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E589BB, High Pressure Coolant Injection System Functional Control Diagram, Sheet 3 NLS2023022, 1 to Updated Safety Analysis Report, Drawing ILE70-3, Sheet 107f, Installation Details - Temperature Detectors for Nuclear Boiler Systems Leak Detection2023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing ILE70-3, Sheet 107f, Installation Details - Temperature Detectors for Nuclear Boiler Systems Leak Detection ML23129A4992023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E471BB, Functional Control Diagram Control Rod Drive Hydraulic System, Sheet 1 ML23129A4852023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 730E805BA, Revision N01, Neutron Monitoring System Functional Control Diagram, Sheet 7 ML23129A4722023-04-20020 April 2023 1 to Updated Safety Analysis Report, Drawing 729E727BB, Recirculation Flow Control System, Sheet 1 2023-04-20
[Table view] |
Text
PIPING AND SYSTEM DESIGNATIONS G. E. G. E.
SYSTEM CODE SYS NO SYSTEM CODE SYS NO VALVE NUMBERING CODE ~ - - - - INDIVIDUAL IDENTIFYING NUMBER FOR OPERATOR AlR REMOVAL AR HEATER & MISC (NON-RADIOACTIVE) DRAINS DR -
TYPICAL NUMBER - - - 4"V243W(A)-3( 4" -300#-ANGLE VALVE-ASTM A216 WCB-BUTT WELD END~)
l AUXILIARY STEAM AS HIGH PRESS COOLANT INJECTION HP 23 CARBON DIOXIDE C HYDROGEN H I ~OMINAL SIZE I t------~
1 l '~--INDIVIDUAL VALVE OPERATOR'S IDENTIFYING NUMBER (USE ON STANDARD VALVES)
~ - - INSERT SPECIAL BODY FEATURE: ANGLE, (SC) STOP CHECK, (WC) WAFER CHECK, (S) SPHERICAL DISC BUTTERFLY, (TD) TILTING DISC, (Pl) POST INDICATOR I
CHEMICAL ADDITION CF INSTRUMENTATION (PROCESS) PI CIRCULATING WATER cw LUBE OIL PURIFICATION & TRANSFER LO I
~
EXAMPLE OF A SPECIAL VALVE I I CLOSED COOLING (REACTOR BLDG) RCC MAIN STEAM MS 2 PREFIX FIRST DIGIT SECOND DIGIT THIRD DIGIT - MATERIAL CLASS (ASTM) ENDS TYPE PRESSURE CLASS-LB CLOSED COOLING (TURBINE BLDG) TCC MISCELLANEOUS RADIOACTIVE WASTE MW STANDARD VALVE WITH MANUAL A 126 CL.B IRON BODY w BUTT WELD 10" 685 SV166W HAND WHEEL OR LEVER; GATE COMPRESSED AIR (CONTROL) CA NITROGEN (ATOMS CONTROL) N 16 V STANDARD LIFT OR SWING 1 125 2 B 61 BRONZE X SOCKET WELD
- - - - - - - - - ~ - ---------- SPECIFIED AS A 1 O" GATE VALVE - 900 LB CLASS COMPRESSED AIR (STATION) SA POTABLE WATER PO CHECK VALVE 2 GLOBE/ ANGLE 2 150 A 216 WCB-2 1 /2" AND LARGER F FLANGED MATERIAL A 351 CFS/CF 8M l----+--------
EV STD. VALVE W/EXTENSION STEM 3 CHECK 3 A 105 GR.11-2" AND SMALLER BUTT WELD ENDS CONDENSATE CH PROCESS (RADJOACTIVE) VENTS PV 3 200 (175) S SCREWED
- -- - - - - - - - ~CARBON
~ - ---STEEL
- - - - - - - - - - - ----1 WITH LIMIT SWITCHES CV STANDARD VALVE WITH CHAIN WHEEL DIAPHRAGM 4 300 (250) A 217 WC6-2 1/2" AND LARGER p CONTROL ROD DRIVE HYDRAULIC HY 3 PROCESS SAMPLING PS PLAIN END 4 ----1 LV STANDARD VALVE WITH LOCK (SAUNPERS TYPE) 5 600 4 A 182 F11-2" AND SMALLER CORE SPRAY cs 14 RADIOACTIVE (EQUIPMENT) WASTE PW 20 _ CH_ROME-MOL'l'_~LLQY STEEL _(1__1 / 4%CR.)
