ML21361A229
ML21361A229 | |
Person / Time | |
---|---|
Site: | Perry |
Issue date: | 12/20/2021 |
From: | Energy Harbor Nuclear Corp |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML21361A235 | List:
|
References | |
L-21-287 | |
Download: ML21361A229 (19) | |
Text
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r N 6 r 6.c F o '! 9 : : ! : I I : 3 I R F N R I R F R R R B ; S 3 t g H E B C t a C 3 I g $ i t 3 I 6 S B E $ S G fi E E 6 3 3 E I E 6 E I R NOTES:
TO HCU'S TO HCU'S (BANK A&B) (BANK C&D) 1. ONE STABILIZING VALVE OF STABILIZING VALVE ASSEMBLY (F007) CLOSES ON WITHDRAWAL SIGNAL PER ONE DRIVE OPERATION. TWO A-3 A-3 A-3 A-3 STABILIZING VALVES OF STABILIZING VALVE ASSEMBLY (F007) CLOSE 1/2" 1/2" 1/2" 1/2" ON INSERT SIGNAL PER ONE DRIVE OPERATION. FOR GANGED ROD DRIVE 302-0872-00000 302-0872-00000 302-0872-00000 302-0872-00000 OPERATION,AN APPROPRIATE NUMBER OF STABILIZING VALVES SHALL BE OPERATED.
E 2. PROVISION FOR CONTAINMENT ISOLATION TO BE IN ACCORDANCE WITH 1" 1" 1" 1" CURRENT LICENSING REQUIREMENTS.
EA015 3. SCRAM DISCHARGE DRAIN MUST BE SUBMERGED DUE TO POTENTIAL O O O O RELEASE OF STEAM LEAK-OFF AND RADIOACTIVE NON-CONDENSIBLES. H13-P680 H13-P680 F533 F534 C22-F535 F536 4. PROVIDE VENT VALVES WITH CAP ON DISCHARGE SIDE AT ALL H13-P613 P002 SYSTEM HIGH POINTS. F101 IS THE VENT VALVE FOR THE INSERT LINE 1" C 1" C 1" C 1" C AND F102 IS THE VENT VALVE FOR THE WITHDRAW LINE. THE FIRST "X" H PS A 3/4" 3/4" 3/4" 3/4" FOLLOWING THE F101/F102 CORRESPONDS TO THE NUMBER OF TIMES A N652 L C22-P001 C22-P002 C22-P001 THE ALPHABET WAS USED TO ENCOMPASS ALL 177 HCU'S. THE SECOND "X" REPRESENTS THE RESPECTIVE ALPHABET LETTER. PI S S S S
- 5. PROVIDE DRAIN VALVES WITH CAP ON DISCHARGE SIDE AT ALL SEE NOTE 26 R013 SYSTEM LOW POINTS.
F513 6. EXHAUST FLOW FROM MOVING DRIVES IS DISPERSED VIA THE HCU'S PT OF ALL OTHER NON-MOVING DRIVES TO REACTOR VESSEL. F159B 7. AVAILABLE FOR TEMPORARY CONNECTION FOR DRIVE TESTING AND N052 FLUSHING. NO PERMANENT PIPING CONNECTIONS TO BE MADE TO C11-P001 FROM REDUNDANT FROM REDUNDANT FROM REDUNDANT FROM REDUNDANT 3/4" F512 REACTIVITY CONTROL REACTIVITY CONTROL REACTIVITY CONTROL REACTIVITY CONTROL THIS VALVE. SYSTEM SYSTEM SYSTEM SYSTEM 8. VACUUM BREAKER VALVE (F120) AND VENT VALVES (F010 & F180) TO F1041 NE F182 F094 1" BE ON HIGH POINT OF VENT LINE. VACUUM BREAKER VALVE SHALL OPEN SEE NOTE 31 1/4" 1/2" D2-4 1/2" 1" SCRAM VALVE PILOT AIR HEADER 1" SCRAM VALVE PILOT AIR HEADER ON A DIFFERENTIAL PRESSURE SETTING OF NO GREATER THAN 1.0 PSI. THE LOCATION OF THE VACUUM BREAKER SHOULD CONSIDER THE LO LO POTENTIAL RELEASE OF RADIOACTIVE NON-CONDENSIBLES, WATER AND STEAM THAT COULD OCCUR IF THE VACUUM BREAKER VALVE WERE TO FAIL IN AN OPEN POSITION WHEN THE VENT SYSTEM PIPING IS 3/4" PRESSURIZED. F159A 9. EXCEPT AT POINTS OF CONNECTION WITH NED SUPPLIED EQUIPMENT OR
SEE NOTE 27 PIPING, THE PIPING DESIGNER SHALL SIZE PIPES IN CONFORMANCE SOL B S S SOL A WITH THE SYSTEM SPECIFICATION AND PROCESS DIAGRAM. FROM REDUNDANT 3/4" 3/4" 10.FOR LOCATION AND IDENTIFICATION OF INSTRUMENTS, SEE INSTRUMENT REACTIVITY CONTROL ND ND ND ND F095 G-9 DATA SHEET LISTED IN MPL FOR EACH INSTRUMENT. 1/2" SYSTEM 1" 11.CRD NITROGEN AND AIR LINES SHALL BE OF A F 302-0244-00000 NON-CORRODING MATERIAL. O F160A F160B F110A F110B F1040 12.MULTIPLE ORIFICES CONNECTED IN SERIES AS SHOWN IN PURCHASE C22-P002 FROM REACTOR D006 PART DRAWING OF ORIFICE D008. THE PRESSURE DROP ACROSS EACH PROTECTION C22-P001 C22-P002 FILTER 75-80 PSIG ORIFICE IS 250 PSI AT PUMP RUN-OUT CONDITION. SEE MPL F0R THE C SYSTEM INSTRUMENT AIR QUANTITIES OF ORIFICES. VALVE F034 SUPPLEMENTS THE ORIFICES 1/4" REFERENCE 9 H13-P680 1/2" D008 FOR THE REQUIRED PRESSURE DROP. K-13 RMS 13.THE SCRAM DISCHARGE VOLUME ARRANGEMENT SHOWN IS FOR REFERENCE S F163A 302-0872-00000 ONLY. FOR REQUIREMENT, SEE CRD DESIGN SPEC. REFERENCE 10.
F089 NE F009 INSTRUMENT 14.DELETED 1/2"D2-4 SEE NOTE 31 O C O C DC DC DC DC AIR SUPPLY EXHAUST LO 15.FLUSHING CONNECTIONS SHALL BE PROVIDED IN ACCORDANCE WITH O REFERENCE 7. TEMPORARY STRAINER SCREENS SHALL BE PROVIDED ON H13-THE SUCTION SIDE OF ALL PUMPS IN ACCORDANCE WITH REFERENCE 7. 2 P680 S F163B FROM REDUNDANT FROM REACTOR PROTECTION 16.ISOLATION VALVES SHALL BE LOCATED AS CLOSE AS PRACTICABLE C H13-P680 REACTIVITY CONTROL SYSTEM SYSTEM C71-1010,SH.1,J-6 & J-8 TO THE CONTAINMENT PENETRATION. D2-2 E1-4 C22-RMS 17.CONTINUOUS FLOW TO THE REACTOR SAMPLE STATION SHOULD BE SEE P002 SOL B S S SOL A 1 LITER/MINUTE MAXIMUM SHALL BE 2 LITER/MINUTE. NOTE 30 O 18.VENT PORT TO CONFORM WITH SAE INTERNAL STRAIGHT THREAD BOSS SEE NOTE 8 DIMENSIONS FOR.50 TUBE STRAIGHT THREAD FITTING (3/4-16UNF-2B) AND DEPTH OF.50 MINIMUM EFFECTIVE THREAD TO BE COMPATIBLE C WITH THE INSTRUMENT USE FOR TESTING. F120 C C FROM REDUNDANT DIV 1 19.A PORTABLE NITROGEN CHARGING SYSTEM SHALL BE PROVIDED TO 3/4" FROM REACTOR B-3 MEET THE REQUIREMENTS OF THE HCU. SEE REFERENCE 15 FOR NC065 NC064 REACTIVITY PROTECTION SPECIFIC ACCUMULATOR CHARGING REQUIREMENTS. IT SHALL BE 1" CONTROL SYSTEM DIV 2 SYSTEM 302-0872-00000 DESIGNED AND CONSTRUCTED IN ACCORDANCE WITH GOOD INDUSTRY REFERENCE 9 3/4" FROM HCU'S PRACTICE AND SHALL HAVE THE APPROPRIATE SAFETY DEVICES,GAGES, D0410 E1-2 D0409 (89 TYP.) AND VALVES. A PRESSURE RELIEF VALVE SHALL BE INSTALLED 3/4" 1" 1" DOWNSTREAM OF THE CHARGING STATION PRESSURE REGULATOR WHICH SHALL PREVENT PRESSURIZATION ABOVE SYSTEM REQUIREMENTS. F180 F010 