STANDARD VALVE WITH DOUBLE 5 PLUG/BALL 6 900 A 217 WC9-2 1(.2" AND LARGER SPECIAL DESIGNATIONS:
CONDENSATE POLISHING CP REACTOR CORE ISOLATION COOLING RC 13 GV PACKING & GLAND FOR RADIOACTIVE I---- - ------ --- -
5 FLUID SERVICE 6 NEEDLE/ 7 1500 A 182 F-22-2' AND SMALLER CHROME-MOLY ALLOY STEEL (2 1 / 4%CR.'
(NUMBERED CONSECUTIVELY & COVERED DEMINERALIZED WATER OW REACTOR FEEDWATER RF 6 --- - - - - - - - t - - - - - - *------------ - - - - - - - - - ,
INSTRUMENT
- IMV MOTOR OPERATED VALVE 8 2500 A 351 CF8/CF8M (OR EQUIVALENT) BY SEPARATE SPECIFICATIONS)
DIESEL OIL (CLASS I) DO REACTOR RECIRCULATION RL 2 6
- !AV AIR OPERATED VALVE 7 THREE-WAY 9 SPECIAL 18-8 STAINLESS STEEL DIESEL STARTING AIR STA REACTOR WATER CLEAN UP cu 12 - *I;V - ---SPECIAL- VALVE-(AS DESCRIBED- 8 BUTTERFLY 7 B 26 GR.SG70A (OR EQUIVALENT)
SAFETY OR RELIEF VALVES -(RV) ISOLATION VALVES (IV)(IMV) WITH MOTOR OPER.
IN SPECIFICATION) ALUMINUM ALLOY EXTRACTION (BLEED) STEAM BS RESIDUAL HEAT REMOVAL RH 10 ~-----+--------------------i SOLENOID VALVES -(SSV) BYPASS VALVES (BV)(BMV) WITH MOTOR OPEN NON-RETURN 9 SPECIAL A 352 GR.LCB 2 1 /2" AND LARGER VALVES (AIR OPERATtD, 13LEEDER CHECK)-(NRV)' DRAIN VALVE (ORV)
EXHAUST STEAM ES ROOF DRAINS RD *LEAD NUMBER DESIGNATES EXACT 8 A 350 GR.LFI 2" AND SMALLER FIRE Hor VALVE -(HV) FIRE HYDRANT (HT) DUMP VALVE -(DV)
VALVE FOR WIRING DIAGRAMS, ETC. CARBON STEEL (IMPACT TESTED) MISC SPECIALTIES (TRAPS, STRAINERS, tXPANSION JOINTS, ..... E1Ct-(S)
FILTERED WATER FW SCREEN WASH WW THE FOLLOWING NUMBER RANGES CONTROL VALVES - SEE INSTRUMENT CODING (DWG 2001 SHT 1 . CONTROL ARE RESERVED FOR THE MOTOR OPERATED, 9 SPECIAL VALVES SHALL HAVE THE SAME NUMBER AS HE CONTROL FIRE PROTECTION FP SERVICE (RIVER) WATER SW LOOP OF WHICH THEY FORM A PART.
AIR OPERATED & SPECIAL VALVES IN FLOOR DRAINS (NON-RADIOACTIVE) FON STANDBY LIQUID CONTROL LC 11 THE DESIGNATED SYSTEMS.