20.DELETED F155C F155D DRYWELL CONTAINMENT 3/4" 1" 1" 21.DELETED LO LO 2 (9 TYP.) (9 TYP.) 22.SOURCE OF CRD SYSTEM WATER SHALL BE NORMALLY FROM CONDENSATE VALVE VENT ELEVATION TREATMENT SYSTEM. CONDENSATE STORAGE TANK IS THE ALTERNATE F156C F156D 2 SOURCE IF CONDENSATE TREATMENT SYSTEM IS NOT IN OPERATION. E1-4 E1-2 FOR DETAILED DESIGN REQUIREMENT FOR SOURCE AND QUALITY OF SEE SEE NOTES 8" E1-2 E1-2 8" WATER, SEE REFERENCE 10. LX LX NOTE 23,24 & 25 23.THE SCRAM DISCHARGE VOLUME VENT LINE SHALL BE ROUTED VIA A 35 F1045 DEDICATED LINE TO A NON-SUBMERGED DISCHARGE. THE VENT SYSTEM 1/2"E2-2 1/2"E2-2 LO 3/4"E2-2 PIPING SHOULD NOT CONTAIN SIGNIFICANT FLOW RESTRICTIONS LS LS F1044 F1043A WHICH COULD INHIBIT VENTING OF THE SCRAM DISCHARGE VOLUME TO 3/4" 3/4" F1043B THE EXTENT OF LIMITING THE SCRAM DISCHARGE VOLUME DRAIN RATE. N013 N013 LO LO LO THE DESIGN OF THE NON-SUBMERGED VENT DISCHARGE MUST CONSIDER C D A SCRAM THE POTENTIAL FOR THE RELEASE OF RADIOACTIVITY DUE TO THE F090A F090B F093A F093B F090C F090D F155A F155B VOLUME DISCHARGE OF NON-CONDENSIBLES, WATER, AND STEAM WHICH MAY LO LO LO LO LO LO LO LO 2 SEE OCCUR DURING THE PERIOD AFTER SCRAM PRIOR TO VENT VALVE
NOTE 13 CLOSURE AND UPON SCRAM RESET WHEN THE VENT VALVES ARE REOPENED F157C F157D F134A F135A F135B F134C F134D SEE WITH THE SCRAM DISCHARGE VOLUME PRESSURIZED. 1/2" 1/2" NOTE 24.TO PREVENT LOOP SEALS FROM OCCURING IN RELATIVELY SMALL LX F1348 LO LO LO LX F156A F156B 35 DIAMETER LINES OF THE SCRAM DISCHARGE VOLUME VENT AND DRAIN LX LX LX SYSTEM, A CONTINUOUS DOWNWARD PITCH AWAY FROM THE SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES MUST BE MAINTAINED. F158C F158D SEE 2 LX LX THERMAL EXPANSION EFFECTS SHOULD BE ADDRESSED IN THE DESIGN LO TO RPS LO NOTE OF THE VENT AND DRAIN SYSTEMS. (REF.9) 35 C C 25.THE DESIGN OF THE SCRAM DISCHARGE VOLUME, ASSOCIATED VENT, 3/4"E2-2 H13-P691 H13-P692 H13-P693 H13-P694 SCRAM AND DRAIN SYSTEM PIPING AND COMPONENTS MUST CONSIDER THE NC060 NC061 LS LS POTENTIAL PRESSURE, TEMPERATURE, AND TRANSIENT LOADING WHICH LT LS LS LT LIS LIS LT LS LS LT 3/4" 3/4" ELEVATION SEE MAY RESULT FROM: (A) THE DISCHARGE TO THE SCRAM DISCHARGE H51-N601 N601 H51-N602 N602 H51-N601 N601 H51-N013 N013 N012 N012 C D N012 N012 NOTE 29 VOLUME AND DOWN THE VENT AND DRAIN LINE DURING A FULL SCRAM 3/4"E2-2 P1335 A A B B P1336 P1338 C C D D P1339 A B PRIOR TO VENT AND DRAIN VALVE CLOSURE. (B) THE PRESSURIZATION H13-P629 H13-P618 HALF THE OF THE SCRAM DISCHARGE VOLUME TO REACTOR VESSEL PRESSURE INSTRUMENT FOLLOWING VENT AND DRAIN VALVE CLOSURE, AND (C) DEPRESSUR-VOLUME IZATION OF THE SCRAM DISCHARGE VOLUME UPON SCRAM RESET AND H13-P629 H13-P618 OPENING OF THE SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES. 1/2" 12" LIS LIS 12" F157A F157B ROD BLOCK 26.THE F159B VALVE SHALL BE ADJUSTED SO THAT THE F180 VALVE AND
N602 N602 THE F181 VALVE FULLY CLOSE AT LEAST FIVE (5) SECONDS AFTER F091A F091B A B F091C F091D LX LX ELEVATION THE F010 AND F011 VALVES, RESPECTIVELY, DURING A FULL CORE SCRAM. O LX LX LX LX F158A TO RPS F158B INSTRUMENT 27.THE F159A VALVE SHALL BE ADJUSTED SO THAT THE F010 AND F011 H13-LT LT LO (REF.9) LO VALVES START TO OPEN AT LEAST FIVE (5) SECONDS AFTER THE F180 P680 F092A F092B F092C F092D VOLUME AND F181 VALVES, RESPECTIVELY, UPON THE RESET OF A FULL C 1/4" LO LO N017 N017 LO LO SEE 2 CORE SCRAM.
H51-A C C B H51-NOTE 28.INSTRUMENT LOW POINT PIPING TAP LOCATION SHOULD BE 12_ 1/2"E2-2 P1337 P1340 1/2" 3/4"E2-2 35 INCHES ABOVE THE SCRAM DISCHARGE INSTRUMENT VOLUME REFERENCE NC062 NC063 DATUM ELEVATION. 29.THE ELEVATION WITHIN THE SCRAM DISCHARGE INSTRUMENT VOLUME F-5 1" 2 ALARM ELEVATION CORRESPONDING TO THE SCRAM INITIATION SET POINT SHALL BE 302-0872-00000 TO REACTOR PROTECTION TO REACTOR PROTECTION > 8 1/2 INCHES BELOW THE LOWEST ELEVATION OF THE HORIZONTAL_ E1-4 E1-2 C71-1010,SH.3 F103A F103B C71-1010,SH.3 SCRAM DISCHARGE VOLUME ELEVATION. C C SEE NOTE 28 SEE NOTE 28 NOMINAL 5 GALLONS F104A F104B 30.SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVE CONTROL ROOM E2-4 E1-4 NC067 NC066 1/2"E2-2 LX LX 1/2"E2-2 INDICATORS SHALL INDICATE OPEN WHEN BOTH VALVES ARE OPEN AND ROD WITHDRAWL SHALL INDICATE CLOSED WHEN EITHER VALVE IS CLOSED. 2" LO BLOCK LO 2" 31.THE PNEUMATIC PIPING FROM NEEDLE VALVE F159B AND SOLENOID 2" 2"E1-2 2"E1-2 VALVE F009 TO THE VENT AND DRAIN VALVES F181. F011, F180, TO SUPPRESSION POOL F010 SHALL BE ROUTED AND SUPPORTED TO MINIMIZE THE POSSIBILITY SEE NOTES 3, 24 & 25 OF PIPE CRIMP AND ALSO IT SHOULD BE ADEQUATE PIPE THICKNESS F181 F011 AND MATERIAL TO MINIMIZE THE CONSEQUENCES OF PIPE CRIMP. SCRAM DISCHARGE VOLUME PIPING CONTAINMENT 32.HCU MPL NUMBERS CORRESPOND TO CORE GRID CONTROL ROD NUMBERING DESIGNATION. 33.LS 129 MPL NUMBERS CORRESPOND TO N (HCU NUMBER) A. PS 130 MPL NUMBERS CORRESPOND TO N (HCU NUMBER) B. PI 131 MPL NUMBERS CORRESPOND TO R (HCU NUMBER). H13-P601 34.FLOW ELEMENTS 1C11N5840A/B ARE INSTALLED TO MONITOR H13-P601 A RECIRCULATION SEAL PURGE FLOW STABILITY. THESE ELEMENTS D-5 H O MAY BE CONNECTED TO TEMPORARY M&TE FOR DATA COLLECTION. RMS 1" 3/4" 302-0102-00000 H13-P601 35.INSTRUMENTATION CONNECTED TO VALVES 1C11F0155A/B/C/D A H13-P601 S AND 1C11F0158A/B/C/D IS INSTALLED AS SAFETY RELATED, L CONDENSATE C NON-ASME. VENT AND DRAIN VALVES 1C11F156A/B/C/D AND F112B T H13-P601 TRANSFER F402 F510A F510B F403 1C11F157A/B/C/D WERE PROCURED TO ASME SECTION III, CLASS 3/4" dPIS H13-P601 2 REQUIREMENTS.