FLOOR DRAINS (RADIOACTIVE) FDR 20 VENTS (NON-RADIOACTIVE) OPEN V TYPICAL VALVE NO's SYSTEMS 1MV-36MV REAC FEED & COND FUEL OIL (TO HTG BLRS) FO VENTS (RADIOACTIVE) OPEN VR 37MV-59MV MN. & AUX. STM FUEL POOL COOLING FC 19 WELL DISCHARGE WD 1 HEATER DRAIN SYST FUEL GAS (TO HTG BLRS) FG RIVER WELL DISCHARGE RWD 60MV-99MV i & BLEED STM NOTES:
VENTILATION SYSTEM PIPING CIRC WTR, SERVICE 100MV-129MV WTR, SCREEN WASH, THE ABOVE IDENTIFICATION CODE IS FOR GUIDANCE ONLY AND DOES NOT FIRE PROTECTION COVER ALL VALVE TYPES PRESSURE RATINGS AND/OR MATERIALS. REFER TO THE SPECIFICATIONS FOR THE ASSIGNMENT OF NUMBERS TO SPECIAL DESIGN CONDITIONS 130MV-149MV TURBINE BLDG CLOSED VALVE CATEGORIES AND SPECIFIC MATERIALS.
COOLING SYSTEM CODE SUFFIX NO.* I -1 -2 -3 -4 -5 -6 150MV-169MV AIR REMOVAL &
n<lSS l~MP ,, 1lMP Pi<E:,:, It.Mt" i "' i OFF-GAS SYS CODE LETTERS
'F PSIG 'F PSIG 'F PSIG 'F PSIG i °F PSIG ~F ------------~-----------1
! SEE NOTE I
MISC MECHANICAL AR 650 VAC-30 220 170MV-229MV i 1 BELOW i SYSTEMS AS 300 420 - - - 225 400 50 305 15 305 -- I HTG, VENTILATING AIR
--- ------ - ----- ----- ------------- ,--- __ ,, ____ -*- --- *---- ,, ___ -----* ------ -- - . --------- -- ---- --- - - - --+------ -- - 230MV-299MV C , (NOT I CONTR ,CT E-$9-4) I
' CONDITIONING SYST'S CF I' 250 100 250 ! 1 00 300MV-399MV l OPEN
~ic~TCC-------~1--,fo---+-:~ - 0--~: 4- 5---1------1-- - - - ,1 --,----,---+ 1 400MV-490MV 491 MV-499MV
, RADWASTE SYSTEMS REACTOR BLDG STEAM CA, SA : 1 25 200 -----*------*- --*--*-***---------- - - - - - *- ----- ------ **-------
RESIDUAL HEAT CH 670 375 185 200 VAC-50! 110 500MV-549MV REMOVAL SYSTEM DW, FW, PO, WD, WW 150 150 HIGH PRESS COOLANT 550MV-574MV DO VAC-50 100 INJECTION SYSTEM 30"HG BS 225 400 1 00 : 350 300 REACTOR CORE !SOL VAC-50 575MV-590MV ES iVAC-15 250 I COOLING SYSTEM
~-----------1---
REACTOR WATER FP ! 175 100 591 MV-629MV CLEAN-UP SYSTEM FON RD I 1 50 150 50 : 150 FUEL POOL COOLING FO I 150 220 630MV-640MV SYSTEM I
I DR I 300 400 22s 400 100 350 VAC-50i 300 15 220 15 220 MISC NUCLEAR 641MV-674MV H , 2000 150 1 50 I 1 50 SYSTEMS PI 1250 575 100 300 CORE SPRAY I
! 675MV-693MV SYSTEM W 75 150 ----
t-------------+----+- REACTOR BUILDING MS 1147 563 450 II 400 694MV-730MV CLOSED COOLING PS 1250 575 500 350 150 325 50 150 SYSTEM RF 1925 370 BALANCE OF 730MV-UPWARD 490 145 i'L__ ------ - NUCLEAR SYSTEMS r
SW
*- ---- ---- -- - - - - - .. --- _____ ._ ___ ------ *t------ - 7_5_ _ ~ _145 . - **-- - - -- ----- --- -- ---
V 15 220 I '
VR I 625 495 15 I 220 :
FG i 150 150 150 ,I 150 VENT SYS PIPE I 75 300 HY 1500 200 VAC-60; 200 1500 400 I - - - - + - - - - + - - - ~ - i- - + - - - - - t - - - - - - - l cs
,-----------+---+---+
[ 1250 575 500 , 350 150 225 : I FDR, PW, MW - - - -------- - --
1 150 150 50 i
-+--- -
150 !