H51-H51-S N002 RMS 36.THE MANUFACTURE, PROCUREMENT, FABRICATION AND INSTALLATION E OF PIPING AND COMPONENTS SHOWN AS ( ) IS SAFETY RELATED.
REFERENCES:
P1082 P1082 H51-P1081 MATERIALS ARE ASME SECTION II PER GE DESIGN SPECIFICATION
PI PS EC002A 1. 302-0606-00000 NUCLEAR BOILER SYSTEM B21 EC003B RO 22A4168 REV.2. F1042B R017 N001 F1030 E FOLLOWING PROPER ADJUSTMENT THE VALVE (F159A/B) SHALL BE 1" A A PX D007 3/4"L1-4 2 LOCKED INTO POSITION TO MAINTAIN ADMINISTRATIVE CONTROL. 2. 302-0601-00000 REACTOR RECIRCULATION SYSTEM B33 D002B A 3/4" MO EC011 X F083 EC012 3. 302-0101-00000 CONDENSATE SYSTEM N21 TO 1C11C0001A 3/4" C1-4 C2-4 C2-4 C2-2 37. THE L2-4 PIPING BETWEEN THE RESTRICTING ORIFICE 1C11D007A/B CRW 1" 3/4" C1-4 C1-4 AND VALVE 1P11F0506 IS SCHEDULE 80 SEAMLESS PIPE. 4. 302-0612-00000 NUCLEAR CLOSED COOLING WATER SYSTEM P43 1" CRD HYDRAULIC PUMP "A" SCHEMATIC F022A F506A FLOOR EL.574'-10" C0001A F1031 5. 302-0950-00000 NITROGEN SUPPLY SYSTEM P86 F113B 1" 2*" F015A SEE NOTE 16
*" F508A DRIVE WATER 1" F020A F021A G-14 6. 302-0772-00000 REACTOR PLANT SAMPLING SYSTEM P35 F115B EL.574'-10" PUMP C1-4 2" 2" 2 1/2" 2 1/2"C2-4 C2-2 TO F001A f" D020A LO 302-0872-00000 7. A62-4140 CLEANING OF PIPING AND EQUIPMENT D010B 3" PUMP SUCTION CRW S PI D003A F128 8. C11-1020 CONTROL ROD DRIVE HYDRAULIC SYS. PROCESS DIA.
FILTER R008 F503 LX f" MAIN OIL PUMP F0109A H51-DRIVE WATER 2 1/2" 9. C71-1010 REACTOR PROTECTION SYSTEM IED A SUCT PRESS LOW *" P1081 f" L H13-P601 FILTER 3/4" 3/4" SEE 4" 4" 10. C11-4010 CONTROL ROD DRIVE HYDRAULIC SYS. DESIGN SPEC. NOTE 22 SHAFT POSITIVE F401 F129 F112A DRIVENC5001A C1-4 3/4"L1-4 F021B F504 11. 302-0872-00000 CONTROL ROD DRIVE HYDRAULIC SYSTEM DIAGRAM PRESSURE SEAL LX F1046A LINE F023A 12. C11-1030 CONTROL ROD DRIVE HYDRAULIC SYSTEM FCD
RMS AUX. OIL PUMP F509 H-13 F123 4"L1-4 F115A D002A F114A H13-P601 C1-4 L1-4 13. 302-0102-00000 CONDENSATE TRANSFER AND STORAGE SYSTEM P11 302-0101-00000 *" 3/4"L1-4 2 1/2" 3/4" 14. A62-4240 WATER SAMPLING CONDENSATE S TO F1042A 15. C11-D001 HCU OUTLINE DRAWING 1" T C1-4 CRW F1038A F511A S TI 16. A62-1010 GROUP CLASS 8 CONTAINMENT ISOLATION DIAGRAM F013B M ELEC. H13-P601 C1-4 C2-4 MOTOR R0709 17. C11-1050 ROD CONTROL AND INFO SYSTEM 1" A F022B 3/4" (J-7) *" 18. 302-0671-00000 REACTOR WATER CLEANUP SYSTEM G33 H13-P601 f" F113A 1" C0002A F1036A P43 302-0612-00000 f" PI F020B
dPIS EL.574'-10" NCC 2" 2" 2 1/2" C2-4 A 302-0612-00000 R0706 H N015 CRW (J-7) D010A A LOW OIL (REV. 20 10/2017) H51-PUMP SUCTION PRESSURE D003B P1122 PS A DRIVE WATER FILTER F0071A F0070A L
*" N0705 F117 D013 F116 A H13-P601 FILTER
*" *" f" C1-4 3/4"L1-4 PS GEAR REDUCER "A" LUBE OIL SCHEMATIC F511B 3/4" F0017 N0704 F023B LOCATED ON 1C11C0001A PUMP SKID PERRY NUCLEAR POWER PLANT THRUST PUMP TO/FROM PUMP RADIAL BEARING SEAL PUMP SEAL BEARING A C1-4 L1-4 FLOOR EL.574'-10" FOR FOR STATION FOR FOR C0001B C0001A F1037A 10 CENTER RD., PERRY, OHIO 44081 C0001A C0001A C0001A PS TO GEAR '" N0703 REDUCER CRW A
HIGH SEAL LEAKAGE PS SHAFT DRIVEN A OIL PUMP H SIGHT CONTROL ROD DRIVE HYDRAULIC N0702A GAUGE (PARENT FLC# H13-P601 1C11C0001A) (TYP.3) F1039A F F TI 1C11A5006A CRD PUMP LUBE OIL SUMP F SYSTEM D5004A D5005A R0707 D5009A A DRW RO
D007 PI f" FIGURE 4.6-5 (SHEET 1 OF 2) B GEAR REDUCER "B" LUBE OIL SCHEMATIC (J-7) f" R0708 R0017B (H51-P1082)F0507BB5003BD0020BF1046B LOCATED ON 1C11C0001B PUMP SKID CRD HYDRAULIC PUMP "B" SCHEMATIC N0001B (H51-P1082)F0508BN0702BF0506BN0705B 2*" 302-0612-00000 A SAME CONFIGURATION AS PUMP "A" SAME CONFIGURATION AS "A" P43 C0001B F0001B R0709B A5006B N0704B F015B NCC FLOOR EL.574'-10" F0109B C0002B R0706B F1036B N0703B 2" C1-4 C1-4 1" FLOOR EL.574'-10" D5009BB5008B 302-0612-00000 C5001B F1034B F0070B F0071B F1037BR0707B (DWG. 302-0871-00000) (K-7) F1035B D5004B LO F1039BR0708B F1038B D5005B DRYWELL
TO ROD POSITION DRYWELL INFO. SYSTEM VENT ( SEE FCD ) POS