:- -----, ----+- - - - ~ - - - - - -------- ---- - -
i i 200 f----
FC HP, RC
+-- ---
150
/s0o0o : :~~ scio___ 400-+-15_0_@ 325 -- 85 I 200 ! ----- ----
________ ____ _ J so_ _______ 100 25 100 --- --- ------- -- _____ J__ _ ---** *l- - - -------- - --------
15 220 l
1 RL __ _ _ _ _12_7_4_+__ 5_6_2_ +-1146 575 _ 150 300
-t----
cu 1300 575 150 i 250 1300 150 RH 1326 562 450 i 400 150 350 125 225 LC 1375 575 1460 150 100 150 ' 1
~ - - - - - - - - - - - - + - - - + - - - - - - , c - - - - - t - - - + - - - - - + - - - - - + - - - - + - - - - + - '- - - + - - - - - t - - - - - - - i CP , 200 150 i STA i 300 i 150 RH-IS I 1275 575 .
RF-IS i 1250 575 i i i t - - - - - - - - - - - - - - - + ,- - - - ~ - - - - + - - - ~ ' - - - + - - --j-------,' - - - - f -------, - - + - --+-,-------- - - - - -
RWD : 1 50 1 00 i i ,
NOTE: WHERE CODE SUFFIX NUMBER IS FOLLOWED BY A LETTER (EXAMPLE: FC-1 S) THE DESIGN CONDITIONS WILL BE THE SAME AS CODE NUMBER WITHOUT A LETTER EXCEPT RH-1 S & RF -1 S WHICH ARE LISTED IN TABLE SEPARATELY.
- LINE DESIGNATIONS SIGNIFY MATERIALS AS FOLLOWERS:
-1 NUMBER ONLY - STANDARD MATERIAL FOR THAT PRESSURE AND TEMPERATURE.
-1A ALUMINUM PIPING AND/OR VALVES FOR SPECIAL CONDITIONS.
-1C CHROME - MOLY ALLdY STEEL PIPING AND/OR VALVES FOR SPECIAL CONDITIONS.
-1S(a) STAINLESS STEEL PIPING AND/OR VALVES tOR SPECIAL CONDITIONS. "(a)" INDICATES CARPENTER "20" ALLOY.
-1 D IMPACT TESTED (CARBON STErL) ON CERTAIN SYSTEMS MEETING AEC CRitERIA 35.
EXAMPLES: AS BUILT CH-2 DR-2C CONDENSATE PIPING WITH DESIGN CONDITIONS 670 PSIG, 375'F, CARBON STEEL PIPE.
HEATER DRAIN PIPING WITH DESIGN CONDITIONS OF 225 PSIG, 400'F, BUT WITH CHROME - MOLY ALLOY STEEL PIPE.
454003579 STATUS: Release NOTES: STATUS DATE: 10/20/2017 DS APPROVED: DTWALEN
- 1. AR: 1 DESIGN PRESSURE (DUE TO IMPACT OF HZ EXPLOSION) VAC-350 PSIG FOR STRAIGHT PIPE, VER: AB REV: 08 SIZE: F VAC-900 PSIG FOR ELBOWS, CAPS, TEES AND OTHER POINTS OF DIRECTIONAL CHANGE. SJGNJFICANT DRAWN I DATE NUMBER RGA 4/23/04
- 2. DESIGN CONDITIONS ARE FOR GENERAL REFERENCE ONLY. WHERE THERE IS A CONFLICT WITH PIPING CONTRACT SPECIFICATION, THE SPECIFICATION GOVERNS.
FOR PREVIOUS REVISIONS, SEE SUPERSEDED CARDS. GROUP
' ' CHECKED I DATE
'°r---
VERSIONS/REVISIONS BY N_P_P_O_ BURNS & ROE
- 3. SEE B&R DWG 2044 NOTE 11. NO. DESCRIPTION OFT DATE ENG FLOW DIAGRAM APPROVED I DATE
<D
"'"'0 AB/08 DR-2017-0001 DLR 10/20/17 DTWALEN SYMBOLS & ABBREVIATIONS SEE ~rf~JEDED f---~---'----------1 cu c..i 0
COOPER NUCLEAR STATION 2001 SH 2 OF 2 FILMED
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