X 2 LOGIC CHANNEL A A-3/A-4 TE HYDRAULIC CONTROL UNIT - TYPICAL 177 - MPL NO. D001 (EL.620'- 6") LOGIC CHANNEL B A-8/A-9 NE 116 1/2" X F102XX ( SEE NOTES 4 & 18 ) TO REACTOR S S -871 PROTECTION SYSTEM 139 (HCU IDENTIFICATION NUMBERS FOR INFORMATION ONLY. SEE NOTE 32) ( C71-1010,SH.1 ) SCRAM VALVE PILOT AIR HEADER
FROM C2-2 OTHER SEE NOTE 36 DRIVES EXHAUST 1"C2-2 DRIVE WATER 102
( WITHDRAW ) LO
2 ROD STATUS TEMPERATURE F101XX ( SEE NOTES 4 & 18 ) DISPLAY BOARD
RECORDER SEE NOTE 36 AND SCANNER E1-2
POS C2-2 R018 X H22-P007 CRD 123
1 1/4"C2-2 DRIVE WATER 101 ND 122 ND 112 D-6/E-11 1" -871
A ( INSERT ) 127 114 LO 3/4" H S S TO SCRAM DISCHARGE HEADER H13-P601 SEE 2 2 NOTE 36 2
POS SEE NOTE 36 WITHDRAW SEE NOTE 36 X SEE NOTE 36
INSERT SEE FROM ROD CONTROL AND CONTROL ROD DRIVE NOTE 36 SETTLE INFORMATION SYSTEM ( TYPICAL ) WITHDRAW
126 INSERT
H13-P629 107 PI H O DRAIN 2 S S PS 131 ND ND HIGH POINT
N655 N VENT A 2 121 111 TO HCU'S BANKS C & D AT 270O 3/4" H13-P629 115 138 137 1/2" 120 F414 1/2" PT PIS PSL LS H51-P1140 H N054 N654 130 129 1/2" A A 113 104 103 105 1/2" 3/4" SEE NOTE 6 3/4" 1" 1"
D-302-012 SEE NOTE 33 132 F-11 SEE NOTE 36 SEE NOTE 36 H13-P629 1/2" TO HCU'S BANKS USE REDUCER BEFORE 1/2" C & D AT 270O THIRD TO LAST HCU
PT PIS 1/2" H51-P1140 N054 N654 C C H 1/2" TO HCU'S BANKSO D-302-012 SEE NOTE 4 1/2" 1/2" 1 1/2" 1 1/2" 1/2" A & B AT 90
F-11F-11 1/2" A L 1/2" TO HCU'S (TYP) PIS FOR ROD CONTROL SEE NOTE 19 1/2" TO HCU'S SEE AND INFORMATION TO HCU'S (TYP) 208-0020-00003 E51 SYSTEM C11-1050 3/4" -950 1/2" 1/2" F415 N600 D-2/F-2 ROD STATUS FROM OTHER F530D SEE NOTE 4 3/4" H13-P618 3/8"IPC-6 1/2" 1/2" F529 DISPLAY BOARD HCU'S NITROGEN 1" 3/4" HIGH POINT SUPPLY PT PIS VENT H51-P1141 -607 2" 2" 2" A-3 N054 N654 D D G-8 F541D -607 1"C2-4 D-302-012 1" FI F-14 3/8"IPC-6 F407D F521D H13-P618 DETAIL "A" PI 3/4" F054D R605 PRESSURE D-3 G-12 SEE NOTE 7 SEE DETAIL "A" F151 EQ. VALVE F152 PT R006 1" 1" PIS -607 -607 D H51-P1141 F408D F524D F525D F525B N054 N654 F541B F541C 3/8" 3/8" LO F150A LO B B 3/8"IPC-6 3/8"IPC-6 C B A E E FI FT FE FT FE D-302-012 F409D F523D EA006 F-14 EA002A R003 N007 3/8" N006 N009 3/8" F525C F525A N010 3/4" F520 F416 PI 3/4"F412 F411 PI EA003B D D D
PS PI EA004C R007 C11P001 R010 EA005D 3/4" R601 F406 F515 1/2" X 3/8" (TYP) 1/2" X 3/8"(TYP) N655 PI 3/4" FI 1"C2-4 DRIVE WATER PRESSURE C11P001 B 3/4" X 1/2" (TYP) 3/4" EQ. VALVE R016 R604 3/4" X 1/2"(TYP) 3/4" F154 F153 H13-P618 A D 1"C2-4 DRIVE WATER 1" L C2-4 1"C2-4 DRIVE WATER H13-P601 F034 3/4" DRIVE 3/4" LO F150B LO 1" PS PI WATER
N600 R015 F004 RO SEE 1 1/2" 2" 3/4" D008 NOTE 12 1 1/2" 2" 3/4" 1"E1-4 F-13 2"C2-4 3/4" IN-LINE FE D -871 F1029 F410 RELIEF PT F405 F514 N016 TO 3/4" VALVE SUPPRESSION E F012 3/4" F040 F062 N005 1 1/2" 1" POOL EAO11
3/4" 1 1/2" LO 3/4" 3/4"
1 1/2" FUEL CONTAINMENT 2" E F537 F538 RMS H13-P601 BUILDING A-9 SEE EC009 F1032 REACTOR PLANT F036 NOTE 7 EC010 C2-4E1-4 2 -772 SAMPLING FE 3/4" O N003 H13-P601 MCV F016 C2-2 C2-4 F1033 F124 F003 1 1/2" C H-3 F130 AP-229 SEE NOTE 17 F046A F047A M LO C2-2 2 1/2" 1/2" 2"C2-4 2" 1 1/2" FCV 1 1/2"C2-4 1 1/2" 1 1/2"
-871
F122 F060 F061 F069 2" LO PEN# SEE F131 F522A F522B 3/4" P204 NOTE 16 H13-C F127A
3/4" 1/2" 1/2" P601 O
1"
F132 F522C F522D 3/4" DETAIL "B" F067A 1/4" F526D F526B A 3/4" 3/4" 3/4" 3/8" 3/4" PFV F067D FI 1 1/2" FI FE F002 S F526C F526A R019 FT E A 1/4" R004 3/8" N014 3/4"C2-4 E
N004 EA001 F126A EC015 F540 F404 EC016 3/4" PI D004A F007D 1/2" X 3/8"(TYP) F149A F145A R021 FILTER FI F X 3/4" X 1/2"(TYP) F144A S PI PI PCV SEE DETAIL "B" R606 F140 F143A F146A F147A X X X F148A F125A CRD AUTO LOADING MANUAL LOADING 3/4"
F149B D004B SYSTEM MANUAL/AUTO STATION D009A STABILIZING F142 F145B C FLOW VALVE C B A PI FILTER R5840 MA001 SEE NOTE 1 D
F143B F144B F146B F147B K001 3/4"
FC 3/4" 3/4" 3/4" 3/4" 3/4" F141 F148B I/P
f" C2-4 R600 F518A dPI F517A F068D F068A C2-4 E1-4 R603 FLOW REGULATOR 3/4" MANUAL/AUTO STATION D009B NOTES: F025B D AUTO LOADING MANUAL LOADING
RO F125B FOR NOTES AND REFERENCES, SEE DRAWING 302-0871-00000. PI PI PCV dPT dPI 1" dPT dPI D011 D012 D0021B BLANK B B 3/4" X X X N008 R602 N011 R005 SEE NOTE 34 F126B C11-1030 F026B F024B G-13 3/4" FI FE FOR PUMP "B" dPI E E
-601 R020 N5840 EA007 B B R009 EA008 F518B C2-4 E1-4 (REV. 22 10/2021) 1/4" PFV FLOW REGULATOR E F002 F517B REACTOR PRESS. SENSING LINE F-14 F025A B A 3/4"C2-4 (SEE NOTE 2) 3/4" EC007 -606 RO EC008
D0021A BLANK D011 D012 3/4" A A SEE NOTE 34 H13-O PERRY NUCLEAR POWER PLANT F026A F024A G-13 P601 F127B DRIVE WATER PRESSURE CONTROL STATION C11P001 FI FE C 1/4"
-601 FOR PUMP "A" 10 CENTER RD., PERRY, OHIO 44081
R020 N5840 A A PI 1 1/2" REACTOR RECIRCULATION PUMP SEAL PURGE SUPPLY R012 F039 F046B FCV F047B
FILTER REGULATOR 3/4"
F516 CONTROL ROD DRIVE 120 PSIG 1/4" F038 INSTRUMENT 1/4" 1/4"
AIR SUPPLY
F 1/2" HYDRAULIC SYSTEM
30PSIG FLOW CONTROL STATION C11P002
FILTER D005 FIGURE 4.6-5 (SHEET 2 OF 2) 75-80 PSIG INSTRUMENT AIR SUPPLY
1/2" 1/2"
-871 (DWG. D-302-0872-00000)
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